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Sample records for bruce nuclear generating

  1. AECB staff annual assessment of the Bruce B 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 reactor safety at the Bruce Nuclear Generating Station B for 1996. It was concluded that Ontario Hydro operated Bruce B safely in 1996. Although the Bruce B plant is safe,it was noted that the number of outages and the number of secondary and tertiary equipment failures during reactor unit upsets increased. Ontario Hydro needs to pay special attention to prevent such a decrease in the safety performance at Bruce B

  2. AECB staff annual assessment of the Bruce A Nuclear Generating Station for the year 1995

    International Nuclear Information System (INIS)

    1996-06-01

    The Atomic Energy Control Board conducts a staff assessment of safety at Bruce Nuclear Generating Station A for 1995. On-site Project Officers and Ottawa based specialists monitored the station throughout the year. Ontario Hydro operated Bruce A safely in 1995, maintaining the risk to workers and the public at an acceptably low level. Radiation doses to workers and releases to the environment were well below regulatory limits. However, Ontario Hydro must improve contamination control at Bruce A. Special safety system performance a Bruce A was less than adequate. The negative pressure containment system and units 4's shutdown system two exceeded unavailability targets in 1995. However, we are satisfied Ontario Hydro is taking appropriate action to correct this. 5 tabs., 5 figs

  3. AECB staff annual assessment of the Bruce A 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 reactor safety at the Bruce Nuclear Generating Station A for 1996. Ontario Hydro operated Bruce A safely in 1996, maintaining the risk to workers and the public at an acceptably low level. Special safety system performance at Bruce A was adequate. Availability targets were all met. Improvement is needed to reduce the number of operating licence non-compliances

  4. The Bruce nuclear project

    International Nuclear Information System (INIS)

    Rose, J.B.

    1981-01-01

    This case study assesses the industrial relations impact of the construction of the Bruce Nuclear Power Development. It examines the labour relations system in the Ontario electric power sector and in major building construction. Industrial relations problems and practices at the Bruce project are reviewed. The focus of the study is on the relationship between the project and the rest of the Ontario industrial construction industry

  5. AECB staff annual assessment of the Bruce B Nuclear Generating Station for the year 1994

    International Nuclear Information System (INIS)

    1995-06-01

    AECB staff believes Ontario Hydro operated Bruce B safely in 1994. The Bruce B reactors will remain limited to 88% full power until Ontario Hydro is able to demonstrate that it is safe to operate at higher powers. Ontario Hydro's compliance with AECB regulations and the Operating Licence was satisfactory. AECB found no major violations. The station performance was similar to previous years. Radiation doses to workers and the public were well below the legal limits and also remained below Ontario Hydro's internal targets. Worker radiation doses increased slightly but were comparable to previous years. Inspection of pressure tubes and steam generator tubes by Ontario Hydro showed continuing tube degradation. However, we believe that Ontario Hydro made progress in correcting and managing these problems. Ontario Hydro carried out a full-scale fire drill at Bruce B in 1994. AECB witnessed the drill and were pleased to observe a significant improvement in the station's fire-fighting capability. 7 tabs., 4 figs

  6. Review of Ontario Hydro Pickering 'A' and Bruce 'A' nuclear generating stations' accident analyses

    International Nuclear Information System (INIS)

    Serdula, K.J.

    1988-01-01

    Deterministic safety analysis for the Pickering 'A' and Bruce 'A' nuclear generating stations were reviewed. The methodology used in the evaluation and assessment was based on the concept of 'N' critical parameters defining an N-dimensional safety parameter space. The reviewed accident analyses were evaluated and assessed based on their demonstrated safety coverage for credible values and trajectories of the critical parameters within this N-dimensional safety parameter space. The reported assessment did not consider probability of occurrence of event. The reviewed analyses were extensive for potential occurrence of accidents under normal steady-state operating conditions. These analyses demonstrated an adequate assurance of safety for the analyzed conditions. However, even for these reactor conditions, items have been identified for consideration of review and/or further study, which would provide a greater assurance of safety in the event of an accident. Accident analyses based on a plant in a normal transient operating state or in an off-normal condition but within the allowable operating envelope are not as extensive. Improvements in demonstrations and/or justifications of safety upon potential occurrence of accidents would provide further assurance of adequacy of safety under these conditions. Some events under these conditions have not been analyzed because of their judged low probability; however, accident analyses in this area should be considered. Recommendations are presented relating to these items; it is also recommended that further study is needed of the Pickering 'A' special safety systems

  7. 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

  8. Design and verification of computer-based reactor control system modification at Bruce-A candu nuclear generating station

    International Nuclear Information System (INIS)

    Basu, S.; Webb, N.

    1995-01-01

    The Reactor Control System at Bruce-A Nuclear Generating Station is going through some design modifications, which involve a rigorous design process including independent verification and validation. The design modification includes changes to the control logic, alarms and annunciation, hardware and software. The design (and verification) process includes design plan, design requirements, hardware and software specifications, hardware and software design, testing, technical review, safety evaluation, reliability analysis, failure mode and effect analysis, environmental qualification, seismic qualification, software quality assurance, system validation, documentation update, configuration management, and final acceptance. (7 figs.)

  9. Optimizing the use of operating experience at Ontario Hydro's Bruce Nuclear Generating Station 'A'

    International Nuclear Information System (INIS)

    Williams, E.L.

    1991-01-01

    One of the most significant lessons learned from the Three Mile Island event (March 1979), and again with the Chernobyl disaster - (April 1986) was the ongoing requirement to learn from our mistakes and near misses, and those of our fellow utilities around the world: so that as an industry we do not repeat the same mistakes. The very future of our industry will depend on how well each one of us accomplishes this important ask. This paper describes in detail the challenges encountered by one station when incorporating a comprehensive 'Operating Program'. It begins with the Corporate Office's directives to its stations for such a program; and follows up with the details of the actual station implementation of the program, and day to day operating experiences. The paper describes in detail the following Operating Experience programs: - Root Cause Determination process. The Institute of Nuclear Power Operations, Human Performance Enhancement System (HPES) as an integral component of the Root Cause process. Finding solutions for our station for problems identified elsewhere is covered herein; - Significant Event Recommendation Tracking System: - Commitment Tracking System; - Operating Experience (Sharing Lessons Learned) System. The paper will show all the above processes tie closely together and complement each other. The paper discusses the staff required for such processes and their training requirements. It recommends process time lines, reporting mechanisms, and sign off requirements. It will describe the equipment utilized to carry out this work effectively, and with a minimum of staff. One unique feature of the Bruce 'A' system is an 'Effectiveness Follow-Up', usually three to six months after the event recommendations have been completed. By rechecking the finished actions and reviewing them with the personnel involved with the originating event we ensure that the real root causes have been identified and resolved. (author)

  10. Optimizing the use of operating experience at Ontario Hydro's Bruce Nuclear Generating Station 'A'

    Energy Technology Data Exchange (ETDEWEB)

    Williams, E L [Operating Experience Reactor Safety, Bruce Nuclear Generating Station ' A' , Ontario Hydro, Tiverton, Ontario (Canada)

    1991-04-01

    One of the most significant lessons learned from the Three Mile Island event (March 1979), and again with the Chernobyl disaster - (April 1986) was the ongoing requirement to learn from our mistakes and near misses, and those of our fellow utilities around the world: so that as an industry we do not repeat the same mistakes. The very future of our industry will depend on how well each one of us accomplishes this important ask. This paper describes in detail the challenges encountered by one station when incorporating a comprehensive 'Operating Program'. It begins with the Corporate Office's directives to its stations for such a program; and follows up with the details of the actual station implementation of the program, and day to day operating experiences. The paper describes in detail the following Operating Experience programs: - Root Cause Determination process. The Institute of Nuclear Power Operations, Human Performance Enhancement System (HPES) as an integral component of the Root Cause process. Finding solutions for our station for problems identified elsewhere is covered herein; - Significant Event Recommendation Tracking System: - Commitment Tracking System; - Operating Experience (Sharing Lessons Learned) System. The paper will show all the above processes tie closely together and complement each other. The paper discusses the staff required for such processes and their training requirements. It recommends process time lines, reporting mechanisms, and sign off requirements. It will describe the equipment utilized to carry out this work effectively, and with a minimum of staff. One unique feature of the Bruce 'A' system is an 'Effectiveness Follow-Up', usually three to six months after the event recommendations have been completed. By rechecking the finished actions and reviewing them with the personnel involved with the originating event we ensure that the real root causes have been identified and resolved. (author)

  11. Experience in ultrasonic gap measurement between calandria tubes and liquid injection shutdown systems nozzles in Bruce Nuclear Generating Station

    International Nuclear Information System (INIS)

    Abucay, R.C.; Mahil, K.S.; Goszczynski, J.J.

    1995-01-01

    The gaps between calandria tubes (CT) and Liquid Injection Shutdown System (LISS) nozzles at the Bruce Nuclear Generating Station ''A'' (Bruce A) are known to decrease with time due to radiation induced creep/sag of the calandria tubes. If this gap decreases to a point where the calandria tubes come into contact with the LISS nozzle, the calandria tubes could fail as a result of fretting damage. Proximity measurements were needed to verify the analytical models and ensure that CT/LISS nozzle contact does not occur earlier than predicted. The technique used was originally developed at Ontario Hydro Technologies (formerly Ontario Hydro Research Division) in the late seventies and put into practical use by Research and Productivity Council (RPC) of New Brunswick, who carried out similar measurements at Point Lepreau NGS in 1989 and 1991. The gap measurement was accomplished y inserting an inspection probe, containing four ultrasonic transducers (2 to measure gaps and 2 to check for probe tilt) and a Fredericks electrolytic potentiometer as a probe rotational sensor, inside LISS Nozzle number-sign 7. The ultrasonic measurements were fed to a system computer that was programmed to convert the readings into fully compensated gaps, taking into account moderator heavy water temperature and probe tilt. Since the measured gaps were found to be generally larger than predicted, the time to CT/LISS nozzle contact is now being re-evaluated and the planned LISS nozzle replacement will likely be deferred, resulting in considerable savings

  12. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro's Bruce Nuclear Generating Station 'A'

    International Nuclear Information System (INIS)

    Day, J.E.; Baker, R.L.

    1995-01-01

    Ontario Hydro at the Bruce Nuclear Generating Station 'A' has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

  13. Power raise through improved reactor inlet header temperature measurement at Bruce A Nuclear Generation Station

    International Nuclear Information System (INIS)

    Basu, S.; Bruggemn, D.

    1997-01-01

    Reactor Inlet Header (RIH) temperature has become a factor limiting the performance of the Ontario Hydro Bruce A units. Specifically, the RIH temperature is one of several parameters that is preventing the Bruce A units from returning to 94% power operation. RIH temperature is one of several parameters which affect the critical heat flux in the reactor channel, and hence the integrity of the fuel. Ideally, RIH temperature should be lowered, but this cannot be done without improving the heat transfer performance of the boilers and feedwater pre-heaters. Unfortunately, the physical performance of the boilers and pre-heaters has decayed and continues to decay over time and as a result the RIH temperature has been rising and approaching its defined limit. With an understanding of the current RIH temperature measurement loop and methods available to improve it, a solution to reduce the measurement uncertainty is presented

  14. Preventive maintenance: optimization of time - based discard decisions at the bruce nuclear generating station

    International Nuclear Information System (INIS)

    Doyle, E.K.; Jardine, A.K.S.

    2001-01-01

    The use of various maintenance optimization techniques at Bruce has lead to cost effective preventive maintenance applications for complex systems. As previously reported at ICONE 6 in New Orleans, 1996, several innovative practices reduced Reliability Centered Maintenance costs while maintaining the accuracy of the analysis. The optimization strategy has undergone further evolution and at the present an Integrated Maintenance Program (IMP) is in place where an Expert Panel consisting of all players/experts proceed through each system in a disciplined fashion and reach agreement on all items under a rigorous time frame. It is well known that there are essentially 3 maintenance based actions that can flow from a Maintenance Optimization Analysis: condition based maintenance, time based maintenance and time based discard. The present effort deals with time based discard decisions. Maintenance data from the Remote On-Power Fuel Changing System was used. (author)

  15. AECB staff annual assessment of the Bruce A Nuclear Generating Station for the year 1994

    International Nuclear Information System (INIS)

    1995-06-01

    AECB believe that Ontario Hydro operated Bruce A in a safe manner during 1994, and that the risk to workers and the public has been maintained at an acceptably low level. Radiation doses to workers and releases to the environment were well below regulatory limits. All special safety systems met availability targets. We noted improvements in operation and maintenance but some further improvements are still required. This is particularly true of the station's compliance with the Operating Licence. AECB believe that the station continues to be well managed, with a high priority placed on safety. However, there is a need for increased capability in the area of safety analysis and assessment. 4 tabs., 4 figs

  16. Steam generator tubesheet waterlancing at Bruce B

    Energy Technology Data Exchange (ETDEWEB)

    Persad, R. [Babcock and Wilcox Canada, Cambridge, Ontario (Canada); Eybergen, D. [Bruce Power, Tiverton, Ontario (Canada)

    2006-07-01

    High pressure water cleaning of steam generator secondary side tubesheet surfaces is an important and effective strategy for reducing or eliminating under-deposit chemical attack of the tubing. At the Bruce B station, reaching the interior of the tube bundle with a high-pressure water lance is particularly challenging due to the requirement to setup on-boiler equipment within the containment bellows. This paper presents how these and other design constraints were solved with new equipment. Also discussed is the application of new high-resolution inter-tube video probe capability to the Bruce B steam generator tubesheets. (author)

  17. Implementation of a radiological emergency monitoring system for Bruce Power nuclear power plant (Canada); Implementierung eines radiologischen Umgebungsueberwachungsmesssystems fuer das Kernkraftwerk Bruce Power (Kanada)

    Energy Technology Data Exchange (ETDEWEB)

    Madaric, M. [Saphymo GmbH, Frankfurt (Germany)

    2016-07-01

    The Bruce Power nuclear power plant (BP NPP) in Ontario, Canada, is the largest nuclear generating station in the world, operating 8 nuclear reactors producing 6300 MW. In correlation with Bruce Power's safety culture, ''Safety first'' and continuous improvements are essential and substantial parts of the Bruce Power philosophy and management system. After the Fukushima nuclear accident the existing radiological emergency monitoring was analyzed and improved.

  18. Ontario Hydro's operating experience with steam generators with specifics on Bruce A and Bruce B problems

    Energy Technology Data Exchange (ETDEWEB)

    Eatock, J W; Patterson, R W [Ontario Hydro, Toronto, ON (Canada); Dyck, R W [Ontario Hydro, Central Production Services Division, Toronto, ON (Canada)

    1991-04-01

    The performance of the steam generators in Ontario Hydro nuclear power stations is reviewed. This performance has generally been outstanding compared to world averages, with very low tube failure and plugging rates. Steam generator problems have made only minor contributions to Ontario Hydro nuclear station incapability factors. The mechanisms responsible for the the observed tube degradation and failures are described. The majority of the leaks have been due fatigue in the U-bend of the Bruce 'A' steam generators. There have been very few failures attributed to corrosion of the three tube materials used in Ontario Hydro steam generators. Recent performance has been deteriorating primarily due to deposit accumulation in the steam generators. Plugging of the broached holes in the upper support plates at Bruce 'A' has caused some derating of two units. Increases have been observed in the primary heat transport system reactor inlet temperature of several units. These increases may be attributed to steam generator tube surface fouling. In addition, several units have accumulated deep, hard sludge piles on the tube sheet, although little damage been observed. Recently some fretting of tubes has been observed at BNGSB in the U-bend support region. Remedial measures are being taken to address the current problems. Solutions are being evaluated to reduce the generation of corrosion products in the feedtrain and their subsequent transport to the steam generators. (author)

  19. Ontario Hydro's operating experience with steam generators with specifics on Bruce A and Bruce B problems

    International Nuclear Information System (INIS)

    Eatock, J.W.; Patterson, R.W.; Dyck, R.W.

    1991-01-01

    The performance of the steam generators in Ontario Hydro nuclear power stations is reviewed. This performance has generally been outstanding compared to world averages, with very low tube failure and plugging rates. Steam generator problems have made only minor contributions to Ontario Hydro nuclear station incapability factors. The mechanisms responsible for the the observed tube degradation and failures are described. The majority of the leaks have been due fatigue in the U-bend of the Bruce 'A' steam generators. There have been very few failures attributed to corrosion of the three tube materials used in Ontario Hydro steam generators. Recent performance has been deteriorating primarily due to deposit accumulation in the steam generators. Plugging of the broached holes in the upper support plates at Bruce 'A' has caused some derating of two units. Increases have been observed in the primary heat transport system reactor inlet temperature of several units. These increases may be attributed to steam generator tube surface fouling. In addition, several units have accumulated deep, hard sludge piles on the tube sheet, although little damage been observed. Recently some fretting of tubes has been observed at BNGSB in the U-bend support region. Remedial measures are being taken to address the current problems. Solutions are being evaluated to reduce the generation of corrosion products in the feedtrain and their subsequent transport to the steam generators. (author)

  20. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro's Bruce nuclear generating station open-quotes Aclose quotes

    International Nuclear Information System (INIS)

    Day, J.E.; Baker, R.L.

    1994-01-01

    Ontario Hydro at the Bruce Nuclear Generating Station open-quotes Aclose quotes has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

  1. Primary separator replacement for Bruce Unit 8 steam generators

    International Nuclear Information System (INIS)

    Roy, S.B.; Mewdell, C.G.; Schneider, W.G.

    2000-01-01

    During a scheduled maintenance outage of Bruce Unit 8 in 1998, it was discovered that the majority of the original primary steam separators were damaged in two steam generators. The Bruce B steam generators are equipped with GXP type primary cyclone separators of B and W supply. There were localized perforations in the upper part of the separators and large areas of generalized wall thinning. The degradation was indicative of a flow related erosion corrosion mechanism. Although the unit- restart was justified, it was obvious that corrective actions would be necessary because of the number of separators affected and the extent of the degradation. Repair was not considered to be a practical option and it was decided to replace the separators, as required, in Unit 8 steam generators during an advanced scheduled outage. GXP separators were selected for replacement to minimize the impact on steam generator operating characteristics and analysis. The material of construction was upgraded from the original carbon steel to stainless steel to maximize the assurance of full life. The replacement of the separators was a first of a kind operation not only for Ontario Power Generation and B and W but also for all CANDU plants. The paper describes the degradations observed and the assessments, the operating experience, manufacture and installation of the replacement separators. During routine inspection in 1998, many of the primary steam separators in two of steam generators at Bruce Nuclear Division B Unit 8 were observed to have through wall perforations. This paper describes assessment of this condition. It also discusses the manufacture and testing of replacement primary steam separators and the development and execution of the replacement separator installation program. (author)

  2. Chemical cleaning of the Bruce A steam generators

    International Nuclear Information System (INIS)

    Le Surf, J.E.; Mason, J.B.; Symmons, W.R.; Yee, F.

    1992-01-01

    Deposits consisting mostly of oxides and salts and copper metal in the secondary side of the steam generators at the Bruce A Nuclear Generating Station have caused instability in the steam flow and loss of heat capacity, resulting in derating of the units and reduction in power production. Attempts to remove the deposits by pressure pulsing were unsuccessful. Water lancing succeeded in restoring stability, but restrictions on access prevented complete lancing of the tube support plate holes. Chemical cleaning using a modified EPRI-SGOG process has been selected as the best method of removing the deposits. A complete chemical cleaning system has been designed and fabricated for Ontario Hydro by Pacific Nuclear, with support from AECL CANDU and their suppliers. The system consists of self contained modules which are easily interconnected on site. The whole process is controlled from the Control Module, where all parameters are monitored on a computer video screen. The operator can control motorized valves, pumps and heaters from the computer key board. This system incorporates all the advanced technologies and design features that have been developed by Pacific Nuclear in the design, fabrication and operation of many systems for chemical decontamination and cleaning of nuclear systems. 2 figs

  3. Clean energy for a new generation. Steam generator life cycle management and Bruce restart

    International Nuclear Information System (INIS)

    Newman, G.W.

    2009-01-01

    In the mid to late 1990s, Ontario Hydro decided to lay-up and write-down the Bruce A Nuclear Reactors. Upon transition to Bruce Power L.P., Canada's first and only private nuclear operator, new life and prospects were injected into the site, local economy and the provincial energy portfolio. The first step in this provincial power recovery initiative involved restart of Bruce Units 3 and 4 in the 2003/04 time-frame. Units 3 and 4 have performed beyond expectation during the last five-year operating interval. A combination of steam generator and fuel channel issues precluded a similar restart of Units 1 and 2. Enter the refurbishment of Bruce Units 1 and 2. This first-of-a-kind undertaking within the Canadian nuclear power industry is testament to the demonstrated industry leadership by Bruce Power L.P., their investors and the significant vendor community contribution that is supporting this major power infrastructure enhancement. Initiated as a 'turn-key' project solution separated from the operating units, this major refurbishment project has evolved to a fully managed in-house refurbishment project with the continued support from the broader vendor community. As part of this first-of-kind undertaking, Bruce Power L.P. is in the process of accomplishing such initiatives as a complete fuel channel re-tube (i.e. full core calandria and pressure tube replacement), replacement of all boilers (i.e. 16 in total) and the majority of feeder pipe replacement. Complimentary major upgrades and replacement of the remainder of plant equipment including both nuclear and non-nuclear valves, heat exchangers, electrical infrastructure, service water systems and components, all while meeting a parallel evolving/maturing regulatory environment related to achieving compliance with IAEA derived modern codes and standards. Returning to ground level, boiler replacement is a key part of the refurbishment undertaking and this further reflected a meeting of the 'old' and the 'new'. Pre

  4. Stress corrosion cracking experience in steam generators at Bruce NGS

    International Nuclear Information System (INIS)

    King, P.J.; Gonzalez, F.; Brown, J.

    1993-01-01

    In late 1990 and through 1991, units 1 and 2 at the Bruce A Nuclear Generating Station (BNGS-A) experienced a number of steam generator tube leaks. Tube failures were identified by eddy current to be circumferential cracks at U-bend supports on the hot-leg side of the boilers. In late 1991, tubes were removed from these units for failure characterization. Two active failure modes were found: corrosion fatigue in both units 1 and 2 and stress corrosion cracking (SCC) in unit 2. In unit 2, lead was found in deposits, on tubes, and in cracks, and the cracking was mixed-mode: transgranular and intergranular. This convincingly indicated the involvement of lead in the stress corrosion cracking failures. A program of inspection and tube removals was carried out to investigate more fully the extent of the problem. This program found significant cracking only in lead-affected boilers in unit 2, and also revealed a limited extent of non-lead-related intergranular stress corrosion cracking in other boilers and units. Various aspects of the failures and tube examinations are presented in this paper. Included is discussion of the cracking morphology, measured crack size distributions, and chemical analysis of tube surfaces, crack faces, and deposits -- with particular emphasis on lead

  5. Bruce nuclear power development (BNPD) postoperational aquatic studies

    International Nuclear Information System (INIS)

    Carey, W.E.

    1984-01-01

    This report summarizes the results of three years of postoperational aquatic study conducted between 1979 and 1981 at the Bruce Nuclear Power Development site. An increase in the rate of organic and inorganic sedimentation during the summer was noted, and was possibly related to construction activity at the Bruce GS 'B' intake site. Vertical thermal stratification persisted later in the year at the 7 m contour of Bruce GS 'A' discharge than at other locations sampled. Water quality conditions reflected the oliogtrophic state of Lake Huron. Several changes were noted in the biotic community. The taxonomic composition of attached algae, zooplankton and benthic macroinvertebrates varied between sampling years. The number of common naids, amphipods and the trichopteran Cheumatopsyche increased substantially in the 1981 rock cage collections. The relative abundance of adult walleye, channel catfish and round whitefish in gill nets increased, with the former two species being more abundant (15 fish per net in September, 1980, and 33 fish per net in July, 1981, respectively) at the 3 m contour of the Bruce GS 'A' discharge transect than at other shoreline sampling locations

  6. Steam generator leak detection at Bruce A Unit 1

    International Nuclear Information System (INIS)

    Maynard, K.J.; McInnes, D.E.; Singh, V.P.

    1997-01-01

    A new steam generator leak detection system was recently developed and utilized at Bruce A. The equipment is based on standard helium leak detection, with the addition of moisture detection and several other capability improvements. All but 1% of the Unit 1 Boiler 03 tubesheet was inspected, using a sniffer probe which inspected tubes seven at a time and followed by individual tube inspections. The leak search period was completed in approximately 24 hours, following a prerequisite period of several days. No helium leak indications were found anywhere on the boiler. A single water leak indication was found, which was subsequently confirmed as a through-wall defect by eddy current inspection. (author)

  7. Steam generator replacement in Bruce A Unit 1 and Unit 2

    International Nuclear Information System (INIS)

    Hart, R.S.

    2006-01-01

    The Bruce A Generating Station consists of four 900 MW class CANDU units. The reactor and Primary Heat Transport System for each Unit are housed within a reinforced concrete reactor vault. A large duct running below the reactor vaults accommodates the shared fuel handling system, and connects the four reactor vaults to the vacuum building. The reactor vaults, fuelling system duct and the vacuum building constitute the station vacuum containment system. Bruce A Unit 2 was shut down in 1995 and Bruce A Units 1, 3 and 4 were shutdown in 1997. Bruce A Units 3 and 4 were returned to service in late 2003 and are currently operating. Units 1 and 2 remain out of service. Bruce Power is currently undertaking a major rehabilitation of Bruce A Unit 1 and Units 2 that will extend the in-service life of these units by at least 25 years. Replacement of the Steam Generators (eight in each unit) is required; this work was awarded to SNC-Lavalin Nuclear (SLN). The existing steam drums (which house the steam separation and drying equipment) will be retained. Unit 2 is scheduled to be synchronized with the grid in 2009, followed by Unit 1 in 2009. Each Bruce A unit has two steam generating assemblies, one located above and to each end of the reactor. Each steam generating assembly consists of a horizontal cylindrical steam drum and four vertical Steam Generators. The vertical Steam Generators connect to individual nozzles that are located on the underside of the Steam Drum (SD). The steam drums are located in concrete shielding structures (steam drum enclosures). The lower sections of the Steam Generators penetrate the top of the reactor vaults: the containment pressure boundary is established by bellows assemblies that connect between the reactor vault roof slab and the Steam Generators. Each Steam Generators is supported from the bottom by a trapeze that is suspended from the reactor vault top structure. The Steam Generator Replacement (SGR) methodology developed by SLN for Unit 1

  8. Steam generator cleaning campaigns at Bruce A: 1993-1996

    International Nuclear Information System (INIS)

    Puzzuoli, F.V.; Leinonen, P.J.; Lowe, G.A.

    1997-01-01

    Boiler chemical cleaning (BOCC) and high-pressure water lancing operations were performed during the Bruce A 1993 Unit 3, 1994 Unit 3, 1995 Unit 1 and 1996 Unit 3 outages to remove secondary side deposits. High-pressure water lancing focused on three boiler areas: tube support plates, to remove broached hole deposits, hot leg U-bend supports to dislodge deposits contributing to boiler tube stress corrosion cracking and tube sheets with the aim of removing accumulated sludge piles and post BOCC insoluble residues. The chemical cleaning processes applied were modified versions of the one developed by the Electric Power Research Institute/Steam Generator Owners Group. During these BOCC operations, corrosion for several key boiler materials was monitored and was well below the specified allowances

  9. Steam generator replacement in Bruce A Unit 1 and Unit 2

    International Nuclear Information System (INIS)

    Hart, R.S.

    2007-01-01

    The Bruce A Generating Station consists of four 900 MW class CANDU units. The reactor and Primary Heat Transport System for each Unit are housed within a reinforced concrete reactor vault. A large duct running below the reactor vaults accommodates the shared fuel handling system, and connects the four reactor vaults to the vacuum building. The reactor vaults, fuelling system duct and the vacuum building constitute the station vacuum containment system. Bruce A Unit 2 was shut down in 1995 and Bruce A Units 1, 3 and 4 were shutdown in 1997. Bruce A Units 3 and 4 were returned to service in late 2003 and are currently operating. Units 1 and 2 remain out of service. Bruce Power is currently undertaking a major rehabilitation of Bruce A Unit 1 and Unit 2 that will extend the in-service tile of these units by at least 25 years. Replacement of the Steam Generators (eight in each unit) is required; this work was awarded to SNC-Lavalin Nuclear (SLN). The existing steam drums (which house the steam separation and drying equipment) will be retained. Unit 2 is scheduled to be synchronized with the grid in 2009, followed by Unit 1 in 2009. Each Bruce A unit has two steam generating assemblies, one located above and to each end of the reactor. Each steam generating assembly consists of a horizontal cylindrical steam drum and four vertical Steam Generators. The vertical Steam Generators connect to individual nozzles that are located on the underside of the Steam Drum (SD). The steam drums are located in concrete shielding structures (steam drum enclosures). The lower sections of the Steam Generators penetrate the top of the reactor vaults: the containment pressure boundary is established by bellows assemblies that connect between the reactor vault roof slab and the Steam Generators. Each Steam Generators is supported from he bottom by a trapeze that is suspended from the reactor vault top structure. The Steam Generator Replacement (SGR) methodology developed by SLN for Unit 1

  10. Monitoring the risk of loss of heat sink during plant shutdowns at Bruce Generating Station 'A'

    International Nuclear Information System (INIS)

    Krishnan, K.S.; Mancuso, F.; Vecchiarelli, D.

    1996-01-01

    A relatively simple loss of shutdown heat sink fault tree model has been developed and used during unit outages at Bruce Nuclear Generation Station 'A' to assess, from a risk and reliability perspective, alternative heat sink strategies and to aid in decisions on allowable outage configurations. The model is adjusted to reflect the various unit configurations planned during a specific outage, and identifies events and event combinations leading to loss of fuel cooling. The calculated failure frequencies are compared to the limits consistent with corporate and international public safety goals. The importance measures generated by the interrogation of the fault tree model for each outage configuration are also used to reschedule configurations with high fuel damage frequency later into the outage and to control the configurations with relatively high probability of fuel damage to short intervals at the most appropriate time into the outage. (author)

  11. Bruce Power's nuclear pressure boundary quality assurance program requirements, implementation and transition

    International Nuclear Information System (INIS)

    Krane, J.C.

    2009-01-01

    The development of a full scope nuclear pressure boundary quality assurance program in Canada requires extensive knowledge of the structure and detailed requirements of codes and standards published by the Canadian Standards Association (CSA) and American Society of Mechanical Engineers (ASME). Incorporation into company governance documents and implementation of these requirements while managing the transition to more recent revisions of these codes and standards represents a significant challenge for Bruce Power, Canada's largest independent nuclear operator. This paper explores the key developments and innovative changes that are used to ensure successful regulatory compliance and effective implementation of the Bruce Power Pressure Boundary Quality Assurance Program. Challenges and mitigating strategies to sustain this large compliance based program at Bruce Power's 8 unit nuclear power plant site will also be detailed. (author)

  12. Characterization and dissolution studies of Bruce Unit 3 steam generator secondary side deposits

    International Nuclear Information System (INIS)

    Semmler, J.

    1998-01-01

    The physical and chemical properties of secondary side steam generator deposits in the form of powder and flake obtained from Bruce Nuclear Generating Station A (BNGS A) Unit 3 were studied. The chemical phases present in both types of deposits, collected prior to the 1994 chemical cleaning during the pre-clean water lancing campaign, were magnetite (Fe 3 O 4 ), metallic copper (Cu), hematite (Fe 2 O 3 ) and cuprous oxide (Cu 2 O). The major difference between the chemical composition of the powder and the flake was the presence of zinc silicate (Zn 2 SiO 4 ) and several unidentified silicate phases containing Ca, Al, Mn, and Mg in the flake. The flake deposit had high hardness values, high electrical resistivity, low porosity and a lower dissolution rate in the EPRI-SGOG (Electric Power Research Institute-Steam Generator Owner's Group) chemical cleaning solvents compared to the powder deposit. Differences in the deposit properties after chemical cleaning of the Unit 3 steam generators and after laboratory cleaning were noted. The presence of silicates in the deposit inhibit magnetite dissolution

  13. The Bruce Energy Centre

    International Nuclear Information System (INIS)

    Jones, R.I.

    1982-06-01

    The Bruce Energy Centre Development Corporation is a joint venture of the Ontario Energy Corporation and 6 private companies formed to market surplus steam from the Bruce Nuclear Power Development. The corporation will also sell or lease land near Bruce NPD. The Bruce Energy Centre has an energy output of 900 BTU per day per dollar invested. Potential customers include greenhouse operators, aquaculturalists, food and beverage manufacturers, and traditional manufacturers

  14. Top of tubesheet cracking in Bruce A NGS steam generator tubing - recent experience

    International Nuclear Information System (INIS)

    Clark, M.A.; Lepik, O.; Mirzai, M.; Thompson, I.

    1998-01-01

    During the Bruce A Nuclear Generating Station (BNGS-A) Unit 1 1997 planned outage, a dew point search method identified a leak in one steam generator(SG) tube. Subsequently, the tube was inspected with all available eddy current probes and removed for examination. The initial inspection results and metallurgical examination of the removed tube confirmed that the leak was due to intergranular attack/stress corrosion cracking (IGA/SCC) emanating from the secondary side of the tube at the top of the tubesheet location. Subsequently, eddy current and ultrasonic indications were found at the top of the tubesheet of other Alloy 600 SG tubes. To investigate the source of the indications and to validate the inspection probes, sections of 40 tubes with various levels of damage were removed. The metallurgical examination of the removed sections showed that both secondary side and primary side initiated, circumferential, stress corrosion cracking and intergranular attack occurred in the BNGS-A SG tubing. Significant degradation from both mechanisms was found, invariably located in the roll transition region of the top expansion joint between the tube and the tubesheet on the hot leg (304 degrees C) side of the tube. Various aspects of the failures and tube examinations are presented in this paper, including presentation of the cracking morphology, measured crack size distributions, and discussion of some factors possibly affecting the cracking. (author)

  15. Explorability and predictability of the paleozoic sedimentary sequence beneath the Bruce nuclear site

    International Nuclear Information System (INIS)

    Parmenter, A.; Jensen, M.; Crowe, R.; Raven, K.

    2011-01-01

    Ontario Power Generation (OPG) is proposing to develop a Deep Geologic Repository (DGR) for the long-term management of its Low and Intermediate Level Waste (L&ILW) at the Bruce nuclear site located in the Municipality of Kincardine, Ontario. A 4-year program of geoscientific studies to assess the suitability of the 850 m thick Palaeozoic age sedimentary sequence beneath the site to host the DGR was completed in 2010. The studies provide evidence of a geologic setting in which the DGR concept would be safely implemented at a nominal depth of 680 m within the argillaceous limestone of the Cobourg Formation. This paper describes the geologic framework of the Bruce nuclear site with a focus on illustrating the high degree of stratigraphic continuity and traceability at site-specific and regional scales within the Ordovician sediments proposed to host and enclose the DGR. As part of the site-specific studies, a program of deep drilling/coring (6 boreholes) and in-situ testing through the sedimentary sequence was completed from 4 drill sites situated beyond the DGR footprint, approximately 1 km apart. Core logging reveals that the stratigraphic sequence comprises 34 distinct bedrock formations/members/units consistent with the known regional stratigraphic framework. These layered sedimentary formations dip 0.6 o (~10 m/km) to the southwest with highly uniform thicknesses both at the site- and regional-scale, particularly, the Ordovician sediments, which vary on the order of metres. The occurrence of steeply-dipping faults within the sedimentary sequence is not revealed through surface outcrop fracture mapping, micro-seismic (M ≥ 1) monitoring, inclined borehole coring or intersection of hydrothermal type dolomitized reservoir systems. Potential fault structures, interpreted from a 2-D seismic survey, were targeted by angled boreholes which found no evidence for their existence. Formation specific continuity is also evidence by the lateral traceability of physical rock

  16. Analogue to digital upgrade project-boiler feedwater control system for Bruce Power nuclear units 1 & 2

    International Nuclear Information System (INIS)

    Long, R.

    2012-01-01

    Bruce Power Nuclear Generating Station A, “Bruce A” is in the final stages of its Restart Project. This capital project will see a large scale rehabilitation of Units 1 and 2 resulting in addition of 1500MW of safe, reliable, clean electricity to the Ontario grid. Restart Project Scope 375, Boiler Feedwater Controls Upgrade was sanctioned to replace obsolete analog devices with a modern digital control system. This project replaced the existing Foxboro H Line analog controls which comprised of 81 individual control modules and support instrumentation. The replacement system was a Triconex Triple Modular Redundant PLC which interfaces with two redundant touch screen monitors. The upgraded digital system incorporates the following controls: 1. Boiler Level Control Loops 2. Dearator Level Control Loops 3. Dearator Pressure Control Loops 4. Boiler Feedwater Recirculation Flow Control Loops A number of technical challenges were addressed when installing a new digital system within the existing plant configuration. Interfaces to new, old and refurbished field devices must be understood as well as implications of connecting to the plant’s Digital Control Computers (DCC’s) and newly installed Steam Generators. The overall project involved many stakeholders to address various requirements from conceptual / design stage through procurement, construction, commissioning and return to service. In addition, the project highlighted the unique requirements found in Nuclear Industry with respect to Human Factors and Software Quality Assurance. (author)

  17. Steam generator replacement at Bruce A: approach, results, and lessons learned

    International Nuclear Information System (INIS)

    Tomkiewicz, W.; Savage, B.; Smith, J.

    2008-01-01

    Steam Generator Replacement is now complete in Bruce A Units 1 and 2. In each reactor, eight steam generators were replaced; these were the first CANDU steam generator replacements performed anywhere in the world. The plans for replacement were developed in 2004 and 2005, and were summarized in an earlier paper for the CNS Conference held in November, 2006. The present paper briefly summarizes the methodologies and special processes used such as metrology, cutting and welding and heavy lifting. The paper provides an update since the earlier report and focuses on the project achievements to date, such as: - A combination of engineered methodology, laser metrology and precise remote machining led to accurate first time fit-ups of each new replacement steam generator and steam drums - Lessons learned in the first unit led to schedule improvements in the second unit - Dose received was lowest recorded for any steam generator replacement project. The experience gained and lessons learned from Units 1 and 2 will be valuable in planning and executing future replacement steam generator projects. A video was presented

  18. Mitigation of organically bound sulphate from water treatment plants at Bruce NGS and impact on steam generator secondary side chemistry control

    Energy Technology Data Exchange (ETDEWEB)

    Nashiem, R.; Davloor, R.; Harper, B.; Smith, K. [Bruce Power, Tiverton, Ontario (Canada); Gauthier, C. [CTGIX Services Inc., Burlington, Ontario (Canada); Schexnailder, S. [GE Water and Process Technologies, Dallas, Texas (United States)

    2010-07-01

    Bruce Power is the source of more than 20 per cent of Ontario's electricity and currently operates six reactor units at the Bruce Nuclear Generating Station A (two units) and B (four units) stations located on Lake Huron. This paper discusses the challenges faced and operating experience (OPEX) gained in meeting WANO 1.0 chemistry performance objectives for steam generator secondary side chemistry control, particularly with control of steam generator sulphates. A detailed sampling and analysis program conducted as part of this study concluded that a major contributor to steam generator (SG) elevated sulphates is Organically Bound Sulphate (OBS) in Water Treatment Plants (WTP) effluent. The Bruce A and B WTPs consist of clarification with downstream sand and carbon filtration for Lake Water pre-treatment, which are followed by conventional Ion Exchange (IX) demineralization. Samples taken from various locations in the process stream were analyzed for a variety of parameters including both organic bound and inorganic forms of sulphate. The results are inconclusive with respect to finding the definitive source of OBS. This is primarily due to the condition that the OBS in the samples, which are in relatively low levels, are masked during chemical analysis by the considerably higher inorganic sulphate background. Additionally, it was also determined that on-line Total Organic Carbon (TOC) levels at different WTP locations did not always correlate well with OBS levels in the effluent, such that TOC could not be effectively used as a control parameter to improve OBS performance of the WTP operation. Improvement efforts at both plants focused on a number of areas including optimization of clarifier operation, replacement of IX resins, addition of downstream mobile polishing trailers, testing of new resins and adsorbents, pilot-scale testing with a Reverse Osmosis (RO) rig, review of resin regeneration and backwashing practices, and operating procedure improvements

  19. Mitigation of organically bound sulphate from water treatment plants at Bruce NGS and impact on steam generator secondary side chemistry control

    International Nuclear Information System (INIS)

    Nashiem, R.; Davloor, R.; Harper, B.; Smith, K.; Gauthier, C.; Schexnailder, S.

    2010-01-01

    Bruce Power is the source of more than 20 per cent of Ontario's electricity and currently operates six reactor units at the Bruce Nuclear Generating Station A (two units) and B (four units) stations located on Lake Huron. This paper discusses the challenges faced and operating experience (OPEX) gained in meeting WANO 1.0 chemistry performance objectives for steam generator secondary side chemistry control, particularly with control of steam generator sulphates. A detailed sampling and analysis program conducted as part of this study concluded that a major contributor to steam generator (SG) elevated sulphates is Organically Bound Sulphate (OBS) in Water Treatment Plants (WTP) effluent. The Bruce A and B WTPs consist of clarification with downstream sand and carbon filtration for Lake Water pre-treatment, which are followed by conventional Ion Exchange (IX) demineralization. Samples taken from various locations in the process stream were analyzed for a variety of parameters including both organic bound and inorganic forms of sulphate. The results are inconclusive with respect to finding the definitive source of OBS. This is primarily due to the condition that the OBS in the samples, which are in relatively low levels, are masked during chemical analysis by the considerably higher inorganic sulphate background. Additionally, it was also determined that on-line Total Organic Carbon (TOC) levels at different WTP locations did not always correlate well with OBS levels in the effluent, such that TOC could not be effectively used as a control parameter to improve OBS performance of the WTP operation. Improvement efforts at both plants focused on a number of areas including optimization of clarifier operation, replacement of IX resins, addition of downstream mobile polishing trailers, testing of new resins and adsorbents, pilot-scale testing with a Reverse Osmosis (RO) rig, review of resin regeneration and backwashing practices, and operating procedure improvements

  20. Hydrogeological evidence of low rock mass permeabilities in ordovician strata: Bruce nuclear site

    International Nuclear Information System (INIS)

    Beauheim, R.L.; Roberts, R.M.; Avis, J.D.; Heagle, D.

    2011-01-01

    One of the key attributes contributing to the suitability of the Bruce nuclear site to host a Deep Geologic Repository (DGR) for Low and Intermediate Level Waste (L&ILW) is the low permeability of the Ordovician host rock and of the overlying and underlying strata. The permeability of these rocks is so low that diffusion is a much more significant transport mechanism than advection. Hydrogeological evidence for the low permeability of the Ordovician strata comes from two principal sources, direct and indirect. Direct evidence of low permeability is provided by the hydraulic testing performed in deep boreholes, DGR-2 through DGR-6. Straddle-packer hydraulic testing was performed in 57 Ordovician intervals in these five holes. The testing provided continuous coverage using ~30-m straddle intervals of the Ordovician strata exposed in boreholes DGR-2, DGR-3, DGR-4, and DGR-5, while testing was targeted on discontinuous 10.2-m intervals in DGR-6. The average horizontal hydraulic conductivities of these intervals determined from the tests ranged from 2E-16 to 2E-10 m/s. The Lower Member of the Cobourg Formation, which is the proposed host formation for the DGR, was found to have a horizontal hydraulic conductivity of 4E-15 to 3E-14 m/s. The only horizontal hydraulic conductivity values measured that were greater than 2E-12 m/s are from the Black River Group, located at the base of the Ordovician sedimentary sequence. Indirect evidence of low permeability is provided by the observed distribution of hydraulic heads through the Ordovician sequence. Hydraulic head profiles, defined by hydraulic testing and confirmed by Westbay multilevel monitoring systems, show significant underpressures relative to a density-compensated hydrostatic condition throughout most of the Ordovician strata above the Black River Group, whereas the Black River Group is overpressured. Pressure differences of 1 MPa or more are observed between adjacent intervals in the boreholes. The observed

  1. The predictable nature of the Paleozoic sedimentary sequence beneath the Bruce nuclear site in Southern Ontario, Canada

    International Nuclear Information System (INIS)

    Parmenter, Andrew; Jensen, Mark; Crowe, Richard

    2012-01-01

    Document available in extended abstract form only. A key aspect of a Deep Geologic Repository (DGR) safety case is the ability to develop and communicate an understanding of the geologic stability and resilience to change at time frames relevant to demonstrating repository performance. As part of an on-going Environmental Assessment, Ontario Power Generation (OPG) recently completed site-specific investigations within an 850 m thick Paleozoic sedimentary sequence beneath the Bruce nuclear site for the proposed development of a DGR for Low and Intermediate Level Waste (L and ILW). As envisioned, the shaft-accessed DGR would be excavated at a nominal depth of 680 m within the low permeability Ordovician argillaceous limestone of the Cobourg Formation, which is overlain by more than 200 m of low permeability Ordovician shale. The geo-scientific investigations revealed a relatively undeformed and laterally continuous architecture within the sedimentary sequence at the repository scale (1.5 km 2 ) and beyond. This paper explores the predictable nature of the sedimentary sequence that has contributed to increasing confidence in an understanding of the spatial distribution of groundwater system properties, deep groundwater system evolution and natural barrier performance. Multi-disciplinary geo-scientific investigations of the Bruce nuclear site were completed in 3 phases between 2006 and 2010. The sub-surface investigations included a deep drilling, coring and in-situ testing program and, the completion of a 19.7 km (9 lines) 2-D seismic reflection survey. The drilling program involved 6 (150 mm dia.) deep boreholes (4-vertical; 2 inclined) that were extended through the sedimentary sequence from 4 drill sites, arranged around the 0.3 km 2 footprint of the proposed repository. The more than 3.8 km of rock core (77 mm dia.) retrieved have provided, in part, a strong basis to understand bedrock lithology and mineralogy, facies assemblages, structure, and oil and gas

  2. Status of the reliability centered maintenance program at Ontario Hydro's Bruce 'A' Nuclear Division

    International Nuclear Information System (INIS)

    Khan, I.

    1995-01-01

    Bruce A started a preventive maintenance (PM) quality improvement program in August of 1991. This initiative was taken to address the concerns expressed by the AECB and the Peer Audits finding. The concerns were on the quality of the Bruce A PM Program and its execution in the field. Reliability Centered Maintenance (RCM) analysis was selected as the PM program quality improvement and optimization technique. Therefore, RCM became a key component of Bruce A's Integrated PM program and maintenance strategy. As a result of RCM implementation, and improvements in the work planning and scheduling process, Bruce A is seeing downward trends in the corrective maintenance work load, maintenance preventable forced outages, overdue/missed PM tasks and corrective maintenance backlog. Control Room Operators have reported observing an improvement in systems and equipment response to transients. Other benefits include a documented, controlled and traceable PM program. In addition, the team approach required by RCM has started to improve staff confidence in the PM program which, in turn, is improving the compliance with the PM program. (author)

  3. Feasibility analysis of the utilization of moderator heat for agricultural and aquacultural purposes, Bruce nuclear power development

    International Nuclear Information System (INIS)

    1977-12-01

    A study is presented of the feasibility of using moderator reject heat from the Bruce nuclear power development either to heat greenhouses or to aid in a warm water hatchery or aquaculture operation. The study examines heat extraction and delivery plans, reliability of supply, pricing schedules, the Ontario greenhouse industry, site selection criteria, water transmission and distribution, costs, approvals required, and a construction timetable. Total system analysis shows that a greenhouse facility would be viable but the aquaculture/hatchery scheme is more cost-effective. (E.C.B.)

  4. Water lancing of Bruce-A Unit 3 and 4 steam generators

    International Nuclear Information System (INIS)

    Puzzuoli, F.V.; Murchie, B.; Allen, S.

    1995-01-01

    During the Bruce-A 1993 Unit 4 and 1994 Unit 3 outages, three water lancing operations were carried out along with chemical cleaning as part of the station boiler refurbishment program. The water lancing activities focused on three boiler areas.. 1) support plates to clean partially or completely blocked broach holes and prevent boiler water level oscillations, 2) hot leg U-bend supports (HLUBS) to remove deposits contributing to boiler tube stress corrosion cracking (SCC) and 3) tube sheets to dislodge sludge piles that potentially threaten boiler tube integrity and to flush out post chemical cleaning insoluble residues. The combination of water lancing and chemical cleaning effectively reduced broach hole blockage from up to 100% to 0-10% or less. As a result, boilers in Units 3 and 4 will operate for some time to come without concerns over water level oscillations. However, deposits remained in most tube support plate land areas. (author)

  5. GRA model development at Bruce Power

    International Nuclear Information System (INIS)

    Parmar, R.; Ngo, K.; Cruchley, I.

    2011-01-01

    In 2007, Bruce Power undertook a project, in partnership with AMEC NSS Limited, to develop a Generation Risk Assessment (GRA) model for its Bruce B Nuclear Generating Station. The model is intended to be used as a decision-making tool in support of plant operations. Bruce Power has recognized the strategic importance of GRA in the plant decision-making process and is currently implementing a pilot GRA application. The objective of this paper is to present the scope of the GRA model development project, methodology employed, and the results and path forward for the model implementation at Bruce Power. The required work was split into three phases. Phase 1 involved development of GRA models for the twelve systems most important to electricity production. Ten systems were added to the model during each of the next two phases. The GRA model development process consists of developing system Failure Modes and Effects Analyses (FMEA) to identify the components critical to the plant reliability and determine their impact on electricity production. The FMEAs were then used to develop the logic for system fault tree (FT) GRA models. The models were solved and post-processed to provide model outputs to the plant staff in a user-friendly format. The outputs consisted of the ranking of components based on their production impact expressed in terms of lost megawatt hours (LMWH). Another key model output was the estimation of the predicted Forced Loss Rate (FLR). (author)

  6. Nuclear process steam for industry: potential for the development of an Industrial Energy Park adjacent to the Bruce Nuclear Power Development

    Energy Technology Data Exchange (ETDEWEB)

    Seddon, W A

    1981-11-01

    This report summarizes the results of an industrial survey jointly funded by the Bruce County Council, the Ontario Energy Corporation, Atomic Energy of Canada Limited and conducted with the cooperation of Ontario Hydro and the Ontario Ministry of Industry and Tourism. The objective of the study was to identify and assess the future needs and interest of energy-intensive industries in the concept of an Industrial Energy Park adjacent tof the Bruce Nuclear Power Development. The proposed Energy Park would capitalize on the infrastructure of the existing CANDU reactors and Ontario Hydro's proven and unique capability to produce steam, as well as electricity, at a cost currently about half that from a comparable coal-fired station.

  7. CECIL lances Bruce's boilers

    International Nuclear Information System (INIS)

    Malaugh, J.; Monaghan, D.

    1994-01-01

    Over the past few years Ontario Hydro has become increasingly concerned about accumulations of sludge in its nuclear plant boilers, so a comprehensive sludge management programme has been instituted to combat build-up. This included developing the tele-operated robot CECIL (Consolidated Edison Combined Inspection and Lancing) equipment, originally designed for work in PWRs, for CANDU boilers. This required a significantly reconfigured robotic system as well as modifications to the boilers themselves. Work on the Bruce A reactor is described. (4 figures). (author)

  8. Bruce Power - the first 24 exciting months

    International Nuclear Information System (INIS)

    Mottram, R.

    2003-01-01

    In this presentation, Ron Mottram will review the 2 year business evolution since the inception of Bruce Power - Ontario's largest independent electricity generator. Mr. Mottram will provide an overview of the Bruce Power business and operating history, along with specific emphasis on the project to Restart Bruce Units 3 and 4. Ron will share many of the project successes and challenges, and will provide insight into the myriad of issues faced by a large multi-faceted project of this type. (author)

  9. The post irradiation examination of fuel in support of Bruce A nuclear division fueling with flow program

    International Nuclear Information System (INIS)

    Montin, J.; Sagat, S.; Day, R.; Novak, J.; Bromfield, H.

    1995-01-01

    Bruce A Nuclear Division (BAND) units are operating at ∼ 75% of full power, because of the potential of a power pulse in the event of an inlet header break. As a result, BAND is converting to fueling with flow, to eliminate the potential of a power pulse and to allow for full-power operation. Concerns regarding the integrity of the end-of-life (EOL) bundles interacting with the latch at the downstream end of the fuel channel were raised. BAND carried out a test program in which EOL bundles in the upstream position 13 of Unit 2 were cascaded into the downstream latch position 1 of another channel. Six of twelve cascaded bundles and two typical EOL position 13 (benchmark) bundles were selected for post-irradiation examination (PIE). Incipient cracks were found in the assembly welds (endplateto-endcap welds) of all six cascaded bundles. No incipient cracks were found in the benchmark bundles. Metallographic and fractographic examination, along with crack dating, and hydrogen and deuterium analyses, indicated that the incipient cracks were the result of delayed-hydride assisted cracking at the EOL. Consequently, Ontario Hydro changed the design of the outlet shield plug to support all three rings of the fuel bundle, to minimize stress and prevent endplate cracking. Also, an ultrasonic endplate inspection tool (UT) was developed and located in the fuel bay. to inspect fuelbundle endplates for cracks. A second test was done involving a series of four bundle cascades in BAND Unit 4 channels that had new outlet shield plugs. The latch bundles were discharged after a hot shutdown. The cascaded Unit 2 and Unit 4 latch bundles were checked for cracks using the UT. The PIE found incipient cracks or less-than-ideal welds in the assembly welds of fuel elements from Unit 2 (latch-supported fuel bundles) that had been identified by the UT as having incipient cracks. No incipient cracks were found in the assembly welds of fuel elements from Unit 4 (new outlet shield

  10. The post-irradiation examination of fuel in support of Bruce A Nuclear Division fueling with flow program

    International Nuclear Information System (INIS)

    Montin, J.; Sagat, S.

    1995-10-01

    Bruce A Nuclear Division (BAND) units are operating at ∼ 75% of full power, because of the potential of a power pulse in the event of an inlet header break. As a result, BAND is converting to fueling with flow, to eliminate the potential of a power pulse and to allow for full-power operation. Concerns regarding the integrity of the end-of-life (EOL) bundles interacting with the latch at the downstream end of the fuel channel were raised. BAND carried out a test program in which EOL bundles in the upstream position of 13 of Unit 2 were cascaded into the downstream latch position 1 of another channel. Six of twelve cascaded bundles and two typical EOL position 13 (benchmark) bundles were selected for post-irradiation examination (PIE). Incipient cracks were found in the benchmark bundles. Metallographic and fractographic examination, along with crack dating, and hydrogen and deuterium analyses, indicated that the incipient cracks were the result of delayed-hydride assisted cracking at the EOL. Consequently, Ontario Hydro changed the design of the outlet shield plug to support all three rings of the fuel bundle, to minimize stress and prevent end plate cracking. Also, an ultrasonic end plate inspection tool (UT) was developed and located in the fuel bay, to inspect fuel-bundle end plates for cracks. A second test was done involving a series of four bundle cascades in BAND Unit 4 channels that had new outlet shield plugs. The latch bundles were discharged after a hot shutdown. The cascaded Unite 2 and Unit 4 latch bundles were checked for cracks using the UT. The PIE found incipient cracks or less-than-ideal welds in the assembly welds of fuel elements from Unit 2 (latch-supported fuel bundles) that had been identified by the UT as having incipient cracks. No incipient cracks were found in the assemble welds of fuel elements from Unit 4 (new outlet shield-supported fuel bundles) confirming the UT results. (author). 5 refs., 8 figs

  11. Bruce used fuel dry storage project evolution from Pickering to Bruce

    International Nuclear Information System (INIS)

    Young, R.E.

    1996-01-01

    Additional fuel storage capacity is required at Bruce Nuclear Generating Station, which otherwise would soon fill up all its pool storage capacity. The recommended option was to use a dry storage container similar to that at Pickering. The changes made to the Pickering type of container included: fuel to be stored in trays; the container's capacity increased to 600 bundles; the container's lid to be changed to a metal one; the single concrete lid to be changed to a double metal lid system; the container not to be transportable; the container would be dry-loaded. 7 figs

  12. Bruce used fuel dry storage project evolution from Pickering to Bruce

    Energy Technology Data Exchange (ETDEWEB)

    Young, R E [Ontario Hydro, Tiverton, ON (Canada). Bruce Nuclear Generating Station-A

    1997-12-31

    Additional fuel storage capacity is required at Bruce Nuclear Generating Station, which otherwise would soon fill up all its pool storage capacity. The recommended option was to use a dry storage container similar to that at Pickering. The changes made to the Pickering type of container included: fuel to be stored in trays; the container`s capacity increased to 600 bundles; the container`s lid to be changed to a metal one; the single concrete lid to be changed to a double metal lid system; the container not to be transportable; the container would be dry-loaded. 7 figs.

  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. 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. 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.

  16. 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.)

  17. AECB staff annual report of Bruce NGS 'B' for the year 1988

    International Nuclear Information System (INIS)

    1989-05-01

    The operation of the Bruce 'B' Nuclear Generating Station is monitored and licensing requirements are enforced by the Atomic Energy Control Board (AECB) Bruce project staff, with appropriate support from other AECB personnel. The staff observes operation of the reactors, conducts audits, witnesses important activities, reviews station documentation and reports, and issues approvals where appropriate in accordance with license conditions. As required by a condition of its Operating Licence, Ontario Hydro each year submits Technical Reports which summarize various aspects of the operation of Bruce NGS 'B' during the year. When these reports have been reviewed by AECB staff, a formal Annual Review Meeting is held with the station management to discuss safety-related aspects of the station operation, and to inform Ontario Hydro of AECB staff conclusions with respect to the performance of Ontario Hydro in operating the station during the year

  18. RCM: the Bruce B experience

    International Nuclear Information System (INIS)

    Hill, Earl S.; Doyle, E.K.

    1995-01-01

    The use of RCM techniques have begun to change maintenance practice at Bruce B. This paper identifies the status of the program at Bruce B, and examines a new methodology for completing system analysis studies by incorporating lessons learned and results from Bruce A. (author)

  19. Future nuclear power generation

    International Nuclear Information System (INIS)

    Mosbah, D.S.; Nasreddine, M.

    2006-01-01

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

  20. Fans af Bruce

    DEFF Research Database (Denmark)

    Vaaben, Nana Katrine

    2007-01-01

    Analysen viser, hvordan det samme ritual under en koncert forener og opdeler de fans, der orienterer sig mod Bruce Springsteen. På den ene side forener ritualet hele publikum i en stor fælles "Intimitet for mange" og på den anden side splitter det dem, fordi det bliver tydeligt, hvem der er de...... rigtige fans, og hvem der tilhører "pøbelen"....

  1. Bruce A - performance power

    Energy Technology Data Exchange (ETDEWEB)

    Boucher, P. [Bruce Power, Tiverton, ON (Canada)

    2015-07-01

    This paper discusses the strategy for improving performance at Bruce Power. The key to excellence is changing behaviours. Reinforcing and enforcing expectations, aligned with the 2015 operating to the Highest Standards Site Initiative. Long term equipment strategies, supported by the 2015 Equipment Health Site Initiative, individual and group accountability for online/outage Work Management, with further gains through 2015 Maintenance Alignment and Resource Strategy (MARS) Site Initiative. Results showed human performance improvement, more reliable and predictable units and outage performance improvement.

  2. 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)

  3. Impact of bundle deformation on CHF: ASSERT-PV assessment of extended burnup Bruce B bundle G85159W

    International Nuclear Information System (INIS)

    Rao, Y.F.; Manzer, A.M.

    2005-01-01

    This paper presents a subchannel thermalhydraulic analysis of the effect on critical heat flux (CHF) of bundle deformation such as element bow and diametral creep. The bundle geometry is based on the post-irradiation examination (PIE) data of a single bundle from the Bruce B Nuclear Generating Station, Bruce B bundle G85159W, which was irradiated for more than two years in the core during reactor commissioning. The subchannel code ASSERT-PV IST is used to assess changes in CHF and dryout power due to bundle deformation, compared to the reference, undeformed bundle. (author)

  4. 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)

  5. The Bruce Medalists

    Science.gov (United States)

    Tenn, J. S.

    2001-12-01

    The Astronomical Society of the Pacific (ASP) has presented the Catherine Wolfe Bruce gold medal for lifetime contributions to astronomy most years since 1898. The 94 medalists include most of the scientists whose work has greatly changed astronomy since the late nineteenth century: Huggins, Pickering, Campbell, Hale, Eddington, Russell, Adams, Slipher, Hertzsprung, Hubble, Shapley, Oort, Baade, ... Major exceptions include those who died young, those who worked in teams, and, in the early years, women. Mathematicians appear to have been as likely to be honored as astronomers from the beginning, but the fortunes of physicist nominees have varied. The nomination process is an unusual one, with the directors of six observatories, three in the U.S. and three abroad, asked to nominate up to three candidates each year. For the first six decades the observatories rarely varied, and directors had long tenures. They nominated the same individuals repeatedly. Now both observatories and their directors vary regularly. Much can be learned about the changes in astronomy from the late nineteenth century, when observers worked alone with long refractors and a theorist could spend a lifetime computing the orbit of one comet, to the present, when most papers have multiple authors and a single project may include millions of objects. For example, celestial mechanics was the specialty of many of the early medalists but none since 1966. I have posted photographs, brief biographies, extensive bibliographies, and links to publications by and about all of the medalists, from Simon Newcomb in 1898 to Hans Bethe in 2001, at http://phys-astro.sonoma.edu/BruceMedalists/. I will discuss a bit of the history of the medal and some of the medalists.

  6. Waste repository planned for Bruce Site

    International Nuclear Information System (INIS)

    King, F.

    2004-01-01

    Ontario Power Generation (OPG) and Kincardine, the municipality nearest the Bruce site, have agreed in principal to the construction of a deep geologic repository for low and medium level radioactive waste on the site. The two parties signed the 'Kincardine Hosting Agreement' on October 13, 2004 to proceed with planning, seek regulatory approval and further public consultation of the proposed project. A construction Licence is not expected before 2013. (author)

  7. 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)

  8. Carsten Niebuhr and James Bruce

    DEFF Research Database (Denmark)

    Friis, Ib

    2013-01-01

    In 1791 Carsten Niebuhr published a review of the first two volumes of Bruce’s Reisen zur Entdeckung der Quellen des Nils (1790). Niebuhr’s strongest criticism of Bruce was that he seemed to have plagiarized some of Niebuhr’s astronomical observations (“adopted them without examination”) and that......In 1791 Carsten Niebuhr published a review of the first two volumes of Bruce’s Reisen zur Entdeckung der Quellen des Nils (1790). Niebuhr’s strongest criticism of Bruce was that he seemed to have plagiarized some of Niebuhr’s astronomical observations (“adopted them without examination...... as written by Bruce in 1770 at Gondar, Abyssinia, contains information about latitudes identical with some of Niebuhr’s observations which were unpublished in 1770; possible explanations for this are proposed. In summary, it seems that Niebuhr is right; it is almost certain that Bruce plagiarized some...

  9. Experience of oil in CANDU moderator during A831 planned outage at Bruce Power

    International Nuclear Information System (INIS)

    Ma, G.; Nashiem, R.; Matheson, S.; Stuart, C.; Roberts, J.G.

    2011-01-01

    In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

  10. Experience of oil in CANDU® moderator during A831 planned outage at Bruce Power

    International Nuclear Information System (INIS)

    Ma, G.; Nashiem, R.; Matheson, S.; Stuart, C.; Roberts, J.G.

    2010-01-01

    In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU® reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

  11. Experience of oil in CANDU® moderator during A831 planned outage at Bruce Power

    Energy Technology Data Exchange (ETDEWEB)

    Ma, G.; Nashiem, R.; Matheson, S. [Bruce Power, Tiverton, Ontario (Canada); Stuart, C. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Roberts, J.G. [CANTECH Associates Ltd., Burlington, Ontario (Canada)

    2010-07-01

    In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU® reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

  12. Experience of oil in CANDU moderator during A831 planned outage at Bruce Power

    Energy Technology Data Exchange (ETDEWEB)

    Ma, G.; Nashiem, R.; Matheson, S. [Bruce Power, Tiverton, Ontario (Canada); Stuart, C. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Roberts, J.G. [CANTECH Associates Ltd., Burlington, Ontario (Canada)

    2011-03-15

    In their address to the Nuclear Plant Chemistry Conference 2009, Bruce Power staff will describe the effects of oil ingress to the moderator of a CANDU reactor. During the A831 planned outage of Bruce Power Unit 3, an incident of oil ingress into moderator was discovered on Oct 17, 2008. An investigation identified the cause of the oil ingress. Atomic Energy of Canada Ltd. (AECL) assessed operability of the reactor with the oil present and made recommendations with respect to the effect on unit start-up with oil present. The principal concern was the radiolytic generation of deuterium from the breakdown of the oil in-core. Various challenges were presented during start-up which were overcome via innovative approaches. The subsequent actions and consequential effects on moderator chemistry are discussed in this paper. Examination of the plant chemistry data revealed some interesting aspects of moderator system chemistry under upset conditions which will also be presented. (author)

  13. AECB staff review of Bruce NGS 'B' operation for the year 1989

    International Nuclear Information System (INIS)

    1990-06-01

    The operation of the Bruce Nuclear Generating Station 'B' is monitored and licensing requirements are enforced by the Atomic Energy Control Board (AECB), which observes operation of the reactors, conducts audits, witnesses important activities, reviews station documentation and reports, and issue approvals, where appropriate, in accordance with licence conditions. This report records the conclusions of the AECB staff assessment of Bruce NGS 'B' during 1989. In general, the station operated within acceptable safety standards. Quality improvement initiatives started in 1989 should lead to improved station maintenance and operation in coming years. Ontario Hydro still needs to improve the administration of operating memos, deficiency reports and call-ups. Station management must ensure that shift supervisors and reactor first operators operate the station in a conservative manner at all times and put safety interests first when responding to a unit upset. (2 tabs.)

  14. 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)

  15. Bruce A refurbishment - an update

    International Nuclear Information System (INIS)

    Liddle, R.

    2007-01-01

    Running slightly ahead of schedule on the critical path work, the Bruce A Restart Project has not been without its challenges. About a dozen major contractors with a workforce of 1,700 tradespeople share space inside the Units 1 and 2 Construction Island. They share support services, provided by project management contractor AMEC NCL, and they share the consequences when one part of the project advances ahead of schedule or another falls behind. They also share Bruce Power's safety values and are well on their way to surpassing five-million hours without an acute lost time injury. (author)

  16. 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)

  17. Bruce Springsteen as a Symbol

    DEFF Research Database (Denmark)

    Gitz-Johansen, Thomas

    2018-01-01

    The article explores how Bruce Springsteen and his music function as a symbol. The article first presents the Jungian theory of symbols and of music as symbol. The central argument of the article is that, by functioning symbolically, Springsteen has the potential to influence the psyche of his au...

  18. 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.)

  19. Bruce NGS B risk assessment (BBRA) peer review process

    International Nuclear Information System (INIS)

    Kaasalainen, S.; Crocker, W.P.; Webb, W.A.

    2001-01-01

    Risk-informed decision making is considered an effective approach to managing the risk of nuclear power plant operation in a competitive market. Hence, increased reliance on the station probabilistic risk assessments (PRAs) to provide risk perspective inputs is inevitable. With increased reliance on the PRAs it is imperative that PRAs have the characteristics necessary to provide the required information. Recognizing the increased requirements on nuclear power plant PRAs the nuclear industry in the United States has expended significant effort over the past few years defining the required characteristics of a PRA for various applications. More recently several owners groups have drafted guidelines for PRA certification and several U.S. utilities have had their PRAs certified. During the year 2000 Ontario Power Generation, Nuclear (OPG,N) subjected the PRA of one of its stations to the U.S. style certification process. The PRA selected for this process was the Bruce B Risk Assessment (BBRA). BBRA was chosen for this process since it is the first OPG, N PRA to be used for risk-informed applications. However, the strengths of the BBRA identified from the certification process and the lessons learned are also largely applicable to the other OPG, N plant PRAs due to the use of similar methods and tools

  20. AECB staff review of Bruce NGS 'A' operation for the year 1989

    International Nuclear Information System (INIS)

    1990-06-01

    The operation of the Bruce Nuclear Generating Station 'B' is monitored and licensing requirements are enforced by the Atomic Energy Control Board (AECB). This report records the conclusions of the AECB staff assessment of Bruce NGS 'A' during 1989 and the early part of 1990. Overall operation of the station met acceptable safety standards. Despite numerous problems and technical difficulties encountered, station management and supervisory personnel acted with due caution and made decisions in the interests of safety. There was evidence of improvement in a number of key areas, supported by pertinent indicators in the objective measures table. The extensive inspection and maintenance programs carried out during the year revealed the extent of component deterioration due to aging to be larger than expected. Hydrogen embrittlement of pressure tubes, erosion/corrosion of steam and feed water valves, heat exchanger tubes and piping, fouling of boilers and heat exchangers, and environmental damage of electrical equipment are examples. Continued aging of plant equipment and its potential for reducing the margins for safe operation must be taken into account by Ontario Hydro in establishing priorities and target dates for completion of actions to resolve identified problems at Bruce NGS 'A'. (2 tabs.)

  1. 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

  2. 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)

  3. Review of Bruce A reactor regulating system software

    International Nuclear Information System (INIS)

    1995-12-01

    Each of the four reactor units at the Ontario Hydro Bruce A Nuclear Generating Station is controlled by the Reactor Regulating System (RRS) software running on digital computers. This research report presents an assessment of the quality and reliability of the RRS software based on a review of the RRS design documentation, an analysis of certain significant Event Reports (SERs), and an examination of selected software changes. We found that the RRS software requirements (i.e., what the software should do) were never clearly documented, and that design documents, which should describe how the requirements are implemented, are incomplete and inaccurate. Some RRS-related SERs (i.e., reports on unexpected incidents relating to the reactor control) implied that there were faults in the RRS, or that RRS changes should be made to help prevent certain unexpected events. The follow-up investigations were generally poorly documented, and so it could not usually be determined that problems were properly resolved. The Bruce A software change control procedures require improvement. For the software changes examined, there was insufficient evidence provided by Ontario Hydro that the required procedures regarding change approval, independent review, documentation updates, and testing were followed. Ontario Hydro relies on the expertise of their technical staff to modify the RRS software correctly; they have confidence in the software code itself, even if the documentation is not up-to-date. Ontario Hydro did not produce the documentation required for an independent formal assessment of the reliability of the RRS. (author). 37 refs., 3 figs

  4. Review of Bruce A reactor regulating system software

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    Each of the four reactor units at the Ontario Hydro Bruce A Nuclear Generating Station is controlled by the Reactor Regulating System (RRS) software running on digital computers. This research report presents an assessment of the quality and reliability of the RRS software based on a review of the RRS design documentation, an analysis of certain significant Event Reports (SERs), and an examination of selected software changes. We found that the RRS software requirements (i.e., what the software should do) were never clearly documented, and that design documents, which should describe how the requirements are implemented, are incomplete and inaccurate. Some RRS-related SERs (i.e., reports on unexpected incidents relating to the reactor control) implied that there were faults in the RRS, or that RRS changes should be made to help prevent certain unexpected events. The follow-up investigations were generally poorly documented, and so it could not usually be determined that problems were properly resolved. The Bruce A software change control procedures require improvement. For the software changes examined, there was insufficient evidence provided by Ontario Hydro that the required procedures regarding change approval, independent review, documentation updates, and testing were followed. Ontario Hydro relies on the expertise of their technical staff to modify the RRS software correctly; they have confidence in the software code itself, even if the documentation is not up-to-date. Ontario Hydro did not produce the documentation required for an independent formal assessment of the reliability of the RRS. (author). 37 refs., 3 figs.

  5. 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

  6. 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.

  7. 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

  8. Challenges of restarting Bruce Units 3 and 4 from a chemistry and materials perspective

    International Nuclear Information System (INIS)

    Roberts, J.G.; Langguth, K.

    2005-01-01

    In 2001, Bruce Power leased the Bruce Units 1-8 reactors from Ontario Power Generation. Bruce Power decided to restart Bruce Units 3 and 4 following a condition assessment of Bruce A Units 3 and 4. This paper describes the challenges that were encountered and how they were overcome, specifically for heat transport system chemistry in order to adequately protect carbon steel surfaces. The heat transport system, by design, has close inter-relations with other station systems and the related issues of some of these systems are also discussed. Considerations of material impacts have significant influences on the approach to, and control of, chemistry. Specific material impacts led to a novel, and successful, approach. This approach was arrived at following significant efforts by a multi-disciplinary team of operations, maintenance and chemistry staff. The issues, approaches considered and solutions used for a successful outcome will be presented. (author)

  9. Challenges of restarting Bruce Units 3 and 4 from a chemistry and materials perspective

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, J.G.; Langguth, K. [Bruce Power, Tiverton, Ontario (Canada)

    2005-07-01

    In 2001, Bruce Power leased the Bruce Units 1-8 reactors from Ontario Power Generation. Bruce Power decided to restart Bruce Units 3 and 4 following a condition assessment of Bruce A Units 3 and 4. This paper describes the challenges that were encountered and how they were overcome, specifically for heat transport system chemistry in order to adequately protect carbon steel surfaces. The heat transport system, by design, has close inter-relations with other station systems and the related issues of some of these systems are also discussed. Considerations of material impacts have significant influences on the approach to, and control of, chemistry. Specific material impacts led to a novel, and successful, approach. This approach was arrived at following significant efforts by a multi-disciplinary team of operations, maintenance and chemistry staff. The issues, approaches considered and solutions used for a successful outcome will be presented. (author)

  10. Bruce A refurbishment - preparatory work completed, major tasks to begin soon

    International Nuclear Information System (INIS)

    Boyd, F.

    2006-01-01

    Over the past year Bruce Power has been planning and organizing for an extensive refurbishment of the Units 1 and 2 of the Bruce A station. Now the company and its several major contractors are ready to proceed with the most challenging aspects of the actual work. The largest tasks are the replacement of the 8 steam generators and of the 480 complete fuel channels in each unit Bruce Power has created a separate website connected to their basic one to provide ongoing information about the progress of the work. The following brief note is intended to provide an outline of this challenging refurbishment program and to invite readers to visit this website to follow its progress. To provide background the writer was accorded an informative and interesting tour of the units by Rob Liddle, of Bruce Power, on September 28, 2006 the day after the ceremony commemorating the Douglas Point station held at the Bruce site. (author)

  11. 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

  12. Corrosion-product inventory: the Bruce-B secondary system

    International Nuclear Information System (INIS)

    Sawicki, J.A.; Price, J.; Brett, M.E.

    1995-01-01

    Corrosion inspection and corrosion-product characterization in water and steam systems are important for component and systems maintenance in nuclear power stations. Corrosion products are produced, released and redeposited at various sites in the secondary system. Depending on the alloys used in the condenser and feedwater heaters, particulate iron oxides and hydroxides can account for about 95-99% of the total corrosion-product transport. Where brass or cupro-nickel alloys are present, copper and zinc contribute significantly to the total transport and deposition. Particulates are transported by the feedwater to the steam generators, where they accumulate and can cause a variety of problems, such as loss of heat transfer capability through deposition on boiler tubes, blockage of flow through boiler-tube support plates and accelerated corrosion in crevices, either in deep sludge piles or at blocked tube supports. The influx of oxidized corrosion products may have a particularly adverse effect on the redox environment of steam generator tubing, thereby increasing the probability of localized corrosion and other degradation mechanisms. In this paper, there is a description of a survey of general corrosion deposits in Bruce-B, Units 5-8, which helps to identify the origin, evolution and inventory of corrosion products along the secondary system of Candu reactors

  13. 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

  14. 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)

  15. 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.)

  16. Innovations in RCM at Bruce B

    International Nuclear Information System (INIS)

    Hill, E.S.; Doyle, E.K.

    1996-01-01

    The use of RCM techniques have begun to change maintenance practice at Bruce B. This paper discusses innovative practices begun recently. Bruce B has decided to evaluate plant systems using different methods based on the effects of system failure. This approach reduces costs, by using a streamlined method, while maintaining the accuracy of analysis. In addition, the approach increases the likelihood that program recommendations will be implemented by the maintenance department by providing maintenance craft with input to the process. Bruce B has also developed techniques to accelerate the analysis process by evaluating analyses performed at other units. These innovations have been successful piloted at the station

  17. Instrument calibration optimization at Bruce Power: ECI loops

    Energy Technology Data Exchange (ETDEWEB)

    Chugh, V.; Angelova, M.; Ghias, S.; Parmar, R.; Wang, V.; Xie, H. [AMEC NSS, Toronto, Ontario (Canada); Higgs, J.; Schut, J.; Cruchley, I. [Bruce Power, Tiverton, Ontario (Canada)

    2011-07-01

    Most instruments in a nuclear power plant are calibrated at regular intervals to ensure consistency with the assumptions in the plant Technical Specifications and/or Safe Operating Envelope (SOE) compliance limits (e.g., As-Found Tolerance). In the Instrument Uncertainty Calculations (IUC), As-Found Tolerance for instrument drift is estimated based on statistical analysis of As-Found and As-Left calibration data such as that carried out for Bruce NGS by EPRI (Electric Power Research Institute) in 1998. Bruce specific drift values were found to compare favorably with industry benchmarks. Recently a significant amount of work has been done by EPRI and IAEA (International Atomic Energy Agency) on extending calibration intervals of safety related instruments. Reduction in calibration frequency reduces time commitments on the part of Authorized Nuclear Operators and safety system qualified Control Maintenance Technicians, and allows more schedule flexibility. To establish the proof of concept, As-Left/As-Found tolerances and available margins have been evaluated for the Bruce B Emergency Coolant Injection (ECI) system instrument loops to determine whether an extension of the calibration period from one or two year to three years is justifiable on the basis that these loops will still be in compliance with SOE. The analysis showed that 60% of instruments in the ECI system are qualified for calibration interval extension up to three years. Sensitivity assessment of the effect of proposed changes in calibration intervals for 60% of the instruments on the ECI system unavailability has also been performed using the current Bruce Power ECI unavailability model. The results show that, the largest ECI Predicted Future Unavailability (PFU) is 9.2E-4 year/year for in-core LOCA accident. This value is still below the target unavailability of 1.0E-3 year/year. (author)

  18. Instrument calibration optimization at Bruce Power: ECI loops

    International Nuclear Information System (INIS)

    Chugh, V.; Angelova, M.; Ghias, S.; Parmar, R.; Wang, V.; Xie, H.; Higgs, J.; Schut, J.; Cruchley, I.

    2011-01-01

    Most instruments in a nuclear power plant are calibrated at regular intervals to ensure consistency with the assumptions in the plant Technical Specifications and/or Safe Operating Envelope (SOE) compliance limits (e.g., As-Found Tolerance). In the Instrument Uncertainty Calculations (IUC), As-Found Tolerance for instrument drift is estimated based on statistical analysis of As-Found and As-Left calibration data such as that carried out for Bruce NGS by EPRI (Electric Power Research Institute) in 1998. Bruce specific drift values were found to compare favorably with industry benchmarks. Recently a significant amount of work has been done by EPRI and IAEA (International Atomic Energy Agency) on extending calibration intervals of safety related instruments. Reduction in calibration frequency reduces time commitments on the part of Authorized Nuclear Operators and safety system qualified Control Maintenance Technicians, and allows more schedule flexibility. To establish the proof of concept, As-Left/As-Found tolerances and available margins have been evaluated for the Bruce B Emergency Coolant Injection (ECI) system instrument loops to determine whether an extension of the calibration period from one or two year to three years is justifiable on the basis that these loops will still be in compliance with SOE. The analysis showed that 60% of instruments in the ECI system are qualified for calibration interval extension up to three years. Sensitivity assessment of the effect of proposed changes in calibration intervals for 60% of the instruments on the ECI system unavailability has also been performed using the current Bruce Power ECI unavailability model. The results show that, the largest ECI Predicted Future Unavailability (PFU) is 9.2E-4 year/year for in-core LOCA accident. This value is still below the target unavailability of 1.0E-3 year/year. (author)

  19. 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

  20. Flux distribution measurements in the Bruce A unit 1 reactor

    International Nuclear Information System (INIS)

    Okazaki, A.; Kettner, D.A.; Mohindra, V.K.

    1977-07-01

    Flux distribution measurements were made by copper wire activation during low power commissioning of the unit 1 reactor of the Bruce A generating station. The distribution was measured along one diameter near the axial and horizontal midplanes of the reactor core. The activity distribution along the copper wire was measured by wire scanners with NaI detectors. The experiments were made for five configurations of reactivity control mechanisms. (author)

  1. 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.)

  2. 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.)

  3. 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.)

  4. Regional and site geological frameworks : proposed Deep Geologic Repository, Bruce County, Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Raven, K.; Sterling, S.; Gaines, S.; Wigston, A. [Intera Engineering Ltd., Ottawa, ON (Canada); Frizzell, R. [Nuclear Waste Management Organization, Toronto, ON (Canada)

    2009-07-01

    The Nuclear Waste Management Organization is conducting geoscientific studies on behalf of Ontario Power Generation into the proposed development of a Deep Geologic Repository (DGR) for low and intermediate level radioactive waste (L and ILW) at the Bruce site, near Tiverton, Ontario. This paper presented a regional geological framework for the site that was based on a review of regional drilling; structural geology; paleozoic stratigraphy and sedimentology; a 3D geological framework model; a DGR geological site characterization model; bedrock stratigraphy and marker beds; natural fracture frequency data; and formation predictability. The studies have shown that the depth, thickness, orientation and rock quality of the 34 rock formations, members or units that comprise the 840 m thick Paleozoic bedrock sequence at the Bruce site are very uniform and predictable over distances of several kilometres. The proposed DGR will be constructed as an engineered facility comprising a series of underground emplacement rooms at a depth of 680 metres below ground within argillaceous limestones. The geoscientific studies are meant to provide a basis for the development of descriptive geological, hydrogeological and geomechanical models of the DGR site that will facilitate environmental and safety assessments. 11 refs., 3 tabs., 9 figs.

  5. Performance of Bruce natural UO2 fuel irradiated to extended burnups

    International Nuclear Information System (INIS)

    Zhou, Y.N.; Floyd, M.R.; Ryz, M.A.

    1995-11-01

    Bruce-type bundles XY, AAH and GF were successfully irradiated in the NRU reactor at Chalk River Laboratories to outer-element burnups of 570-900 MWh/kgU. These bundles were of the Bruce Nuclear Generating Station (NGS)-A 'first-charge' design that contained gas plenums in the outer elements. The maximum outer-element linear powers were 33-37 kW/m. Post-irradiation examination of these bundles confirmed that all the elements were intact. Bundles XY and AAH, irradiated to outer-element burnups of 570-700 MWh/kgU, experienced low fission-gas release (FGR) ( 500 MWh/kgU (equivalent to bundle-average 450 MWh/kgU) when maximum outer-element linear powers are > 50 kW/m. The analysis in this paper suggests that CANDU 37-element fuel can be successfully irradiated (low-FGR/defect-free) to burnups of at least 700 MWh/kgU, provided maximum power do not exceed 40 kW/m. (author). 5 refs., 1 tab., 8 figs

  6. 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

  7. 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.)

  8. 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

  9. Kenyan Young Generation in Nuclear

    International Nuclear Information System (INIS)

    Chesori, R.

    2017-01-01

    KYGN Educates, informs, promotes and facilitate transfer of knowledge on peaceful, safe and secure uses of nuclear science and technology in Kenya. A network of young scientists and students with special interest in the nuclear science and allied fields. It is an affiliate of the IYNC whose membership is drawn from member states of United Nations

  10. 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.)

  11. 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

  12. 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.)

  13. Nuclear fuel element recovery using PEDSCO RMI Unit

    International Nuclear Information System (INIS)

    Martin, D.G.; Pedersen, B.V.

    1984-01-01

    In September 1982, a PEDSCO Remote Mobile Investigation Unit was used to recover damaged irradiated fuel elements from a fueling machine and trolley deck at Bruce Nuclear Generating Station 'A'. This Canadian-made remote controlled vehicle was originally designed for explosive ordinance disposal by law enforcement agencies. This paper describes its adaptation to nuclear service and its first mission, within a nuclear facility

  14. 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

  15. 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.

  16. 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.)

  17. After reliability centred maintenance. Preventive maintenance living program implementation at Bruce Power

    International Nuclear Information System (INIS)

    Harazim, Michael L.; Ferguson, Brian J.

    2003-01-01

    Industrial preventive maintenance (PM) programs represent a large part of plant O and M costs. PM Optimization (PMO) projects represent an effective mechanism for identifying unnecessary PM, extending PM intervals and infusing predictive maintenance (PdM) methods. However, once optimized, what process prevents the PM program from returning to a state of disarray? This is the function of a PM living program (PMLP). In 1997, an independent performance assessment identified concerns with the applicability and effectiveness of all Ontario Power Generation, Inc. (OPGI) PM programs. In response, OPGI instituted an Integrated Maintenance Program (IMP) including Reliability Centred Maintenance (RCM) and a PMLP. It should be noted that the PMLP was developed for the 3 OPGI nuclear Sites (i.e. Bruce, Pickering, and Darlington). Effective 1 May 2001, the Bruce Site has been leased to a group of investors lead by British Energy. This paper is written in historical context and therefore refers to the Bruce Site as part of OPGI. The PMLP is made up of five elements: 1) process control, 2) change control, 3) worker feedback, 4) program performance metrics, and 5) deferral module. A PMLP software tool, originally applied to Duke Energy nuclear plants, was enhanced and customized specifically for the OPGI PMLP, and then implemented at all three of OPGI's nuclear sites. The objective of the OPGI PMLP was to: Provide processes/procedures for continual optimization of all site PM tasks, Ensure effective and timely revision of PM tasks in the work management system, Ensure PM tasks remain applicable/effective at all times, Maintain and enhance PM consistency on a component, system and Site basis, Ensure that new predictive maintenance techniques are applied and integrated with the PM program, Ensure that mandated PM tasks are identified and executed, Provide a mechanism for craft feedback, Meet regulatory requirements for PM program effectiveness, and Provide PM task deferral

  18. 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)

  19. 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

  20. 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

  1. 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

  2. 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

  3. Ergonomics and nuclear power generation

    International Nuclear Information System (INIS)

    Beyers, C.J.; Bogie, K.D.

    1986-01-01

    The design and construction of nuclear power plants are executed to rigorous standards of safety and reliability. Similarly the human interface within the nuclear power plant must meet very high standards, and these must be demonstrated to be maintained and assured through time. The control room, as the operating nerve-centre of the plant, carries a large part of this responsibility. It is the work space dimension within which the operator-instrumentation interface must function as efficiently as possible. This paper provides an overview of how ergonomics has been used as a major tool in reshaping the man-machine interface within the control room in the interest of safety and reliability. Topics covered in the paper include workspace design, control panel layout, demarcation and labelling, switch and meter types, and annunciated and unannunciated alarms

  4. New generation of nuclear reactors

    International Nuclear Information System (INIS)

    Chwaszczewski, S.

    2000-01-01

    The development trends of the construction of nuclear reactors has been performed on the background of worldwide electricity demand for now and predicted for future. The social acceptance, political and economical circumstances has been also taken into account. Seems to Electric Power Research Institute (US) and other national authorities the advanced light water reactors have the best features and chances for further development and commercial applications in future

  5. 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.)

  6. 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

  7. New generation nuclear microprobe systems

    International Nuclear Information System (INIS)

    Jamieson, David N.

    2001-01-01

    Over the past 20 years, the minimum probe size for nuclear microscopy has stayed around 1 μm with only a few groups reporting a sub-micron probe size around 0.5 μm. No breakthroughs in nuclear microprobe design have been forthcoming to produce dramatic improvements in spatial resolution. The difficulties of breaking the constraints that are preventing reduction of the probe size have been well recognised in the past. Over the past 5 years it has become clear that some of these constraints may not be as limiting as first thought. For example, chromatic aberration clearly is not as significant as implied from first-order ion optics calculations. This paper reviews the constraints in view of the increased understanding of the past 5 years and looks at several new approaches, presently being evaluated in Melbourne and elsewhere, on how to make progress. These approaches include modified RF ion sources for improved beam brightness and exploitation of relaxed constraints on some lens aberrations allowing the use of high demagnification probe forming lens systems

  8. 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)

  9. Bruce A units 1 and 2 restart project

    International Nuclear Information System (INIS)

    Routledge, K.

    2006-01-01

    This presentation provides an overview of the Bruce A Units 1 and 2 Restart project from the vantage point of the Project Management Contractor (PMC). The presentation will highlight the unique structure of the project, which has been designed to maximize project efficiencies while minimizing the impact to the Bruce Power operational reactors. Efficiency improvements covered in the presentation includes: support services provided to the direct work contractors, radiation protection, worker protection, engineering, field execution, maintenance and facilities. The presentation focusses on the roles of the PMC in helping to ensure the successful outcome of this ambitious reactor refurbishment project. In addition, the Construction Island concept that has been implemented on the project will be presented, with some of the innovative thinking that has gone into its creation. The organization of the PMC and an overview of the project schedule is also presented. AMEC NCL is a privately held consultancy in the Canadian nuclear industry which provides experienced and flexible multi-disciplined resources to support full project management, engineering solutions and safety consultancy services throughout the life cycle of nuclear facilities in Canada, and for customers in related markets in North America and overseas. AMEC NCL is a wholly-owned subsidiary of AMEC plc

  10. Bruce NGS a loss of flow analysis for effectiveness of level 2 defence-in-depth provisions

    International Nuclear Information System (INIS)

    Won, W.; Jiang, Y.; Kwee, M.; Xue, J.

    2014-01-01

    The concept of defence-in-depth is applied to CANDU (CANada Deuterium Uranium) reactor designs and operations to provide series of levels of defence to prevent accidents progressing and to provide protection for reactor and public safety. The level 2 defence-in-depth provisions are designed to detect and intercept deviation from normal operation in order to prevent anticipated operating occurrences (AOOs) from escalating to accident conditions, and to return the plant to a state of normal operations, according to the Canada Nuclear Safety Commission (CNSC) regulatory document RD-337. Historically, safety analysis has focused on the effectiveness of level 3 defence-in-depth provisions in accident conditions, and the effectiveness of level 2 defence-in-depth has not been assessed. In this study, the effectiveness of Level 2 defence-in-depth is assessed for loss of flow (LOF) events for Bruce Nuclear Generating Station (NGS) A reactors. The level 2 defence-in-depth in Bruce NGS A design is identified to be the stepback function of reactor regulating system (RRS). The behavior of RRS stepback following the initiation of loss of flow event is simulated using RFSP/TUF/RRS - em coupled code. The behavior of full system and single channel is simulated and assessed against the acceptance criteria - fitness for service of systems, structures and components (SSCs). (author)

  11. Bruce NGS a loss of flow analysis for effectiveness of level 2 defence-in-depth provisions

    Energy Technology Data Exchange (ETDEWEB)

    Won, W. [AMEC NSS, Toronto, ON (Canada); Jiang, Y.; Kwee, M.; Xue, J. [Bruce Power, Toronto, ON (Canada)

    2014-07-01

    The concept of defence-in-depth is applied to CANDU (CANada Deuterium Uranium) reactor designs and operations to provide series of levels of defence to prevent accidents progressing and to provide protection for reactor and public safety. The level 2 defence-in-depth provisions are designed to detect and intercept deviation from normal operation in order to prevent anticipated operating occurrences (AOOs) from escalating to accident conditions, and to return the plant to a state of normal operations, according to the Canada Nuclear Safety Commission (CNSC) regulatory document RD-337. Historically, safety analysis has focused on the effectiveness of level 3 defence-in-depth provisions in accident conditions, and the effectiveness of level 2 defence-in-depth has not been assessed. In this study, the effectiveness of Level 2 defence-in-depth is assessed for loss of flow (LOF) events for Bruce Nuclear Generating Station (NGS) A reactors. The level 2 defence-in-depth in Bruce NGS A design is identified to be the stepback function of reactor regulating system (RRS). The behavior of RRS stepback following the initiation of loss of flow event is simulated using RFSP/TUF/RRS{sub -}em coupled code. The behavior of full system and single channel is simulated and assessed against the acceptance criteria - fitness for service of systems, structures and components (SSCs). (author)

  12. 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)

  13. Steam generator for nuclear reactors

    International Nuclear Information System (INIS)

    Byerley, W.M.; Bennett, R.R.

    1978-01-01

    In the steam generator, the primary medium is led through a U-shaped tube bundle heating up a secondary medium (feedwater) which flows around the tube bundle via a preheating chamber. In order to optimize heat transfer inside the preheating chamber, the feedwater is separated into a counterflow and a parallel flow with regard to the primary medium by means of partitioning walls and deflectors. The ratio is 70/30%. This way, boiling in the preheater is avoided, i.e. the high LMTD (logaritmic mean temperature difference) is fully utilized. (DG) [de

  14. 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)

  15. 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

  16. 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.

  17. 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

  18. 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)

  19. 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

  20. 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.)

  1. 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

  2. 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

  3. Design of the MiniSLAR system for Bruce A

    International Nuclear Information System (INIS)

    Gray, M.G.

    1995-01-01

    Cancellation of Bruce A Retube created the need to perform SLAR on Unit 1. The existing SLAR system cannot reach Unit 1 and alternative systems had limitations. The concept and design of MiniSLAR were driven by the availability of existing components made for Retube. The MiniSLAR concept was developed by a team with members representing operators, technicians, and designers from various departments within Ontario Hydro and GE Canada. Overall project leadership was provided by Bruce A Projects and Modifications Department with assistance from Ontario Hydro Nuclear Technology Services. The responsibility for detailed design was assigned by Ontario Hydro to GE Canada. The detailed design proceeded with continual input and review by the team. The MiniSLAR delivery machine consists of a closure removal ram, a shield plug removal ram and a SLAR tool delivery ram attached to the sliding plate of a horizontal indexing mechanism. The moving plate is constrained by guide rails to a fixed plate and seals against it with o-rings. A snout and clamping mechanism mounts on the front of the fixed plate. The machine mounts atop a work table which provides the various motions required for endfitting engagement. Some operations are performed manually while others are remote and automatic. (author)

  4. 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

  5. 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)

  6. 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

  7. 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)

  8. 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.

  9. 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.)

  10. Nuclear safety in the next century

    Energy Technology Data Exchange (ETDEWEB)

    Meneley, D A [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

    1993-12-31

    Can nuclear plants b made safe enough to be suitable for worldwide large-scale use? Can the radioactive wastes generated be safely managed over long terms? This paper addresses these questions from a vantage point within the nuclear industry. It also provides a scenario of the possible development over the next century of the Bruce nuclear energy centre on Lake Huron as an illustration of why it is worthwhile to further nuclear technology. (author). 4 figs.

  11. Geoscientific Characterization of the Bruce Site, Tiverton, Ontario

    Science.gov (United States)

    Raven, K.; Jackson, R.; Avis, J.; Clark, I.; Jensen, M.

    2009-05-01

    Ontario Power Generation is proposing a Deep Geologic Repository (DGR) for the long-term management of its Low and Intermediate Level Radioactive Waste (L&ILW) within a Paleozoic-age sedimentary sequence beneath the Bruce site near Tiverton, Ontario, Canada. The concept envisions that the DGR would be excavated at a depth of approximately 680 m within the Ordovician Cobourg Formation, a massive, dense, low- permeability, argillaceous limestone. Characterization of the Bruce site for waste disposal is being conducted in accordance with a four year multi-phase Geoscientific Site Characterization Plan (GSCP). The GSCP, initially developed in 2006 and later revised in 2008 to account for acquired site knowledge based on successful completion of Phase I investigations, describes the tools and methods selected for geological, hydrogeological and geomechanical site characterization. The GSCP was developed, in part, on an assessment of geoscience data needs and collection methods, review of the results of detailed geoscientific studies completed in the same bedrock formations found off the Bruce site, and recent international experience in geoscientific characterization of similar sedimentary rocks for long-term radioactive waste management purposes. Field and laboratory work related to Phase 1 and Phase 2A are nearing completion and have focused on the drilling, testing and monitoring of four continuously cored vertical boreholes through Devonian, Silurian, Ordovician and Cambrian bedrock to depths of about 860 mBGS. Work in 2009 will focus on drilling and testing of inclined boreholes to assess presence of vertical structure. The available geological, hydrogeological and hydrogeochemical data indicate the presence of remarkably uniform and predictable geology, physical hydrogeologic and geochemical properties over well separation distances exceeding 1 km. The current data set including 2-D seismic reflection surveys, field and lab hydraulic testing, lab petrophysical and

  12. 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)

  13. 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

  14. Bruce Unit 2 lay-up engineering assessment

    International Nuclear Information System (INIS)

    Iley, D.

    1995-01-01

    The overall lay-up program initiated as a result of the strategic decision to shut down Bruce A unit 2 is briefly described as an introduction to the engineering assessment of the unit 2 systems. The assessment has identified the need to prepare 67 system and 9 equipment lay-up specifications. A summary of the selected system specifications is described. A complete summary and the specifications and the status of unit 2 systems and equipment required to support lay-up and/or the other three operating units is available on request due to the volume of the information. Some logistical details of the lay-up implementation plans, results, and problems to date demonstrate the complexity of the lay-up requirements for a nuclear unit in a multi-unit CANDU station. (author)

  15. 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

  16. 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

  17. 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

  18. 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.)

  19. 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)

  20. 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

  1. 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

  2. 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.

  3. 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)

  4. 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.

  5. 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

  6. 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)

  7. Bruce unit 1 moderator to end shield cooling leak repairs

    Energy Technology Data Exchange (ETDEWEB)

    Boucher, P; Ashton, A [Ontario Hydro, Tiverton, ON (Canada). Bruce Nuclear Generating Station-A

    1996-12-31

    In October 1994, a leak developed between the heavy water Moderator System and the light water End Shield Cooling System at Ontario Hydro`s Bruce A Generating Station Unit 1. The interface between these two systems consists of numerous reactor components all within the reactor vessel. This paper describes the initial discovery and determination of the leak source. The techniques used to pinpoint the leak location are described. The repair strategies and details are outlined. Flushing and refilling of the Moderator system are discussed. The current status of the Unit 1 End Shield Cooling System is given with possible remedial measures for clean-up. Recommendations and observations are provided for future references. (author). 7 figs.

  8. 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

  9. 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

  10. 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.

  11. 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

  12. 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.

  13. 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)

  14. 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.

  15. 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

  16. 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

  17. 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...

  18. Chemistry control at Bruce NGS 'B' from constructed to commercial operation

    International Nuclear Information System (INIS)

    Roberts, J.G.

    1987-01-01

    Pre-operational storage chemistry and flushing of the secondary side is described. The approach devised for Bruce NGS 'B' Unit 6 was unique for an Ontario Hydro Nuclear Unit. The significance of the improved Construction installation and Quality Assurance procedures, combined with those of Operations is identified. Secondary side chemistry during both commissioning and later operation is reported. It will be shown that the application of ALARA (As Low As is Reasonably Achievable) concept has resulted in tighter chemical specifications being met

  19. 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.)

  20. Ion chamber repairs in Bruce A

    International Nuclear Information System (INIS)

    Millard, J.; Edwards, T.; Kerker, J.; Pletch, R.; Edwards, T.

    2012-01-01

    This paper discusses identification and successful remediation of leakage of shield tank water on vertical and horizontal Ion Chambers in Bruce A. In doing so, it discusses real events moving from the initial investigation to understand the problem, through looking at options for solutions, and moving to site work and actual resolution.. In multiunit 900 MW class CANDU® reactors, the calandria vessel is suspended within a larger shield tank. Due to temperature changes or changes in moderator fluid levels in the calandria, the calandria can move relative to the shield tank and its reactivity deck. Thimbles which contain the reactivity sensors and controls connect the two vessels and allow the reactivity drives and controls connections to be placed on the deck structure on the top of the reactor assembly for RRS and SDS1 and horizontally for SDS2. These thimbles have expansion joints with metal bellows where they meet the deck structure or shield tank walls. The deck structure lies on a vault containment boundary. The horizontal ion chambers are not in the containment boundary as they connect the outside of the calandria and shield tank around mid plane in the reactor vault, but due to geometry difference provides a more challenging work environment. Bruce had a beetle alarm (1-63851-MIA2-ME30 in alarm state (vertical IC housing)) at the start of April 2012 on Unit 1 channel F vertical Ion chamber expansion joint at the deck connection. This occurred after the moderator levels had been raised after the several years long refurbishment outage and the expansion joint had a significant travel. The investigation showed shield tank water in the collection chamber at the beetle. In addition, Channel J of the horizontal ion chamber had a seized instrument, which on removal was found to relate to oxide build up as a result of minor water leakage into the site. Repairs in both cases were performed as part of the long Bruce 1 & 2 refurbishment outage to completely stop the

  1. 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...

  2. 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

  3. Fuelling with flow at Bruce A

    Energy Technology Data Exchange (ETDEWEB)

    Gray, M G [Canadian General Electric Co. Ltd., Peterborough, ON (Canada)

    1997-12-31

    Fuelling with flow is the solution chosen by Bruce A to overcome the potential power pulse caused by a major inlet header failure. Fuelling with flow solves the problem by rearranging the core to place new fuel at the channel inlet and irradiated fuel at the channel outlet. The change has a significant impact on the Bruce A fuel handling system which was designed primarily to do on power fuelling in the against flow direction. Mechanical changes to the fuelling machine include a modification to the existing ram head and the replacement of standard fuel carriers with new fuelling with flow fuel carriers having the capability of opening the channel latch. Changes to the control system are more involved. A new set of operational sequences are required for both the upstream and downstream fuelling machines to achieve the fuel change. Steps based on sensitive ram push are added to reduce the risk of failing to close the latch at the correct position to properly support the fuel string. Changes are also required to the protective interlocks to allow fuelling with flow and reduce risk. A new fuel string supporting shield plug was designed and tested to reduce the risk of endplate cracking that could occur on the irradiated bundle that would have been supported directly by the channel latch. Some operational changes have been incorporated to accommodate this new shield plug. Considerable testing has been carried out on all aspects of fuel handling where fuelling with flow differs from the reference fuelling against flow. (author). 3 figs.

  4. 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)

  5. Nuclear power

    International Nuclear Information System (INIS)

    Porter, Arthur.

    1980-01-01

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

  6. 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)

  7. 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.)

  8. Business health reporting process at Bruce Power helps drive successful plant performance

    International Nuclear Information System (INIS)

    Krane, J.C.

    2007-01-01

    Developing and implementing consistent and comprehensive measures of performance on a large multi-reactor unit nuclear power plant site is a significant challenge. Linking these performance measures back to licence compliance standards and all aspects of the operations, engineering, maintenance and support activities is needed to ensure cohesive site-wide safe operations and satisfy regulatory needs. At Bruce Power, Canada's largest independently-owned nuclear power producer, a Business Health reporting process has been developed to provide a standardized performance rating scheme. The reporting process ties all self assessment activities to common management principles and process structure areas that comprise the Bruce Power Management System. The principles used for performance ratings link directly back to the operating licenses and the primary referenced management system standard. The Business Health reporting process provides a natural business and regulatory oversight framework report that is easily understood and consistently measured over time. The rating data is derived from easily understood quantitative and qualitative descriptions that can be trended over time. The results derived from semi-annual Business Health reports provide an ongoing overall measure of Bruce Power's management system effectiveness for enabling and sustaining required business results and high standards of safety. (author)

  9. Next-generation Nuclear Data Web Services

    Energy Technology Data Exchange (ETDEWEB)

    Sonzogni, A.A. [National Nuclear Data Center, Building 197D, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)

    2005-07-25

    The National Nuclear Data Center collects, evaluates, and disseminates nuclear physics data for basic nuclear research and applied nuclear technologies. We have recently produced a nuclear data portal featuring modern and powerful servers, relational database software, Linux operating system, and Java programming language. The portal includes nuclear structure, decay and reaction data, as well as literature information. Data can be searched for using optimized query forms; results are presented in tables and interactive plots. Additionally, a number of nuclear science tools, codes, applications, and links are provided. A brief tutorial of the different databases and products will be provided.

  10. Next-generation Nuclear Data Web Services

    International Nuclear Information System (INIS)

    Sonzogni, A.A.

    2005-01-01

    The National Nuclear Data Center collects, evaluates, and disseminates nuclear physics data for basic nuclear research and applied nuclear technologies. We have recently produced a nuclear data portal featuring modern and powerful servers, relational database software, Linux operating system, and Java programming language. The portal includes nuclear structure, decay and reaction data, as well as literature information. Data can be searched for using optimized query forms; results are presented in tables and interactive plots. Additionally, a number of nuclear science tools, codes, applications, and links are provided. A brief tutorial of the different databases and products will be provided

  11. Equipment transporter for nuclear steam generator

    International Nuclear Information System (INIS)

    Hayes, L.R.

    1987-01-01

    A transporter is described for use in a steam generator of a nuclear power installation. The generator is essentially a heat exchanger having a vertically extended shell. Across the lower portion extends a horizontal tube sheet having an upper surface which supports a bundle of vertically extending tubes forming a limited annular space with the inside of the shell wall and the upper surface. An opening of limited dimensions through the shell wall gains manual access to the limited annular space. The transporter has means for locating and removing solid debris from the upper surface of the tube sheet in the annular space and has a means for assembly and disassembly of the transporter so that it may be manually passed through the shell opening to and from a position on the upper surface of the tube sheet in the annular space. The transporter includes: a body; at least three wheels mounted on the body for engaging the upper surface of the tube sheet; a first motor mounted on the body drivingly connected to the wheels for moving the transporter along the upper surface of the tube sheet in the annular space; a remotely operated means on the body for locating solid debris on the upper surface of the tube sheet; and means for securing and removing solid debris on the upper surface of the tube sheet located by the means for locating

  12. 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)

  13. Restoration to serviceability of Bruce 'A' heat transfer equipment

    International Nuclear Information System (INIS)

    Gammage, D.; Machowski, C.; McGillivray, R.; Durance, D.; Kazimer, D.; Werner, K.

    2009-01-01

    Bruce Units 1 to 4 were shut down during the 1990s by the former Ontario Hydro, due in part to a long list of system and equipment deficiencies and concerns, including steam generator tube degradation as a consequence of the then-existing steam generator secondary side water chemistry conditions. Upon its creation in 2001, and following a program of condition assessment, Bruce Power was able to determine that Units 3 and 4 could return to service; but that Units 1 and 2 would require refurbishment. That Refurbishment Program, which is currently well advanced, included the re-assessment of the condition of equipment throughout the plant including the heat transfer equipment; and determination item-by-item as to what inspection, cleaning, repair, or even replacement would be required to put the equipment into a condition where it could be expected to operate reliably for the additional 30 years expected from the plant. Clearly the objective is to suitably restore the equipment to serviceability without doing more refurbishment work than is warranted - without replacing equipment except where absolutely necessary. The first task in such a program is determination of its scope - i.e. a listing of all heat exchangers. That list included everything from the steam generators (which required replacement, now completed), to much smaller heat exchangers in the heavy water upgrader systems (which were found to be in very good overall condition). There is also a very large number of other so-called 'balance-of-plant' heat exchangers; these include the maintenance coolers, moderator heat exchangers, shutdown coolers and a whole raft of smaller coolers - many of which are cooled directly by lake water with its potential for bio-fouling and 'BIC' (Biologically Induced Corrosion). This paper focuses primarily on the engineering assessment, inspection, repair and general refurbishment of the balance-of-plant heat exchangers. As will be discussed in the paper, the assessment of the

  14. 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)

  15. 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.

  16. 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.

  17. 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

  18. 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

  19. Methyl iodide trapping efficiency of aged charcoal samples from Bruce-A emergency filtered air discharge systems

    International Nuclear Information System (INIS)

    Wren, J.C.; Moore, C.J.; Rasmussenn, M.T.; Weaver, K.R.

    1999-01-01

    Charcoal filters are installed in the emergency filtered air discharge system (EFADS) of multiunit stations to control the release of airborne radioiodine in the event of a reactor accident. These filters use highly activated charcoal impregnated with triethylenediamine (TEDA). The TEDA-impregnated charcoal is highly efficient in removing radioiodine from flowing airstreams. The iodine-removal efficiency of the charcoal is presumed to deteriorate slowly with age, but current knowledge of this effect is insufficient to predict with confidence the performance of aged charcoal following an accident. Experiments were performed to determine the methyl iodide removal efficiency of aged charcoal samples taken from the EFADS of Ontario Hydro's Bruce-A nuclear generating station. The charcoal had been in service for ∼4 yr. The adsorption rate constant and capacity were measured under post-loss-of-coolant accident conditions to determine the efficiency of the aged charcoal. The adsorption rate constants of the aged charcoal samples were observed to be extremely high, yielding a decontamination factor (DF) for a 20-cm-deep bed of the aged charcoal >1 X 10 15 . The results show that essentially no CH 3 I would escape from a 20-cm-deep bed of the aged charcoal and that the requirement for a DF of 1000 for organic iodides in the EFADS filters would be exceeded by a tremendous margin. With such high DFs, the release of iodine from a 20-cm-deep bed would be virtually impossible to detect. The adsorption capacities observed for the aged charcoal samples approach the theoretical chemisorption capacity of 5 wt% TEDA charcoal, indicating that aging in the EFADS for 4 yr has had a negligible impact on the adsorption capacity. The results indicate that the short- and long-term performances of the aged charcoal in the EFADS of Bruce-A following an accident would still far exceed performance requirements. (author)

  20. Nuclear Knowledge Management Programmes for Young Generations

    International Nuclear Information System (INIS)

    De Grosbois, John

    2017-01-01

    The Future of Nuclear Energy: Today’s Challenges - •Climate change •Investment in renewables •Societal acceptance of nuclear energy •Nuclear R&D declining •Aging reactor fleets •Phase-outs •Pace of new builds •Future uncertainties. Future Opportunities - •Shift to smart energy grids •Carbon tax and “cap and trade” systems •Possible need for new nuclear energy solutions: –high temperature reactors –hybrids → steam reforming –smaller plants needed –minimized nuclear waste –inherently safe designs. Supporting TC’s “Strategic Capacity Building Approach” (SCBA) by Strengthening Sustainable National Nuclear Education Systems: Knowledge sharing & eLearning platforms (e.g. CLP4NET) and supporting tools → Regional Nuclear Education Networks; → National Nuclear Education Networks; → Stakeholder Networking for Human Resource and Knowledge Development

  1. Nuclear reactors for electric power generation

    International Nuclear Information System (INIS)

    Hoogenboom, J.E.

    1987-01-01

    In this article the operation of a nuclear power plant, the status quo about the application of nuclear energy in the world are explained, the subjects of discussion between supporters and adversaries nowadays and the prospects for prolonged usage of nuclear power are summarized, viewed from the actual technical possibilities. 2 refs.; 7 figs.; 2 tabs

  2. 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)

  3. 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.)

  4. Next Generation Nuclear Plant GAP Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

    2008-12-01

    As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

  5. Lawsuits concerning nuclear power generation in FRG

    International Nuclear Information System (INIS)

    Saito, Osamu

    1980-01-01

    The confirmation of the courts of justice is required for the permission of power stations. This proposition is not in the laws in FRG, but in view of the recent judicatory regulation, it seems to be the norm established experimentally. From the character of German nation, more than 40 specialists and the committees independent of administration take part in the procedure of administrative permission, but considering the temporary procedure, the processes of five classes of courts join in these. Based on the background of such situation, the author outlined the traditional practice in the legislation and administration in the field of nuclear power generation, then investigated into the decisions of Freiburg and Wuerzburg courts of administrative litigation in 1977 and the decision of the federal constitutional court in 1978. Confronting the same technology of light water reactors, the Freiburg court said that the device protecting from the burst of a pressure vessel is necessary, but the Wuerzburg court did not demand it. The confrontations similar to it were seen in the requirements for the utilization of radioactive substances and the final storage of them. The recent decision of the federal constitutional court is concerned with FBRs, and the court discussed the problem of ''residual risks''. The studies on the German decisions are useful for Japan. (Kako, I.)

  6. Measurements of Sheath Temperature Profiles in Bruce LVRF Bundles Under Post-Dryout Heat Transfer Conditions in Freon

    International Nuclear Information System (INIS)

    Guo, Y.; Bullock, D.E.; Pioro, I.L.; Martin, J.

    2006-01-01

    An experimental program has been completed to study the behaviour of sheath wall temperatures in the Bruce Power Station Low Void Reactivity Fuel (shortened hereafter to Bruce LVRF) bundles under post-dryout (PDO) heat-transfer conditions. The experiment was conducted with an electrically heated simulator of a string of nine Bruce LVRF bundles, installed in the MR-3 Freon heat transfer loop at the Chalk River Laboratories (CRL), Atomic Energy of Canada Limited (AECL). The loop used Freon R-134a as a coolant to simulate typical flow conditions in CANDU R nuclear power stations. The simulator had an axially uniform heat flux profile. Two radial heat flux profiles were tested: a fresh Bruce LVRF profile and a fresh natural uranium (NU) profile. For a given set of flow conditions, the channel power was set above the critical power to achieve dryout, while heater-element wall temperatures were recorded at various overpower levels using sliding thermocouples. The maximum experimental overpower achieved was 64%. For the conditions tested, the results showed that initial dryout occurred at an inner-ring element at low flows and an outer-ring element facing internal subchannels at high flows. Dry-patches (regions of dryout) spread with increasing channel power; maximum wall temperatures were observed at the downstream end of the simulator, and immediately upstream of the mid-bundle spacer plane. In general, maximum wall temperatures were observed at the outer-ring elements facing the internal subchannels. The maximum water-equivalent temperature obtained in the test, at an overpower level of 64%, was significantly below the acceptable maximum temperature, indicating that the integrity of the Bruce LVRF will be maintained at PDO conditions. Therefore, the Bruce LVRF exhibits good PDO heat transfer performance. (authors)

  7. 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)

  8. 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)

  9. 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

  10. 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.)

  11. 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.)

  12. Global movement in reviewing nuclear power generation

    International Nuclear Information System (INIS)

    Kimura, Yoshiyasu

    2007-01-01

    The price of crude oil, natural gas and coal has increased since 2004 with the rapid increase of primary energy demand in China, India and other developing countries. Moreover due to the political uncertainty in the Middle East, and the state control of energy resources in countries like Russia, the issue of energy security has become a critical issue. Nuclear power has been reconsidered in recent years in the US and European countries, because nuclear power is one of the cheapest sources of low carbon energy and also has relatively stable costs, and is thereby useful to energy security and to prevent climate change. Electricity demand is growing very rapidly in China and additional reactors are planned to give a fivefold increase in nuclear capacity to 40,000 MWe by 2020. India has a largely indigenous nuclear power program and expects to have 20,000 MWe nuclear capacity by 2020. Russia is moving steadily forward with plans for a much expanded role of nuclear energy, and the restructuring of nuclear industries has begun to strengthen competitiveness in international nuclear markets. (author)

  13. 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)

  14. Worldwide experience in nuclear power generation

    International Nuclear Information System (INIS)

    Stueger, R.; Krejsa, P.; Putz, F.

    1982-01-01

    Five years after their own big conference on nuclear energy and the nuclear fuel cycle of 1977 in Salzburg, and one year before the new Geneva conference planned by the United Nations, the International Atomic Energy Organization (IAEO) organized from 13. to 17.9.82 in Vienna in connection with their 25 years' existence an international conference on nuclear power experience. The NPE differs from other big international conferences of the present year and the last years with similar overall topics mainly by the fact that the Soviet Union and other Eastern countries as well as a great number of developing countries were very much represented, with contributions. (orig.) [de

  15. 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.

  16. 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.

  17. 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)

  18. 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.

  19. 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.)

  20. Nuclear Power's Role in Generating Electricity

    National Research Council Canada - National Science Library

    Falk, Justin

    2008-01-01

    This study assesses the commercial viability of advanced nuclear technology as a means of meeting future demand for electricity by comparing the costs of producing electricity from different sources...

  1. 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)

  2. 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)

  3. Nuclear energy resources for electrical power generation

    International Nuclear Information System (INIS)

    Alder, K.F.

    1974-01-01

    'Nuclear Energy Resources' is interpreted as the nuclear power systems currently available commercially and those at an advanced stage of development, together with full and associated resources required to implement large-scale nuclear programs. Technical advantages and disadvantages of the established power reactor systems are reviewed, and the uranium fuel situation is outlined in terms of supply and demand, the relationship of resources to the requiremnts of current reactor types, and the likely future implications of the Fast Breeder Reactor (FBR). Because of its importance for the future, the problems, status, and likely time scale of the FBR are discussed in some detail. It is concluded that the most important areas for nearterm attention in Australia are the criteria and conditions that would apply to nuclear installations, and the possible development of uranium fuel cycle industries. The pattern of development of reactor and fuel cycle strategies overseas is important for uranium industry planning, and in the long term plutonium availability may be a key factor in power and energy planning. Finally, acceptance of nuclear power includes acceptance that its radioactive wastes will have to be stored on earth, and recent developments to demonstrate that this can be done safely and economically are very important in terms of longterm public attitudes. (author)

  4. 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.)

  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. Public attitudes toward nuclear generating facilities: positive

    International Nuclear Information System (INIS)

    Krannich, R.S.

    1977-01-01

    Public opposition and intervention in the siting and development of nuclear power plants has become more of a limiting factor than technological issues. Attitude surveys indicate that, while the majority of Americans support nuclear power, the utilities would do well to respond to the concerns and opinions of local residents when projects are in the planning stages. Recent polls are analyzed to identify the demographic and perceptive factors of opposition. Demographic studies indicate that the greatest opposition comes from women, young people, urban residents, farmers, low-income groups, and the unemployed. Perceptual opposition is associated with anticipated negative impacts in the form of hazards and social disruption. Since there appears to be a correlation between access to pertinent information and level of support, utility planners could develop educational programs to provide this information on the advantages of nuclear power. 10 references

  7. Human factor problem in nuclear power generation

    International Nuclear Information System (INIS)

    Yoshino, Kenji; Fujimoto, Junzo

    1999-01-01

    Since a nuclear power plant accident at Threemile Island in U.S.A. occurred in March, 1979, twenty years have passed. After the accident, the human factor problem became focussed in nuclear power, to succeed its research at present. For direct reason of human error, most of factors at individual level or work operation level are often listed at their center. Then, it is natural that studies on design of a machine or apparatus suitable for various human functions and abilities and on improvement of relationship between 'human being and machine' and 'human being and working environment' are important in future. Here was, as first, described on outlines of the human factor problem in a nuclear power plant developed at a chance of past important accident, and then was described on educational training for its countermeasure. At last, some concrete researching results obtained by human factor research were introduced. (G.K.)

  8. Economic analysis of nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-01

    The major contents in this study are as follows : (1) Efforts are made to examine the role of nuclear energy considering environmental regulation. An econometric model for energy demand and supply including carbon tax imposition is established. (2) Analysis for the learning effect of nuclear power plant operation is performed. The study is focused to measure the effect of technology homogeneity on the operation performance. (3) A preliminary capital cost of the KALIMER is estimated by using cost computer program, which is developed in this study. (author). 36 refs.,46 tabs., 15 figs.

  9. Developing people for the new nuclear generation

    International Nuclear Information System (INIS)

    Gordon, C.; Fluke, R.; Moya, R.

    2005-01-01

    The importance of having high-calibre people and the urgency in ensuring adequate numbers of knowledgeable staff has been recognized in the nuclear industry world wide. This paper describes how Nuclear Safety Solutions Limited is addressing these challenges by adopting a pro-active approach to training and development. This paper describes the integrated processes and tools used to ensure: adequate numbers of appropriately qualified staff to meet current and projected business needs, suitably qualified staff are assigned to projects for clients, and individual staff development. NSS uses a Qualification and Experience (Q and E) Registry to ensure the proper functioning of these processes. (author)

  10. Bruce A restart (execution and lessons-learned)

    International Nuclear Information System (INIS)

    Soini, J.

    2011-01-01

    Lessons learned with the Bruce Units 3 and 4 restart have been incorporated into the current refurbishment of Units 1 and 2. In addition, lessons learned on the lead unit (U2) are aggressively applied on the lagging unit (U1) to maximize efficiency and productivity. There will be a discussion on how this internal OPEX, along with external lessons learned, are used to continuously improve all aspects of the Bruce A Restart project management cycle, from scope selection, through planning and scheduling, to execution.

  11. Bruce NGS A Unit 4 preheater divider plate failure

    International Nuclear Information System (INIS)

    Landridge, M.; McInnes, D.

    1995-01-01

    On May 19, 1995, without any prior operational indications, Bruce A discovered preheater divider plate damage in Unit 4 that had the potential to have a major impact on the continued safe operation of the station. Further investigations indicated that Unit 4 may have been operating with this damage for as long as ten years. In the two months following the discovery, Bruce A has procured and replaced the 4 divider plates, located most of the missing pieces, retrieved pieces from the PHT system, investigated historical operational information, performed detailed analytical investigations, investigated root cause, performed in-situ and mock-up testing, updated operational procedures and installed DP monitoring equipment

  12. 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

  13. 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)

  14. 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

  15. 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

  16. 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)

  17. 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.)

  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. Promoting nuclear energy: meeting with new generations

    International Nuclear Information System (INIS)

    Uemura, George; Neves, Maria A.; Pedron, Marilene Quinaud; Guimaraes, Regia R. Ramirez; Filgueiras, Sergio A. Cunha

    2000-01-01

    The VII General Congress on Nuclear Energy (VII CGEN) decided on another approach, in order to promote nuclear energy (NE) for the average public. Instead of promoting an event for the nuclear area, the VII CGEN was open to the general public, aiming at high schools of the city of Belo Horizonte, where the meeting was held. The papers submitted were classified to two poster sessions, one called journalistic, open to the public, and technical, for the congressmen. The authors of the former session were asked to make their posters understandable for an average person. The present article shows the strategies used in dealing with local high schools, which includes the preparation of two series of posters, one dealing with the history of NE until 1945, and the other with applications of NE, due to the lack of this kind of material in Portuguese. The results of these efforts are shown and discussed, in terms of a better public image for NE and her community in Brazil. The public response showed that there is more than enough public for this kind of event, but not events enough. (author)

  20. Chemical cleaning of nuclear (PWR) steam generators

    International Nuclear Information System (INIS)

    Welty, C.S. Jr.; Mundis, J.A.

    1982-01-01

    This paper reports on a significant research program sponsored by a group of utilities (the Steam Generator Owners Group), which was undertaken to develop a process to chemically remove corrosion product deposits from the secondary side of pressurized water reactor (PWR) power plant steam generators. Results of this work have defined a process (solvent system and application methods) that is capable of removing sludge and tube-to-tube support plate crevice corrosion products generated during operation with all-volatile treatment (AVT) water chemistry. Considers a plant-specific test program that includes all materials in the steam generator to be cleaned and accounts for the physical locations (proximity and contact) of those materials. Points out that prior to applying the process in an operational unit, the utility, with the participation of the NSSR vendor, must define allowable total corrosion to the materials of construction of the unit

  1. 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

  2. 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.)

  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. 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

  5. Developing people for the new nuclear generation

    International Nuclear Information System (INIS)

    Gordon, C.; Fluke, R.; Moya, R.

    2005-01-01

    The importance of having high-calibre people and the urgency in ensuring adequate numbers of knowledgeable staff has been recognised in the nuclear industry world wide. This paper describes how NSS is addressing these challenges by adopting a pro-active approach to training and development. This paper describes the integrated processes and tools used to ensure: adequate numbers of appropriately qualified staff to meet current and projected business needs; suitably qualified staff are assigned to projects for clients, and individual staff development. NSS uses a Qualification and Experience (Q and E) Registry to ensure the proper functioning of these processes. (author)

  6. 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

  7. 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.

  8. Reaching the next generation of nuclear engineers

    International Nuclear Information System (INIS)

    Djokic, Denia; Fratoni, Massimiliano

    2008-01-01

    The University of California, Berkeley (UCB) American Nuclear Society (ANS) Student Section hosted two outreach events for young students between the ages of seven and twelve. The students were part of a private after-school club called Adventures Through Open Minds Science TM club for kids (A.T.O.M.S. club for kids) heated by Leslie Buchalter. Buchalter is an expert in early education and teaches children fundamental scientific concepts by using 'kid language' and associating usually difficult ideas with something even the very young children can understand. The greatest challenge for us UCB student organizers was to follow this manner of teaching and to construct activities that would always keep the attention of the children. We put together an array of fundamental concept demonstrations based on this philosophy. For example, the concept of half-life was taught by repeatedly tossing M and M's onto a surface and removing the upside down M and M's, and the concept of a nuclear chain reaction was introduced using a mousetrap-and-ping-pong-ball contraption. The main lessons learned were that the children most successfully absorbed ideas by engaging the students activity in the concept demonstrations, by using concepts and vocabulary already familiar to them which encouraged them to answer questions about familiar topics, and by creating a playful game out of every learning opportunity. (author)

  9. Solid waste generation in reprocessing nuclear fuel

    International Nuclear Information System (INIS)

    North, E.D.

    1975-01-01

    Estimates are made of the solid wastes generated annually from a 750-ton/year plant (such as the NFS West Valley plant): high-level waste, hulls, intermediate level waste, failed equipment, HEPA filters, spent solvent, alpha contaminated combustible waste, and low specific activity waste. The annual volume of each category is plotted versus the activity level

  10. 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)

  11. 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)

  12. 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).

  13. Responses of platinum, vanadium and cobalt self-powered flux detectors near simulated booster rods in a ZED-2 mockup of a Bruce reactor core

    International Nuclear Information System (INIS)

    French, P.M.; Shields, R.B.; Kroon, J.C.

    1978-02-01

    The static responses of Pt, V and Co self-powered detectors have been compared with copper-foil neutron activation profiles in reference and perturbed Bruce reactor core mockups assembled in the ZED-2 test reactor at Chalk River Nuclear Laboratories. The results indicate that the normalized response of each self-powered detector is an accurate measure of the thermal-neutron flux at locations greater than one lattice pitch from either a booster rod or the core boundary. They indicate that, in the Bruce booster/detector configuration, the normalized static Pt response overestimates the neutron flux by less than 3.5% upon full booster-rod insertion. (author)

  14. 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.

  15. Flux distribution measurements in the Bruce B Unit 6 reactor using a transportable traveling flux detector system

    International Nuclear Information System (INIS)

    Leung, T.C.; Drewell, N.H.; Hall, D.S.; Lopez, A.M.

    1987-01-01

    A transportable traveling flux detector (TFD) system for use in power reactors has been developed and tested at Chalk River Nuclear Labs. in Canada. It consists of a miniature fission chamber, a motor drive mechanism, a computerized control unit, and a data acquisition subsystem. The TFD system was initially designed for the in situ calibration of fixed self-powered detectors in operating power reactors and for flux measurements to verify reactor physics calculations. However, this system can also be used as a general diagnostic tool for the investigation of apparent detector failures and flux anomalies and to determine the movement of reactor internal components. This paper describes the first successful use of the computerized TFD system in an operating Canada deuterium uranium (CANDU) power reactor and the results obtained from the flux distribution measurements. An attempt is made to correlate minima in the flux profile with the locations of fuel channels so that future measurements can be used to determine the sag of the channels. Twenty-seven in-core flux detector assemblies in the 855-MW (electric) Unit 6 reactor of the Ontario Hydro Bruce B Generating Station were scanned

  16. 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.)

  17. 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.)

  18. David Bruce Payton : väikeriigid mõistavad üksteist / David Bruce Payton ; interv. Marianne Mikko

    Index Scriptorium Estoniae

    Payton, David Bruce

    2003-01-01

    Uus-Meremaa suursaadik Eestis David Bruce Payton talupidaja toetamise loobumisest Uus-Meremaal, Uus-Meremaa põllumajandussektorist, veinidest, ekspordist, Eesti saamisest EL-i ja NATO liikmeks, Uus-Meremaa rahvastikust, elatustasemest, Iraagi võimalikust ründamisest, Põhja-Koreast

  19. 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)

  20. Nuclear material accounting: The next generation

    International Nuclear Information System (INIS)

    Kern, E.A.; McRae, L.P.; O'Callaghan, P.B.; Yearsley, D.

    1992-07-01

    The Westinghouse Hanford company (Westinghouse Hanford) and the Los Alamos National Laboratory (LANL) have undertaken a joint effort to develop a new generation material accounting system. The system will incorporate the latest advances in microcomputer hardware, software, and network technology. This system, the Local Area Network Material Accounting System (LANMAS), offers greater performance and functionality at a reduced overall cost. It also offers the possibility of establishing a standard among DOE and NRC facilities for material accounting. This report provides a discussion of this system

  1. Economic analysis of nuclear power generation

    International Nuclear Information System (INIS)

    Song, Ki Dong; Lee, Han Myeong; Lee, Man Kee; Moon, Ki Hwan; Kim, Seung Soo; Kim, Seong Ki; Lee, Yeong Ki

    1993-12-01

    As CO 2 emission is recognized as the one of the major causes of the global worming, international CO 2 emission regulation has been of great concern and has been discussed actively on the global level. Several means of CO 2 emission regulation have been raised and have received much attention recently. CO 2 emission regulation is expected to affect the national economy as well as the national energy policy. Since the electricity sector closely interacts with CO 2 emission, environmental regulation has the possibility of implementation in this sector. Considering the enormous role played by electricity in the national economy, it is very important to study the effect of environmental regulation on the electricity sector. The main purpose of this study is to estimate the marginal cost of CO 2 emission by analyzing the effect of CO 2 emission regulation on the electricity sector in terms of capacity and generation mix. This information can be used effectively in energy policy establishment. In addition, the effect of CO 2 emission regulation on economic viability of electricity generating type is also being studied in order to contribute to the establishment of Electric System Expansion Planning in Korea

  2. 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

  3. 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

  4. Compressed beam directed particle nuclear energy generator

    International Nuclear Information System (INIS)

    Salisbury, W.W.

    1985-01-01

    This invention relates to the generation of energy from the fusion of atomic nuclei which are caused to travel towards each other along collision courses, orbiting in common paths having common axes and equal radii. High velocity fusible ion beams are directed along head-on circumferential collision paths in an annular zone wherein beam compression by electrostatic focusing greatly enhances head-on fusion-producing collisions. In one embodiment, a steady radial electric field is imposed on the beams to compress the beams and reduce the radius of the spiral paths for enhancing the particle density. Beam compression is achieved through electrostatic focusing to establish and maintain two opposing beams in a reaction zone

  5. 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.)

  6. 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.

  7. 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.

  8. 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

  9. 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.)

  10. 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

  11. 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.)

  12. 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

  13. 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)

  14. 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

  15. 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.)

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. Non intrusive check valve diagnostics at Bruce A

    International Nuclear Information System (INIS)

    Marsch, S.P.

    1997-01-01

    Bruce A purchased non intrusive check valve diagnostic equipment in 1995 to ensure operability and availability of critical check valves in the Station. Diagnostics can be used to locate and monitor check valve degradation modes. Bruce A initiated a pilot program targeting check valves with flow through them and ones that completed open or close cycles. Approaches to determine how to confirm operability of passive check valves using non intrusive techniques were explored. A sample population of seventy-three check valves was selected to run the pilot program on prior to complete implementation. The pilot program produced some significant results and some inconclusive results. The program revealed a major finding that check valve performance modeling is required to ensure continuous operability of check valves. (author)

  5. Non intrusive check valve diagnostics at Bruce A

    Energy Technology Data Exchange (ETDEWEB)

    Marsch, S.P. [Ontario Hydro, Bruce Nuclear Generating Station A, Tiverton, ON (Canada)

    1997-07-01

    Bruce A purchased non intrusive check valve diagnostic equipment in 1995 to ensure operability and availability of critical check valves in the Station. Diagnostics can be used to locate and monitor check valve degradation modes. Bruce A initiated a pilot program targeting check valves with flow through them and ones that completed open or close cycles. Approaches to determine how to confirm operability of passive check valves using non intrusive techniques were explored. A sample population of seventy-three check valves was selected to run the pilot program on prior to complete implementation. The pilot program produced some significant results and some inconclusive results. The program revealed a major finding that check valve performance modeling is required to ensure continuous operability of check valves. (author)

  6. 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

  7. 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

  8. Integrated inspection programs at Bruce Heavy Water Plant

    International Nuclear Information System (INIS)

    Brown, K.C.

    1992-01-01

    Quality pressure boundary maintenance and an excellent loss prevention record at Bruce Heavy Water Plant are the results of the Material and Inspection Unit's five inspection programs. Experienced inspectors are responsible for the integrity of the pressure boundary in their own operating area. Inspectors are part of the Technical Section, and along with unit engineering staff, they provide technical input before, during, and after the job. How these programs are completed, and the results achieved, are discussed. 5 figs., 1 appendix

  9. Integrated inspection programs at Bruce Heavy Water Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, K C [Ontario Hydro, Tiverton, ON (Canada)

    1993-12-31

    Quality pressure boundary maintenance and an excellent loss prevention record at Bruce Heavy Water Plant are the results of the Material and Inspection Unit`s five inspection programs. Experienced inspectors are responsible for the integrity of the pressure boundary in their own operating area. Inspectors are part of the Technical Section, and along with unit engineering staff, they provide technical input before, during, and after the job. How these programs are completed, and the results achieved, are discussed. 5 figs., 1 appendix.

  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. 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)

  12. 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)

  13. Removal of bulk contaminants from radioactive waste water at Bruce A using a clay based flocculent system

    International Nuclear Information System (INIS)

    Davloor, R.; Harper, B.

    2011-01-01

    Bruce Power's Bruce Nuclear Generating Station 'A', located on Lake Huron, has a treatment system that processes all aqueous radioactive waste water originating from the station. This Active Liquid Waste Treatment System (ALWTS) consists of collection tanks for the collection of radioactive waste water, a Pre-Treatment System (PTS) for the removal of bulk contaminants and suspended solids, a Reverse Osmosis System (ROS) to remove dissolved solids, an Evaporation and Solidification System (ESS) to concentrate and immobilize solids contained in concentrated waste streams from the ROS, and discharge tanks for the dispersal of the treated water. The ALWTS has been in continuous service since 1999 and is used to treat approximately 100,000 litres of Active Liquid Waste (ALW) each day. With the exception of tritium, it discharges waste water containing near zero concentrations of radioactive and conventional contaminants to the lake. The original design of the Bruce A ALWTS used a Backwashable Filtration System (BFS) to provide solids free water to the ROS, as measured by the Silt Density Index (SDI). During commissioning, the BFS was not successful in backwashing the solids from the filter elements. For approximately one year, a temporary solution was implemented using a Disposable Filtration System (DFS). A cationic polymer was added upstream of the DFS to agglomerate the solids. The system proved to be highly unreliable. It was difficult to agglomerate solids in the waste stream containing high amounts of detergent. As a result, DFS consumption was high and very costly. The SDI specification for the RO membrane was not always met, resulting in a quick decline of performance of the first stage ROS membranes in the treatment process. In addition, the excess cationic polymer in the RO feed caused the membranes to become fouled. In-house station staff, together with personnel from Colloid Environmental Technologies (CETCO) Company, worked to develop and

  14. Removal of bulk contaminants from radioactive waste water at Bruce A using a clay based flocculent system

    Energy Technology Data Exchange (ETDEWEB)

    Davloor, R.; Harper, B. [Bruce Power, Tiverton, ON (Canada)

    2011-07-01

    Bruce Power's Bruce Nuclear Generating Station 'A', located on Lake Huron, has a treatment system that processes all aqueous radioactive waste water originating from the station. This Active Liquid Waste Treatment System (ALWTS) consists of collection tanks for the collection of radioactive waste water, a Pre-Treatment System (PTS) for the removal of bulk contaminants and suspended solids, a Reverse Osmosis System (ROS) to remove dissolved solids, an Evaporation and Solidification System (ESS) to concentrate and immobilize solids contained in concentrated waste streams from the ROS, and discharge tanks for the dispersal of the treated water. The ALWTS has been in continuous service since 1999 and is used to treat approximately 100,000 litres of Active Liquid Waste (ALW) each day. With the exception of tritium, it discharges waste water containing near zero concentrations of radioactive and conventional contaminants to the lake. The original design of the Bruce A ALWTS used a Backwashable Filtration System (BFS) to provide solids free water to the ROS, as measured by the Silt Density Index (SDI). During commissioning, the BFS was not successful in backwashing the solids from the filter elements. For approximately one year, a temporary solution was implemented using a Disposable Filtration System (DFS). A cationic polymer was added upstream of the DFS to agglomerate the solids. The system proved to be highly unreliable. It was difficult to agglomerate solids in the waste stream containing high amounts of detergent. As a result, DFS consumption was high and very costly. The SDI specification for the RO membrane was not always met, resulting in a quick decline of performance of the first stage ROS membranes in the treatment process. In addition, the excess cationic polymer in the RO feed caused the membranes to become fouled. In-house station staff, together with personnel from Colloid Environmental Technologies (CETCO) Company, worked to develop and

  15. 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)

  16. 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

  17. 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

  18. 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.)

  19. 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

  20. 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

  1. 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)

  2. 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)

  3. 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.)

  4. 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)

  5. 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)

  6. 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

  7. 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)

  8. 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

  9. 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)

  10. 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)

  11. 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

  12. 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.

  13. Fuel string supporting shield plug (f3sp) for Ontario Hydro - Bruce NGSA

    Energy Technology Data Exchange (ETDEWEB)

    Henry, P T [Canadian General Electric Co. Ltd., Peterborough, ON (Canada)

    1997-12-31

    A reactor `power pulse` problem was identified for the Ontario Hydro Bruce generating stations. On a postulated inlet header break, the fuel strings in a large number of channels could relocate toward the upstream end, resulting in a power pulse. The solution adopted for Bruce GSA is to change the direction of fuelling, from against the flow, to fuelling with the flow. In this revised fuelling scheme, given a postulated inlet header failure, the fuel bundle with the highest burnup would relocate into the reactor core and introduce a negative reactivity during the accident. However, this fuelling configuration results in a highly irradiated fuel bundle residing in the most downstream position against the latch. The latch supports only the outer ring of elements, not the end plate. A resulting high stress on the end plate coupled with high levels of hydrogen and deuterium may result in Zr hydride assisted cracking in the end plate during hot shutdown conditions. (In fuelling against flow, this is not a problem, since the latch supported bundle is not irradiated and has only low levels of hydrogen and deuterium.) A fuel string supporting shield plug (f3sp) which supports the bundle end plate has been developed as a solution to the fuel bundle end plate cracking problem. It would replace the existing outlet shield plug in all channels. This paper will describe the f3sp design, associated fuel handling, operation and qualification for reactor use. (author). 8 figs.

  14. Fuel string supporting shield plug (f3sp) for Ontario Hydro - Bruce NGSA

    International Nuclear Information System (INIS)

    Henry, P.T.

    1996-01-01

    A reactor 'power pulse' problem was identified for the Ontario Hydro Bruce generating stations. On a postulated inlet header break, the fuel strings in a large number of channels could relocate toward the upstream end, resulting in a power pulse. The solution adopted for Bruce GSA is to change the direction of fuelling, from against the flow, to fuelling with the flow. In this revised fuelling scheme, given a postulated inlet header failure, the fuel bundle with the highest burnup would relocate into the reactor core and introduce a negative reactivity during the accident. However, this fuelling configuration results in a highly irradiated fuel bundle residing in the most downstream position against the latch. The latch supports only the outer ring of elements, not the end plate. A resulting high stress on the end plate coupled with high levels of hydrogen and deuterium may result in Zr hydride assisted cracking in the end plate during hot shutdown conditions. (In fuelling against flow, this is not a problem, since the latch supported bundle is not irradiated and has only low levels of hydrogen and deuterium.) A fuel string supporting shield plug (f3sp) which supports the bundle end plate has been developed as a solution to the fuel bundle end plate cracking problem. It would replace the existing outlet shield plug in all channels. This paper will describe the f3sp design, associated fuel handling, operation and qualification for reactor use. (author). 8 figs

  15. 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

  16. 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)

  17. 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).

  18. 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.)

  19. 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.

  20. 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.

  1. 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)

  2. 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.

  3. Leadership Actions to Improve Nuclear Safety Culture

    International Nuclear Information System (INIS)

    Clewett, L.K.

    2016-01-01

    The challenge many leaders face is how to effectively implement and then utilise the results of Safety Culture surveys. Bruce Power has recently successfully implemented changes to the Safety Culture survey process including how corrective actions were identified and implemented. The actions taken in response to the latest survey have proven effective with step change performance noted. Nuclear Safety is a core value for Bruce Power. Nuclear Safety at Bruce Power is based on the following four pillars: reactor safety, industrial safety, radiological safety and environmental safety. Processes and practices are in place to achieve a healthy Nuclear Safety Culture within Bruce Power such that nuclear safety is the overriding priority. This governance is based on industry leading practices which monitor, asses and take action to drive continual improvements in the Nuclear Safety Culture within Bruce Power.

  4. 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.

  5. 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.)

  6. 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)

  7. 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)

  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. 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

  10. AECB assessment of Bruce A comments on the proposed STPA tritium releases

    International Nuclear Information System (INIS)

    Gerdingh, R.F.

    1995-04-01

    In 1993, Ontario Hydro submitted a proposal to the AECB to discharge slightly tritiated water, arising from the steam supplied by Bruce A, through the Steam Transformer Plant A (STPA) discharge lines. The purpose of the proposal is to eliminate the current practice of shipping this water back to Bruce A where it is discharged through the active liquid waste discharge line. One of the STPA lines discharges to the Bruce A intake channel. A small fraction of this water is processed and used as drinking water at Bruce A. At our request, Bruce A management informed Bruce A personnel of the proposal and gave them the opportunity to raise concerns. As part of our evaluation, we assessed those concerns and concluded that they were not an impediment to accept this proposal. This report documents our assessment of the concerns expressed. (author)

  11. AECB assessment of Bruce A comments on the proposed STPA tritium releases

    Energy Technology Data Exchange (ETDEWEB)

    Gerdingh, R F

    1995-04-01

    In 1993, Ontario Hydro submitted a proposal to the AECB to discharge slightly tritiated water, arising from the steam supplied by Bruce A, through the Steam Transformer Plant A (STPA) discharge lines. The purpose of the proposal is to eliminate the current practice of shipping this water back to Bruce A where it is discharged through the active liquid waste discharge line. One of the STPA lines discharges to the Bruce A intake channel. A small fraction of this water is processed and used as drinking water at Bruce A. At our request, Bruce A management informed Bruce A personnel of the proposal and gave them the opportunity to raise concerns. As part of our evaluation, we assessed those concerns and concluded that they were not an impediment to accept this proposal. This report documents our assessment of the concerns expressed. (author).

  12. Childhood leukemia around nuclear facilities

    International Nuclear Information System (INIS)

    1991-01-01

    This Information Bulletin highlights the conclusion made from an Atomic Energy Control Board of Canada (AECB) study on the incidence of childhood leukemia near nuclear facilities. All of the locations with the nuclear facilities are located in Ontario, the nuclear generating stations at Pickering and Bruce; the uranium mines and mills in Elliot Lake; the uranium refining facility in Port Hope; and nuclear research facilities located at Chalk River plus the small nuclear power plant in Rolphton. Two conclusions are drawn from the study: 1) while the rate of childhood leukemias made be higher or lower than the provincial average, there is no statistical evidence that the difference is due to anything but the natural variation in the occurrence of the disease; and 2) the rate of occurrence of childhood leukemia around the Pickering nuclear power station was slightly greater than the Ontario average both before and after the plant opened, but this, too , could be due to the natural variation

  13. 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)

  14. 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)

  15. 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.

  16. 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

  17. 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.

  18. 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)

  19. 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

  20. 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

  1. 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)

  2. 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

  3. 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)

  4. 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

  5. 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)

  6. The Use of Nuclear Generation to Provide Power System Stability

    OpenAIRE

    Heather Wyman-Pain; Yuankai Bian; Furong Li

    2016-01-01

    The decreasing use of fossil fuel power stations has a negative effect on the stability of the electricity systems in many countries. Nuclear power stations have traditionally provided minimal ancillary services to support the system but this must change in the future as they replace fossil fuel generators. This paper explains the development of the four most popular reactor types still in regular operation across the world which have formed the basis for most reactor dev...

  7. Technology standards for structure, etc. concerning nuclear power generating facilities

    International Nuclear Information System (INIS)

    1977-01-01

    Based on the Ordinance for the Technology Standards concerning Nuclear Power Generating Facilities, the technology standards are established for the vessels of class 1 to 4 (including reactor pressure vessels, reactor containment vessels, etc.), the pipes of class 1 to 3, safety valves, pressure test and monitoring test specimens. Those specified are materials, nondestructive tests, structures, shapes, shells, flanges, etc. for the vessels and the pipes, and so on. (Mori, K.)

  8. 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

  9. 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

  10. 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...

  11. 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

  12. Fire fighting capability assessment program Bruce B 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 Bruce B 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. Finally the execution of fire plans by Bruce B NGS, as demonstrated by their application of human and material resources during a simulated large fire, was observed. The fire fighting equipment and the personal protective clothing and associated equipment that was in use was all of good quality and in good condition. There had also been notable improvement in communications equipment. Similarly, the human resources that had been assigned to fire fighting and rescue crews and that were available were more than adequate. Use of a logical incident command system, and the adoption of proper policy and procedures for radio communications were equally significant improvements. Practice should correct the breakdowns that occurred in these areas during the exercise. As well, there remains a need for the development of policy on fire fighting and rescue operations with more depth and clarity. In summary, the key point to be recognized is the degree of improvement that has been realized since the previous evaluation in 1990. Clearly the Emergency Response Teams organization of Bruce B NGS is evolving into an effective fire fighting force. Providing that the deficiencies identified in this report are addressed satisfactorily, Fire Cross is confident that the organization will have the capability to provide rescue and fire fighting services that will satisfy the need. 2 figs

  13. Environmental health scoping study at Bruce Heavy Water Plant

    International Nuclear Information System (INIS)

    Prior, M.; Mostrom, M.; Coppock, R.; Florence, Z.

    1995-10-01

    There are concerns that hydrogen sulfide released from the Heavy Water Plant near Kincardine, Ontario may be the cause of the mortalities and morbidities observed in a nearby flock of sheep. The Philosopher's Wool sheep farm is about four kilometres south-southeast of the Bruce Heavy Water Plant. Ontario Hydro, the owner and operator of the Bruce Heavy Water Plant, claims that hydrogen sulphide emissions from the Bruce Heavy Water Plant are within regulatory limits and well below levels that cause harm. Accordingly, the Atomic Energy Control Board commissioned the Alberta Environmental Centre, Alberta Department of Environmental Protection, to develop a scoping study for this environmental health issue. The first objective was to describe a field investigation model to define clearly the environmental health and operation of the sheep farm. The second objective was to describe possible exposure patterns and develop a holistic environmental pathway model. If appropriate, the third study objective was to describe animal models of the actual situation to elucidate specific aspects of the environmental health concerns. It was not the objective of this report to provide a definitive answer to the present environmental health issue. Ontario Hydro provided data to the Alberta Environmental Centre, as di the sheep farmer, the attending veterinarian, the University of Guelph study team, and the Atomic Energy Control Board. A six-tiered strategy of sequential evaluations of the ovine health problem is based on the multiple-response paradigm. It assumes the observed ovine health results are the result of multiple effector events. Each tier constitutes a separate, but inter-related, study. Sequential evaluation and feedback of each tier allow sound scientific judgements and efficient use of resources. (author). 59 refs., 11 tabs., 22 figs

  14. 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.)

  15. 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

  16. 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

  17. 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)

  18. 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)

  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. 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

  1. 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)

  2. 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

  3. 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

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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)

  9. 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)

  10. 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)

  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. 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.

  13. 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)

  14. The human factors issue in the next generation nuclear plants

    International Nuclear Information System (INIS)

    Noviello, L.; Bolognini, G.; Nobile, M.

    1992-01-01

    The national Energy Plan approved by the Italian Government in 1988, soon after the public referendum on nuclear issues held in the wake of the Chernobyl accident, requested the start of a research program to study next generation nuclear plants. These new reactors should feature some important and innovative characteristics to have a chance to be considered for future constructions, should the politicians decide the conditions for such a step are again re-established in Italy. The most important of these characteristics is certainly the fact that no evaluation nor land set a-side shall be required even in case of the most severe conceivable accident. This challenging objective should be reached through: a) the simplification of the nuclear plant as a whole b) the extensive use of passive components and/or inherent safety features in the design of the engineering safeguard systems c) a containment designed to cope with any conceivable accident sequence without releasing any major quantity of radioactive products into the environment. d) the upgrading of the man-machine interface and the introduction of computerized aids both for operational and maintenance activities. This paper deals in particular with the improvements, described in point d), that aim at greatly reducing the probability of human errors, widely recognized as one of the most important aspects to be pursued to increase nuclear plant safety. (author)

  15. 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

  16. Steam generator replacement at the Obrigheim nuclear power station

    International Nuclear Information System (INIS)

    Pickel, E.; Schenk, H.; Huemmler, A.

    1984-01-01

    The Obrigheim Nuclear Power Station (KWO) is equipped with a dual-loop pressurized water reactor of 345 MW electric power; it was built by Siemens in the period 1965 to 1968. By the end of 1983, KWO had produced some 35 billion kWh in 109,000 hours of operation. Repeated leaks in the heater tubes of the two steam generators had occurred since 1971. Both steam generators were replaced in the course of the 1983 annual revision. Kraftwerk Union AG (KWU) was commissioned to plant and carry out the replacement work. Despite the leakages the steam generators had been run safely and reliably over a period of 14 years until their replacement. Replacing the steam generators was completed within twelve weeks. In addition to the KWO staff and the supervising crew of KWU, some 400 external fitters were employed on the job at peak work-load periods. For the revision of the whole plant, work on the emergency systems and replacement of the steam generators a maximum number of approx. 900 external fitters were employed in the plant in addition to some 250 members of the plant crew. The exposure dose of the personnel sustained in the course of the steam generator replacement was 690 man-rem, which was clearly below previous estimates. (orig.) [de

  17. 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

  18. 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

  19. History of the nuclear power generation technology in Japan

    International Nuclear Information System (INIS)

    2016-01-01

    First, the outline of the historical fact is described. Next, the research institution, the industrial world, and the government which were the bearers of technical development are described and look back upon the history of development from each position. The focus is a viewpoint based on refection of a Fukushima disaster. 'Teachings from history' seen from each actor was described being based on the objective fact. Moreover, it focuses also on the society, the politics, and the economic factor which affected development of nuclear development. The following three were treated as themes. 1. Relation with the atomic power and the nonproliferation policy of the U.S. government. 2. Relation with public opinion or media. 3. Social responsibility of a society, or a scientist and an engineering person. Finally, based on these teachings, the viewpoint considered to be important for future nuclear power generation and technical development was summarized as a proposal. (author)

  20. Nuclear data generation for cryogenic moderators and high temperature moderators

    International Nuclear Information System (INIS)

    Petriw, Sergio

    2007-01-01

    The commonly used processing codes for nuclear data only allow the generation of cross section data for a limited number of materials and physical conditions.At present, one of the most used computer codes for the generation of neutron cross sections is N J O Y, which is based on a phonon expansion of the scattering function starting from the frequency spectrum.Therefore, the information related to the system's density of states is crucial to produce the required data of interest. In this work the formalism of the Synthetic Model for Molecular Solids (S M M S) was implemented, which is in turn based on the Synthetic Frequency Spectrum (S F S) concept.The synthetic spectrum is central in the present work, and it is built from simple, relevant parameters of the moderator, thus conforming an alternative tool when no information on the actual frequency spectrum of the moderator material is available.S F S 's for several material of interest where produced in this work, for both cryogenic and high temperature moderators.We studied some materials of special interest, like solid methane, ice, methyl clathrate and two which are of special interest in the nuclear industry: graphite and beryllium.The libraries generated in the present work for the materials considered, in spite of their synthetic origin, are able to produce results that are even in better agreement with available information [es

  1. 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

  2. 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

  3. 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.

  4. 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

  5. Soviet steam generator technology: fossil fuel and nuclear power plants

    International Nuclear Information System (INIS)

    Rosengaus, J.

    1987-01-01

    In the Soviet Union, particular operational requirements, coupled with a centralized planning system adopted in the 1920s, have led to a current technology which differs in significant ways from its counterparts elsewhere in the would and particularly in the United States. However, the monograph has a broader value in that it traces the development of steam generators in response to the industrial requirements of a major nation dealing with the global energy situation. Specifically, it shows how Soviet steam generator technology evolved as a result of changing industrial requirements, fuel availability, and national fuel utilization policy. The monograph begins with a brief technical introduction focusing on steam-turbine power plants, and includes a discussion of the Soviet Union's regional power supply (GRES) networks and heat and power plant (TETs) systems. TETs may be described as large central co-generating stations which, in addition to electricity, provide heat in the form of steam and hot water. Plants of this type are a common feature of the USSR today. The adoption of these cogeneration units as a matter of national policy has had a central influence on Soviet steam generator technology which can be traced throughout the monograph. The six chapters contain: a short history of steam generators in the USSR; steam generator design and manufacture in the USSR; boiler and furnace assemblies for fossil fuel-fired power stations; auxiliary components; steam generators in nuclear power plants; and the current status of the Soviet steam generator industry. Chapters have been abstracted separately. A glossary is included containing abbreviations and acronyms of USSR organizations. 26 references

  6. Exercise testing of pre-school children using the Bruce treadmill protocol: new reference values

    NARCIS (Netherlands)

    M.H.M. van der Cammen-van Zijp (Monique); H. IJsselstijn (Hanneke); T. Takken (Tim); S.P. Willemsen (Sten); D. Tibboel (Dick); H.J. Stam (Henk); H.J.G. van den Berg-Emons (Rita)

    2010-01-01

    textabstractThe Bruce treadmill protocol is an often-used exercise test for children and adults. Few and mainly old normative data are available for young children. In this cross-sectional observational study we determined new reference values for the original Bruce protocol in children aged 4 and 5

  7. Modular steam generator for use in nuclear power plants

    International Nuclear Information System (INIS)

    Cella, A.

    1979-01-01

    An improved steam generator for a PWR is described. A turbine generator is driven by the steam output of the steam generator to provide electrical power. The improvement provides vertically assemblable modules which are removably mounted together in sealing relationship. The modules comprising a base module, a tube bundle module removably mountable on the base module in sealing relationship, and an uppermost dryer module removably mountable on the tube bundle module in sealing relationship. Ready access to and removal of the tube bundle module in situ from the nuclear power plant steam generator is facilitated. The dryer module contains moisture separator for drying the generated steam. The base module, upon which the associated weight of the vertically assembled dryer module and tube bundle module are supported, contains the inlet and outlet for the heat exchange fluid. The tube bundle module contains the tube bundle through which the heat exchange fluid flows as well as an inlet for feedwater. The tube sheet serves as a closure flange for the tube bundle module, with the associated weight of the vertically assembled dryer module and tube bundle module on the tube sheet closure flange effectuating the sealing relationship between the base module and the tube bundle module for facilitating closure

  8. Risks of turbine generators at WWER-440 nuclear power plants

    International Nuclear Information System (INIS)

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

    1998-01-01

    Many serious fires and incidents have occurred in the turbine halls of nuclear power plants, resulting in serious damage and long shutdown outages. Some of these incidents have endangered the safe shutdown of the plants because of the location of lack of vital fire protection safety systems. A detailed analysis is necessary for all those plants that have equipment important for safe shutdown located in the turbine hall or its vicinity without strict fire separation by fire rated barriers. A reduction in the fire frequencies of the turbine hall is an additional way of improving safety. This is possible by improving all aspects of turbine generator operation. (author)

  9. The random signal generator of imitated nuclear radiation pulse

    International Nuclear Information System (INIS)

    Li Dongcang; Yang Lei; Yuan Shulin; Yang Yinghui; Zang Fujia

    2007-01-01

    Based in pseudo-random uniformity number, it produces random numbers of Gaussian distribution and exponential distribution by arithmetic. The hardware is the single-chip microcomputer of 89C51. Program language makes use of Keil C. The output pulse amplitude is Gaussian distribution, exponential distribution or uniformity distribution. Likewise, it has two mode or upwards two. The time alternation of output pulse is both periodic and exponential distribution. The generator has achieved output control of multi-mode distribution, imitated random characteristic of nuclear pulse in amplitude and in time. (authors)

  10. Operating experience with diesel generators in Belgian nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Merny, R. [Association Vincotte, Avenue du Roi 157, B-1060 Bruxelles/Brussels (Belgium)

    1986-02-15

    Various problems have occurred on the diesel generators in the Belgian nuclear power plants, independently of the D.G. manufacturer or from the operating crew. Furthermore no individual part of the D.G. can be incriminated as being the main cause of the incidents. The incidents reported in this paper are chosen because of the importance for the safety or for the long repair period. The unavailability of a D.G. can only be detected by periodic tests and controls. Combined with a good preventive maintenance, the risks of incidents can be reduced. (author)

  11. Operating experience with diesel generators in Belgian nuclear power plants

    International Nuclear Information System (INIS)

    Merny, R.

    1986-01-01

    Various problems have occurred on the diesel generators in the Belgian nuclear power plants, independently of the D.G. manufacturer or from the operating crew. Furthermore no individual part of the D.G. can be incriminated as being the main cause of the incidents. The incidents reported in this paper are chosen because of the importance for the safety or for the long repair period. The unavailability of a D.G. can only be detected by periodic tests and controls. Combined with a good preventive maintenance, the risks of incidents can be reduced. (author)

  12. Major plant retrofits at Monticello nuclear generating plant

    International Nuclear Information System (INIS)

    Larsen, D.E.; Hogg, C.B.

    1986-01-01

    For the past several years, Northern States Power (NSP) has been making major plant retrofits to Monticello Nuclear generating Station in order to improve plant availability and upgrade the plant components for the potential extension of the operating license (life extension). This paper discusses in detail three major retrofits that have been completed or in the process of completion; recirculation loop piping replacement, reactor pressure vessel (RPV) water level-instrumentation modification, core spray piping replacement, the authors will address the scope of work, design and installation concerns, and life extension considerations during the design and procurement process for these three projects

  13. Static and dynamic high power, space nuclear electric generating systems

    International Nuclear Information System (INIS)

    Wetch, J.R.; Begg, L.L.; Koester, J.K.

    1985-01-01

    Space nuclear electric generating systems concepts have been assessed for their potential in satisfying future spacecraft high power (several megawatt) requirements. Conceptual designs have been prepared for reactor power systems using the most promising static (thermionic) and the most promising dynamic conversion processes. Component and system layouts, along with system mass and envelope requirements have been made. Key development problems have been identified and the impact of the conversion process selection upon thermal management and upon system and vehicle configuration is addressed. 10 references

  14. Steam generator for a pressurized-water coolant nuclear reactor

    International Nuclear Information System (INIS)

    Schroeder, H.J.; Berger, W.

    1975-01-01

    A description is given of a steam generator which has a vertical cylindrical housing having a steam output outlet, a horizontal tube sheet closing the lower end of this housing, and an inverted U-shaped tube bundle inside of the housing and having vertical inlet and outlet legs with their ends mounted in the tube sheet. Beneath the tube sheet there are inlet and outlet manifolds for the respective ends of the tube bundle so that pressurized-water coolant from a pressurized-water coolant nuclear reactor can be circulated through the tube bundle

  15. Review of first line supervisory positions in nuclear power plants - Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Mackenzie, C W; Huntley, M [Hickling Corp., Ottawa, ON (Canada)

    1995-10-01

    This report provides an overview of first line supervisory activities at Ontario Hydro nuclear generating stations (Pickering `A` and Bruce `B`) and the Point Lepreau nuclear generating station in New Brunswick. Activity profiles describing the range of first line supervisory roles and responsibilities for nuclear operators have been developed from survey data and flowcharting methods. These activity profiles have then been compared with formal job responsibilities as identified in job descriptions, supervisory training provided and assessment criteria used to evaluate supervisors. Finally, this report relates the findings of supervisory practices in the group under study with the findings in the current literature relating to supervisory functioning. (author). 32 tabs., 2 figs.

  16. Review of first line supervisory positions in nuclear power plants - Phase II

    International Nuclear Information System (INIS)

    Mackenzie, C.W.; Huntley, M.

    1995-10-01

    This report provides an overview of first line supervisory activities at Ontario Hydro nuclear generating stations (Pickering 'A' and Bruce 'B') and the Point Lepreau nuclear generating station in New Brunswick. Activity profiles describing the range of first line supervisory roles and responsibilities for nuclear operators have been developed from survey data and flowcharting methods. These activity profiles have then been compared with formal job responsibilities as identified in job descriptions, supervisory training provided and assessment criteria used to evaluate supervisors. Finally, this report relates the findings of supervisory practices in the group under study with the findings in the current literature relating to supervisory functioning. (author). 32 tabs., 2 figs

  17. 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

  18. Hydrogen Generation, Combustibility and Mitigation in Nuclear Power Plant Systems

    International Nuclear Information System (INIS)

    Talha, K.A.; El-Sheikh, B.M.; Gad El-Mawla, A.S.

    2003-01-01

    The nuclear power plant is provided with features to insure safety. The engineered safety features (ESFs) are devoted to set operating conditions under accident conditions. If ESFs fail to apply in some accidents, this would lead to what called severe accidents, and core damage. In this case hydrogen will be generated from different sources particularly from metal-water reactions. Since the containment is the final barrier to protect the environment from the release of radioactive materials; its integrity should not be threatened. In recent years, hydrogen concentration represents a real problem if it exceeds the combustibility limits. This work is devoted to calculate the amount of hydrogen to be generated, indelicate its combustibility and how to inertize the containment using different gases to maintain its integrity and protect the environment from the release of radioactive materials

  19. 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

  20. 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)

  1. 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

  2. Quality control of stainless steel pipings for nuclear power generation

    International Nuclear Information System (INIS)

    Miki, Minoru; Kitamura, Ichiro; Ito, Hisao; Sasaki, Ryoichi

    1979-01-01

    The proportion of nuclear power in total power generation is increasing recently in order to avoid the concentrated dependence on petroleum resources, consequently the reliability of operation of nuclear power plants has become important. In order to improve the reliability of plants, the reliability of each machine or equipment must be improved, and for the purpose, the quality control at the time of manufacture is the important factor. The piping systems for BWRs are mostly made of carbon steel, and stainless steel pipings are used for the recirculation system cooling reactors and instrumentation system. Recently, grain boundary type stress corrosion cracking has occurred in the heat-affected zones of welded stainless steel pipings in some BWR plants. In this paper, the quality control of stainless steel pipings is described from the standpoint of preventing stress corrosion cracking in BWR plants. The pipings for nuclear power plants must have sufficient toughness so that the sudden rupture never occurs, and also sufficient corrosion resistance so that corrosion products do not raise the radioactivity level in reactors. The stress corrosion cracking occurred in SUS 304 pipings, the factors affecting the quality of stainless steel pipings, the working method which improves the corrosion resistance and welding control are explained. (Kako, I.)

  3. 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.)

  4. Design of nuclear power generation plants adopting model engineering method

    International Nuclear Information System (INIS)

    Waki, Masato

    1983-01-01

    The utilization of model engineering as the method of design has begun about ten years ago in nuclear power generation plants. By this method, the result of design can be confirmed three-dimensionally before actual production, and it is the quick and sure method to meet the various needs in design promptly. The adoption of models aims mainly at the improvement of the quality of design since the high safety is required for nuclear power plants in spite of the complex structure. The layout of nuclear power plants and piping design require the model engineering to arrange rationally enormous quantity of things in a limited period. As the method of model engineering, there are the use of check models and of design models, and recently, the latter method has been mainly taken. The procedure of manufacturing models and engineering is explained. After model engineering has been completed, the model information must be expressed in drawings, and the automation of this process has been attempted by various methods. The computer processing of design is in progress, and its role is explained (CAD system). (Kako, I.)

  5. 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

  6. AECB staff annual report of Bruce B NGS for the year 1991

    International Nuclear Information System (INIS)

    1992-11-01

    In this account of Bruce NGS B station operation during the year 1991 AECB staff have pointed out non-compliances with the operating licence, which have been few in number and minor in degree of seriousness. There were no exposures of workers to radiation in excess of regulatory limits, but there were contraventions of the ALARA principle. Releases of radioactive material to the environment have been well below the target levels. The performance of the four special safety systems has been good, except for the containment system. A review of the significant event reports and the causes of the events has revealed a lack of a system by which operations and maintenance work could be verified to have been carried out as intended. In operations and maintenance the backlog of work to be done to regularize temporary changes to equipment (removal of jumpers), to carry out preventive maintenance (call-ups), and to make repairs (deficiency reports) has increased from that of the previous year. On the other hand, the station has reduced the number of temporary operating instructions (operating memos) to half of what it was last year. The fretting of steam generator tubes reported last year has not become worse. Nevertheless, inspections continue and modifications to the tube supports are underway. Overall plant chemistry has been acceptable. An Ontario Hydro assessment of the station found the station management's expectations for maintaining the margin of safety in the plant had not been properly communicated to all levels of station staff. The station is now attempting to correct this. Infractions of work protection procedures, which were the subject of many significant events, have led to changes in the procedures and resulted in a major training effort. AECB staff believe that Ontario Hydro has continued to operate Bruce NGS B in a safe manner, but have pointed out areas where improvement is required. (Author)

  7. 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.

  8. 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)

  9. Disposal and handling of nuclear steam generator chemical cleaning wastes

    International Nuclear Information System (INIS)

    Larrick, A.P.; Schneidmiller, D.

    1978-01-01

    A large number of pressurized water nuclear reactor electrical generating plants have experienced a corrosion-related problem with their steam generators known as denting. Denting is a mechanical deformation of the steam generator tubes that occurs at the tube support plates. Corrosion of the tube support plates occurs within the annuli through which the tubes pass and the resulting corrosion oxides, which are larger in volume than the original metal, compress and deform the tubes. In some cases, the induced stresses have been severe enough to cause tube and/or support cracking. The problem was so severe at the Turkey Point and Surrey plants that the tubing is being replaced. For less severe cases, chemical cleaning of the oxides, and other materials which deposit in the annuli from the water, is being considered. A Department of Energy-sponsored program was conducted by Consolidated Edison Co. of New York which identified several suitable cleaning solvents and led to in-plant chemical cleaning pilot demonstrations in the Indian Point Unit 1 steam generators. Current programs to improve the technology are being conducted by the Electric Power Research Institute, and the three PWR NSSS vendors with the assistance of numerous consultants, vendors, and laboratories. These programs are expected to result in more effective, less corrosive solvents. However, after a chemical cleaning is conducted, a large problem still remains- that of disposing of the spent wastes. The paper summarizes some of the methods currently available for handling and disposal of the wastes

  10. Uncertainties in gas dispersion at the Bruce heavy water plant

    International Nuclear Information System (INIS)

    Alp, E.; Ciccone, A.

    1995-07-01

    There have been concerns regarding the uncertainties in atmospheric dispersion of gases released from the Bruce Heavy Water Plant (BHWP). The concern arises due to the toxic nature of H 2 S, and its combustion product SO 2 . In this study, factors that contribute to the uncertainties, such as the effect of the shoreline setting, the potentially heavy gas nature of H 2 S releases, and concentration fluctuations, have been investigated. The basic physics of each of these issues has been described along with fundamental modelling principles. Recommendations have been provided on available computer models that would be suitable for modelling gas dispersion in the vicinity of the BHWP. (author). 96 refs., 4 tabs., 25 figs

  11. Fuel handling solutions to power pulse at Bruce NGS A

    International Nuclear Information System (INIS)

    Day, R.C.

    1996-01-01

    In response to the discovery of the power pulse problem in March of 1993, Bruce A has installed flow straightening shield plugs in the inner zone channels of all units to partially reduce the gap and gain an increase in reactor power to 75%. After review and evaluation of solutions to manage the gap, including creep compensators and long fuel bundles, efforts have focused on a different solution involving reordering the fuel bundles to reverse the burnup profile. This configuration is maintained by fuelling with the flow and providing better support to the highly irradiated downstream fuel bundles by changing the design of the outlet shield plug. Engineering changes to the fuel handling control system and outlet shield plug are planned to be implemented starting in June 1996, thereby eliminating the power pulse problem and restrictions on reactor operating power. (author). 2 refs., 1 tab., 2 figs

  12. Fuel handling solutions to power pulse at Bruce NGS A

    Energy Technology Data Exchange (ETDEWEB)

    Day, R C [Ontario Hydro, Tiverton, ON (Canada). Bruce Nuclear Generating Station-A

    1997-12-31

    In response to the discovery of the power pulse problem in March of 1993, Bruce A has installed flow straightening shield plugs in the inner zone channels of all units to partially reduce the gap and gain an increase in reactor power to 75%. After review and evaluation of solutions to manage the gap, including creep compensators and long fuel bundles, efforts have focused on a different solution involving reordering the fuel bundles to reverse the burnup profile. This configuration is maintained by fuelling with the flow and providing better support to the highly irradiated downstream fuel bundles by changing the design of the outlet shield plug. Engineering changes to the fuel handling control system and outlet shield plug are planned to be implemented starting in June 1996, thereby eliminating the power pulse problem and restrictions on reactor operating power. (author). 2 refs., 1 tab., 2 figs.

  13. Uncertainties in gas dispersion at the Bruce heavy water plant

    Energy Technology Data Exchange (ETDEWEB)

    Alp, E; Ciccone, A [Concord Environmental Corp., Downsview, ON (Canada)

    1995-07-01

    There have been concerns regarding the uncertainties in atmospheric dispersion of gases released from the Bruce Heavy Water Plant (BHWP). The concern arises due to the toxic nature of H{sub 2}S, and its combustion product SO{sub 2}. In this study, factors that contribute to the uncertainties, such as the effect of the shoreline setting, the potentially heavy gas nature of H{sub 2}S releases, and concentration fluctuations, have been investigated. The basic physics of each of these issues has been described along with fundamental modelling principles. Recommendations have been provided on available computer models that would be suitable for modelling gas dispersion in the vicinity of the BHWP. (author). 96 refs., 4 tabs., 25 figs.

  14. Thorium and its future importance for nuclear energy generation

    International Nuclear Information System (INIS)

    Lainetti, Paulo E.O.

    2015-01-01

    Thorium was discovered in 1828 by the Swedish chemist Jons J. Berzelius. Despite some advantages over uranium for use in nuclear reactors, its main use, in the almost two centuries since its discovery, the use of thorium was restricted to use for gas mantles, especially in the early twentieth century. In the beginning of the Nuclear Era, many countries had interested on thorium, particularly during the 1950-1970 period. There are about 435 nuclear reactors in the world nowadays. They need more than 65.000 tons of uranium yearly. 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. 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, since it is possible to convert thorium waste into nonradioactive elements, thorium is an environment-friendly alternative energy source. Thorium fuel cycle is also inherently resistant to proliferation. 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. In this paper a brief history of thorium is presented, besides a review of the world thorium utilization and a discussion about advantages and restrictions of thorium use. (author)

  15. 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

  16. Generation IV nuclear reactors: Current status and future prospects

    International Nuclear Information System (INIS)

    Locatelli, Giorgio; Mancini, Mauro; Todeschini, Nicola

    2013-01-01

    Generation IV nuclear power plants (GEN IV NPPs) are supposed to become, in many countries, an important source of base load power in the middle–long term (2030–2050). Nowadays there are many designs of these NPPs but for political, strategic and economic reasons only few of them will be deployed. International literature proposes many papers and reports dealing with GEN IV NPPs, but there is an evident difference in the types and structures of the information and a general unbiased overview is missing. This paper fills the gap, presenting the state-of-the-art for GEN IV NPPs technologies (VHTR, SFR, SCWR, GFR, LFR and MSR) providing a comprehensive literature review of the different designs, discussing the major R and D challenges and comparing them with other advanced technologies available for the middle- and long-term energy market. The result of this research shows that the possible applications for GEN IV technologies are wider than current NPPs. The economics of some GEN IV NPPs is similar to actual NPPs but the “carbon cost” for fossil-fired power plants would increase the relative valuation. However, GEN IV NPPs still require substantial R and D effort, preventing short-term commercial adoption. - Highlights: • Generation IV reactors are the middle–long term technology for nuclear energy. • This paper provides an overview and a taxonomy for the designs under consideration. • R and D efforts are in the material, heat exchangers, power conversion unit and fuel. • The life cycle costs are competitive with other innovative technologies. • The hydrogen economy will foster the development of Generation IV reactors

  17. 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.

  18. 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

  19. Water releasing electric generating device for nuclear power plant

    International Nuclear Information System (INIS)

    Umehara, Toshihiro; Tomohara, Yasutaka; Usui, Yoshihiko.

    1994-01-01

    Warm sea water discharged after being used for cooling in an equipment of a coastal nuclear powder plant is discharged from a water discharge port to a water discharge pit, and a conduit vessel is disposed in front of the water discharge port for receiving overflown warm sea water. The warm sea water taken to the conduit vessel is converted to a fallen flow and charged to a turbine generator under water, and electric power is generated by the water head energy of the fallen flow before it is discharged to the water discharge pit. The conduit vessel incorporates a foam preventing unit having spiral flow channels therein, so that the warm sea water taken to the conduit vessel is flown into the water discharge pit after consuming the water head energy while partially branched and flown downwardly and gives lateral component to the downwarding flowing direction. Then, warm sea water is made calm when it is flown into the water discharge pit and, accordingly, generation of bubbles on the water surface of the water discharge pit is avoided. (N.H.)

  20. Steam Generator tube integrity -- US Nuclear Regulatory Commission perspective

    International Nuclear Information System (INIS)

    Murphy, E.L.; Sullivan, E.J.

    1997-01-01

    In the US, the current regulatory framework was developed in the 1970s when general wall thinning was the dominant degradation mechanism; and, as a result of changes in the forms of degradation being observed and improvements in inspection and tube repair technology, the regulatory framework needs to be updated. Operating experience indicates that the current U.S. requirements should be more stringent in some areas, while in other areas they are overly conservative. To date, this situation has been dealt with on a plant-specific basis in the US. However, the NRC staff is now developing a proposed steam generator rule as a generic framework for ensuring that the steam generator tubes are capable of performing their intended safety functions. This paper discusses the current U.S. regulatory framework for assuring steam generator (SG) tube integrity, the need to update this regulatory framework, the objectives of the new proposed rule, the US Nuclear Regulatory Commission (NRC) regulatory guide (RG) that will accompany the rule, how risk considerations affect the development of the new rule, and some outstanding issues relating to the rule that the NRC is still dealing with

  1. Decision process regarding nuclear generation: the Brazilian case

    International Nuclear Information System (INIS)

    Metri, Paulo

    2009-01-01

    Countries face a constant need to expand their electricity generation capacities. Electricity sources in a country and the respective generation technologies have different technical, economic, environmental, social and political characteristics. The evaluation criteria of the generating sources and their technologies must not be restricted to the supply of the increased demand at the lowest cost. Compliance with other public policies must be considered in the decision process of the expansion, for instance, maximize local acquisition and minimize foreign fuel purchase. Countries have different energy resources, as well as different levels of technology and development in their industrial parks. Brazil has many mineral reserves, besides the hydraulic potential, for supporting the expansion. The decision process in this sector, which includes nuclear energy as a sub-sector, requires analyzing and evaluating various information and data. In this stage, a quantitative model providing a first approach for the decision may be applied. The new institutional structure adopted in the sector during the 1990s and 2000s brought about new conditions into an already complex decision process. In such context of methodology complexity, political aspects gain relevance, becoming of increased importance. The political environment is described and the players are identified. One conclusion and a few recommendations are provided. (author)

  2. 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.

  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. 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...

  5. Chemistry technician performance evaluation program Palo Verde Nuclear Generating Station

    International Nuclear Information System (INIS)

    Shawver, J.M.

    1992-01-01

    The Arizona Nuclear Power Project (ANPP), a three-reactor site located 50 miles west of Phoenix, Arizona, has developed and implemented a program for evaluating individual chemistry technician analytical performance on a routine basis. About 45 chemistry technicians are employed at the site, 15 at each operating unit. The technicians routinely perform trace level analyses for impurities of concern to PWRs. Each month a set of blind samples is provided by an outside vendor. The blind samples contain 16 parameters which are matrixed to approximate the PWR's primary and secondary cycles. Nine technicians receive the samples, three from each operating unit, and perform the required analyses. Acceptance criteria for successful performance on the blind parameters is based on the values found in the Institute of Nuclear Power Operations (INPO) Document 83-016, Revision 2, August 1989, Chemistry Quality Control Program. The goal of the program is to have each technician demonstrate acceptable performance on each of 16 analytical parameters. On completion of each monthly set, a summary report of all of the analytical results for the sample set is prepared. From the summary report, analytical bias can be detected, technician performance is documented, and overall laboratory performance can be evaluated. The program has been very successful at satisfying the INPO requirement that the analytical performance of each individual technician should be checked on at least a six-month frequency for all important parameters measured. This paper describes the program as implemented at the Palo Verde Nuclear Generating Station and provides a summary report and trend and bias graphs for illustrative purposes

  6. Systematic generation of rules for nuclear power plant diagnostics

    International Nuclear Information System (INIS)

    Reifman, J.; Lee, J.C.

    1988-01-01

    The knowledge base of an expert system is generally represented by a set of heuristic rules derived from the expert's own experience and judgmental knowledge. These heuristic or production rules are cast as if (condition), then (consequence) statements, and represent, for nuclear power plant diagnostic systems, information connecting symptoms to failures. In this paper, the authors apply an entropy minimax pattern recognition algorithm to automate the process of extracting and encoding knowledge into a set of rules. Knowledge is extracted by recognizing patterns in plant parameters or symptoms associated with failures or transient events, and is encoded by casting the discovered patterns as production rules. The paper discusses how the proposed method can systematically generate rules that characterize failure of pressurizer components based on transient events analyzed with a pressurizer components based on transient events analyzed with a pressurizer water reactor simulator program

  7. Public response to the Diablo Canyon Nuclear Generating Station

    International Nuclear Information System (INIS)

    Pijawka, K.D.

    1982-01-01

    The authors examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response

  8. Public response to the Diablo Canyon Nuclear Generating Station

    International Nuclear Information System (INIS)

    Pijawka, K.D.

    1982-01-01

    We examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response. (author)

  9. Hipse: an event generator for nuclear collisions at intermediate energies

    International Nuclear Information System (INIS)

    Lacroix, D.; Van Lauwe, A.; Durand, D.

    2003-11-01

    An event generator, HIPSE (Heavy-Ion Phase-Space Exploration), dedicated to the description of nuclear collisions in the intermediate energy range is presented. Based on the sudden approximation and on geometrical hypothesis, it can conveniently simulate heavy-ion interactions at all impact parameters and thus can constitute a valuable tool for the understanding of processes such as neck emission or multifragmentation in peripheral or/and central collisions. After a detailed description of the ingredients of the model, first comparisons with experimental data collected by the INDRA collaboration are shown. Special emphasis is put on the kinematical characteristics of fragments and light particles observed at all impact parameters for Xe+Sn reactions at 25 and 50 MeV/u and Ni + Ni at 82 MeV/u. (authors)

  10. Public response to the Diablo Canyon Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Pijawka, K D [Arizona State Univ., Tempe (USA)

    1982-08-01

    We examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response.

  11. Analysis of the environmental impact generated by nuclear activities

    International Nuclear Information System (INIS)

    Lazar, Roxana Elena; Dumitrescu, Maria

    2000-01-01

    Assessment of environmental impact represents one of the most formalized examples of interdisciplinary approach. After more then a century from the introduction of the concept of environmental impact assessment, this undertaking still represents an amalgamation of mini-studies based on pre-determined approaches rather than a genuine integrated document. This work presents the most important and adequate techniques of analysis of environmental impact generated by nuclear activities starting from identification of the events causing negative effects upon environment (by using checking list, the matrices and the cause-effect diagram) and radiation dose determination up to the decision making process. To preserve environment integrity the human factor should be re-evaluated as well as its active participation in formation and settling of an real environmental culture

  12. Exergy analysis for Generation IV nuclear plant optimization

    International Nuclear Information System (INIS)

    Gomez, A.; Azzaro-Pantel, C.; Domenech, S.; Pibouleau, L.; Latge, Ch.; Haubensack, D.; Dumaz, P.

    2010-01-01

    This paper deals with the application of the exergy concept to an energy production system involving a very high temperature reactor coupled with an innovative electricity-generating cycle. The objective is to propose a general approach to quantify exergy destruction of the involved process components, modelled by a thermodynamic simulator (Proceedings of the Conference on High Temperature Reactors, Beijing, China, 22-24 September 2004, International Atomic Agency, Vienna (Austria), HTR-2004; 1-11). The minimization of exergy destruction is then identified as the optimization criterion used in an optimization framework based on a genetic algorithm, in which the model is embedded. Finally, the approach is applied to electrical production by a Brayton-Rankine combined cycle connected to a nuclear reactor. Some typical results are presented. The perspectives of this work including the cogeneration of hydrogen and electricity are highlighted. (authors)

  13. Exergy analysis for Generation IV nuclear plant optimization

    Energy Technology Data Exchange (ETDEWEB)

    Gomez, A.; Azzaro-Pantel, C.; Domenech, S.; Pibouleau, L. [Univ Toulouse, Lab Genie Chim, CNRS, UMR 5503, F-31700 Toulouse 1 (France); Latge, Ch. [CEA Cadarache DEN DTN DIR, St Paul Les Durance, (France); Haubensack, D.; Dumaz, P. [CEA Cadarache DEN DER SESI LCSI, St Paul Les Durance (France)

    2010-07-01

    This paper deals with the application of the exergy concept to an energy production system involving a very high temperature reactor coupled with an innovative electricity-generating cycle. The objective is to propose a general approach to quantify exergy destruction of the involved process components, modelled by a thermodynamic simulator (Proceedings of the Conference on High Temperature Reactors, Beijing, China, 22-24 September 2004, International Atomic Agency, Vienna (Austria), HTR-2004; 1-11). The minimization of exergy destruction is then identified as the optimization criterion used in an optimization framework based on a genetic algorithm, in which the model is embedded. Finally, the approach is applied to electrical production by a Brayton-Rankine combined cycle connected to a nuclear reactor. Some typical results are presented. The perspectives of this work including the cogeneration of hydrogen and electricity are highlighted. (authors)

  14. How and when 4. generation nuclear systems could deploy?

    International Nuclear Information System (INIS)

    Safa, H.; Bonin, B.

    2007-01-01

    Fast reactors exhibit two major advantages over classical thermal reactors: sustainability and waste minimization. The deployment of 4. generation nuclear reactors depends on economical, industrial and political issues. We feel that the waste radiotoxicity reduction argument, although very crucial and socially sensitive, could not by itself justify implementing a new reactor system including a dedicated reprocessing scheme. But the foreseen tension of the uranium market may urge on developing fast reactor systems. Putting aside politics, we tentatively try to answer a very simple question: At which uranium price will it be economically competitive to build a fast reactor instead of a light water one? The leveled cost of nuclear electricity is analyzed and split into its different components (investment, fuel supply, fuel cycle,..). Assuming some minimal and reasonable hypotheses, fast reactors costs are compared with light water ones. The uranium price necessary to compensate for the higher investment cost of fast reactors is then deduced. One major conclusion that can be drawn from our study may be summarized as follows: if the uranium market price maintains its present level for a long period of time, fast reactors are already today an economically attractive option. (authors)

  15. How and when 4. generation nuclear systems could deploy?

    Energy Technology Data Exchange (ETDEWEB)

    Safa, H.; Bonin, B. [CEA Saclay, Dir. de l' Energie Nucleaire, 91 - Gif sur Yvette (France)

    2007-07-01

    Fast reactors exhibit two major advantages over classical thermal reactors: sustainability and waste minimization. The deployment of 4. generation nuclear reactors depends on economical, industrial and political issues. We feel that the waste radiotoxicity reduction argument, although very crucial and socially sensitive, could not by itself justify implementing a new reactor system including a dedicated reprocessing scheme. But the foreseen tension of the uranium market may urge on developing fast reactor systems. Putting aside politics, we tentatively try to answer a very simple question: At which uranium price will it be economically competitive to build a fast reactor instead of a light water one? The leveled cost of nuclear electricity is analyzed and split into its different components (investment, fuel supply, fuel cycle,..). Assuming some minimal and reasonable hypotheses, fast reactors costs are compared with light water ones. The uranium price necessary to compensate for the higher investment cost of fast reactors is then deduced. One major conclusion that can be drawn from our study may be summarized as follows: if the uranium market price maintains its present level for a long period of time, fast reactors are already today an economically attractive option. (authors)

  16. World electricity generation, nuclear power, and oil markets

    International Nuclear Information System (INIS)

    1990-01-01

    Striking changes have characterized the world's production and use of energy over the past 15 years. Most prominent have been the wide price fluctuations, politicization of world oil prices and supply, along with profound changes in patterns of production and consumption. This report, based on a study by energy analysts at Science Concepts, Inc., in the United States, traces changes in world energy supply since 1973-74 - the time of the first oil ''price shocks''. In so doing, it identifies important lessons for the future. The study focused in particular on the role of the electric power sector because the growth in fuel use in it has been accomplished without oil. Instead, the growth has directly displaced oil. In the pre-1973 era, the world relied increasingly on oil for many energy applications, including the production of electricity. By 1973, more than on-fourth of the world's electricity was produced by burning oil. By 1987, however, despite a large increase in electric demand, the use of oil was reigned back to generating less than 10% of the world's electricity. Nuclear power played a major role in this turnaround. From 1973-87, analysts at Science Concepts found, nuclear power displaced the burning of 11.7 billion barrels of oil world-wide and avoided US $323 billion in oil purchases

  17. Control technology for nuclear power system of next generation

    International Nuclear Information System (INIS)

    1995-01-01

    This report is the summary of the results obtained by the investigation activities for two years carried out by the expert committee on investigation of control technology for nuclear power system of next generation. The course of investigation is outlined, and as the results, as advanced control technologies, adaptive control. H sub (infinite) control, fuzzy control and the application of autonomous distributed system and genetic algorithm to control; as operation support technology, the operation and monitoring system for nuclear power plants and safety support system; as interface technology which is the basic technology of them, virtual reality, multimedia and so on; further, various problems due to human factors, computer technology, artificial intelligence and others were taken up, and the grasp of the present status and the future subjects was carried out, including the information in international conferences. The items of the investigation are roughly divided into measurement and control technologies, interface technology and operation support, human factors, computer technology and artificial intelligence, and the trend in foreign countries, and the results of investigation for respective items are reported. (K.I.)

  18. Development situation about the Canadian CANDU Nuclear Power Generating Stations

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

    2009-07-15

    The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century.

  19. Development situation about the Canadian CANDU Nuclear Power Generating Stations

    International Nuclear Information System (INIS)

    Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

    2009-07-01

    The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century

  20. 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.)

  1. Metrology for New Generation Nuclear Power Plants - MetroFission

    International Nuclear Information System (INIS)

    Johansson, Lena; Dinsdale, Alan; Keightley, John; Filtz, Jean-Remy; Hay, Bruno; DeFelice, Pierino; Sadli, Mohamed; Plompen, Arjan; Heyse, Jan; Pomme, Stefaan; Cassette, Philippe

    2013-06-01

    MetroFission project has been looking at solving metrological problems related to a new generation of NPPs. The proposed Gen. IV NPPs are designed to run safely, make efficient use of natural resources, minimize the waste and maintain proliferation resistance. In order to reach these goals, the reactor operation involves higher temperatures, high-energy neutron fluence, different types of fuel where the minor actinides are included etc. The work has focused on improved temperature measurements, investigation of thermal properties of advanced materials, determination of new and relevant nuclear data and development of measurement techniques for radionuclides suitable for Gen. IV NPPs. The improved temperature measurement for nuclear power plant applications includes the development of a new Fe-C fixed point. Robust, repeatable and versatile cells have been constructed and compared with success among the project participants and their melting temperatures have been determined. Methodology of self-validating thermocouples has proven efficient at several fixed point temperatures using different designs. A practical acoustic thermometer has been tested at 1000 deg. C with success thanks to the use of innovative signal processing methods. Mo/Nb thermocouples have been obtained with different sheath materials and tested with the aim to achieve for the first time a reference function determined with the best possible uncertainties. Following reviews of designs and technology proposed for fourth generation nuclear plants effort within this project, with regards to thermal properties of advanced materials for nuclear design, has concentrated on provision of thermodynamic data to support the development of the sodium cooled fast reactor. Data has been critically assessed to represent the potential interaction between the Na coolant and the nuclear fuel taken to be based on (U, Pu)O 2 but incorporating minor actinides such as Np and Am. Data for the fission products and

  2. The technology of the bearings used in the nuclear power generation system turbine generator units

    International Nuclear Information System (INIS)

    Vialettes, J.M.; Rossato, M.

    1997-01-01

    A bearing consists of all the stationary part which allow the relative motion in rotation or in translation, of a shaft line. Inside the bearing there is a journal bearing with a metallic anti-friction coating (the babbitt metal). The high power turbine generator unit rotors are supported by smooth transversal journal bearings fed with oil which fills the empty space and runs along the shaft. The technologies used for the bearings and the thrust bearings of the turbine generator units and the various shaft lines of the French CP0/CP1- and CP2/1300 MW-type nuclear power plants are described. The experience feedback is then discussed in terms of the dynamics of the shaft line, i.e. vibrational problems, the influence of the alignment and the babbitt metal incidents. (author)

  3. Advanced ceramic materials for next-generation nuclear applications

    Science.gov (United States)

    Marra, John

    2011-10-01

    The nuclear industry is at the eye of a 'perfect storm' with fuel oil and natural gas prices near record highs, worldwide energy demands increasing at an alarming rate, and increased concerns about greenhouse gas (GHG) emissions that have caused many to look negatively at long-term use of fossil fuels. This convergence of factors has led to a growing interest in revitalization of the nuclear power industry within the United States and across the globe. Many are surprised to learn that nuclear power provides approximately 20% of the electrical power in the US and approximately 16% of the world-wide electric power. With the above factors in mind, world-wide over 130 new reactor projects are being considered with approximately 25 new permit applications in the US. Materials have long played a very important role in the nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced reactor systems and fuel cycles that minimize waste and increase proliferation resistance, materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Advanced metallic and ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles, advanced alloy fuels for 'deep-burn' applications, as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, a number of fuel reprocessing operations are being investigated. Advanced materials continue to provide a vital contribution in 'closing the fuel cycle' by stabilization of associated low-level and high-level wastes in highly durable cements, ceramics, and glasses. Beyond this fission energy application, fusion energy will demand advanced materials capable of withstanding the extreme environments of high

  4. Advanced ceramic materials for next-generation nuclear applications

    Energy Technology Data Exchange (ETDEWEB)

    Marra, John [Savannah River National Laboratory Aiken, SC 29802 (United States)

    2011-10-29

    The nuclear industry is at the eye of a 'perfect storm' with fuel oil and natural gas prices near record highs, worldwide energy demands increasing at an alarming rate, and increased concerns about greenhouse gas (GHG) emissions that have caused many to look negatively at long-term use of fossil fuels. This convergence of factors has led to a growing interest in revitalization of the nuclear power industry within the United States and across the globe. Many are surprised to learn that nuclear power provides approximately 20% of the electrical power in the US and approximately 16% of the world-wide electric power. With the above factors in mind, world-wide over 130 new reactor projects are being considered with approximately 25 new permit applications in the US. Materials have long played a very important role in the nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced reactor systems and fuel cycles that minimize waste and increase proliferation resistance, materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Advanced metallic and ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles, advanced alloy fuels for 'deep-burn' applications, as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, a number of fuel reprocessing operations are being investigated. Advanced materials continue to provide a vital contribution in 'closing the fuel cycle' by stabilization of associated low-level and high-level wastes in highly durable cements, ceramics, and glasses. Beyond this fission energy application, fusion energy will demand advanced materials capable of withstanding the extreme

  5. Next Generation Nuclear Plant Intermediate Heat Exchanger Acquisition Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Mizia, Ronald Eugene [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2008-04-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C to 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium cooled, prismatic or pebble-bed reactor, and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. The purpose of this report is to address the acquisition strategy for the NGNP Intermediate Heat Exchanger (IHX).This component will be operated in flowing, impure helium on the primary and secondary side at temperatures up to 950°C. There are major high temperature design, materials availability, and fabrication issues that need to be addressed. The prospective materials are Alloys 617, 230, 800H and X, with Alloy 617 being the leading candidate for the use at 950°C. The material delivery schedule for these materials does not pose a problem for a 2018 start up as the vendors can quote reasonable delivery times at the moment. The product forms and amount needed must be finalized as soon as possible. An

  6. 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)

  7. 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.

  8. 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

  9. Nuclear Fusion Effects Induced in Intense Laser-Generated Plasmas

    Directory of Open Access Journals (Sweden)

    Lorenzo Torrisi

    2013-01-01

    Full Text Available Deutered polyethylene (CD2n thin and thick targets were irradiated in high vacuum by infrared laser pulses at 1015W/cm2 intensity. The high laser energy transferred to the polymer generates plasma, expanding in vacuum at supersonic velocity, accelerating hydrogen and carbon ions. Deuterium ions at kinetic energies above 4 MeV have been measured by using ion collectors and SiC detectors in time-of-flight configuration. At these energies the deuterium–deuterium collisions may induce over threshold fusion effects, in agreement with the high D-D cross-section valuesaround 3 MeV energy. At the first instants of the plasma generation, during which high temperature, density and ionacceleration occur, the D-D fusions occur as confirmed by the detection of mono-energetic protonsand neutrons with a kinetic energy of 3.0 MeV and 2.5 MeV, respectively, produced by the nuclear reaction. The number of fusion events depends strongly on the experimental set-up, i.e. on the laser parameters (intensity, wavelength, focal spot dimension, target conditions (thickness, chemical composition, absorption coefficient, presence of secondary targets and used geometry (incidence angle, laser spot, secondary target positions.A number of D-D fusion events of the order of 106÷7 per laser shot has been measured.

  10. Recent technology for nuclear steam turbine-generator units

    International Nuclear Information System (INIS)

    Moriya, Shin-ichi; Kuwashima, Hidesumi; Ueno, Takeshi; Ooi, Masao

    1988-01-01

    As the next nuclear power plants subsequent to the present 1,100 MWe plants, the technical development of ABWRs was completed, and the plan for constructing the actual plants is advanced. As for the steam turbine and generator facilities of 1,350 MWe output applied to these plants, the TC6F-52 type steam turbines using 52 in long blades, moisture separation heaters, butterfly type intermediate valves, feed heater drain pumping-up system and other new technologies for increasing the capacity and improving the thermal efficiency were adopted. In this paper, the outline of the main technologies of those and the state of examination when those are applied to the actual plants are described. As to the technical fields of the steam turbine system for ABWRs, the improvement of the total technologies of the plants was promoted, aiming at the good economical efficiency, reliability and thermal efficiency of the whole facilities, not only the main turbines. The basic specification of the steam turbine facilities for 50 Hz ABWR plants and the main new technologies applied to the turbines are shown. The development of 52 in long last stage blades, the development of the analysis program for the coupled vibration of the large rotor system, the development of moisture separation heaters, the turbine control system, condensate and feed water system, and the generators are described. (Kako, I.)

  11. The spanish electric system operation. The contribution of nuclear generation

    International Nuclear Information System (INIS)

    Duvison, M. R.; Torre, M. de la

    2009-01-01

    Operation of an electric system encloses the collection of activities which extend from affective generation dispatch to issuing instruction for network manoeuvring along with international exchange scheduling. Based on the market mechanisms that apply to energy transactions, these tasks guarantee the security of supply end consumers, which is the final goal of the System Operators actions. In Spain this function is executed by Red Electrica de Espana (REE) since 1985, after being constituted as the first Transmission and System Operator (TSO) in the world. Additionally the variations to Law 54/1997 introduced by law 17/2007 also assign REE the function of sole transmission owner in the Spanish electric system. In order to achieve the aforementioned goal, nuclear energy plays in Spain a fundamental role in electric generation thanks to its high availability rate, the predictability of its fuel recharges, its high operational reliability, its geographical location, the stability of its costs and the security of supply given by the possibility of on-site fuel storage in the power plant. (Author)

  12. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

    2006-10-02

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector

  13. 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

  14. Sensitivity to temperature of nuclear energy generation by hydrogen burning

    International Nuclear Information System (INIS)

    Mitalas, R.

    1981-01-01

    The sensitivity to temperature of nuclear energy generation by hydrogen burning is discussed. The complexity of the sensitivity is due to the different equilibration time-scales of the constituents of the p-p chain and CN cycle and the dependence of their abundances and time-scales on temperature. The time-scale of the temperature perturbation, compared to the equilibrium time-scale of a constituent, determines whether the constituent is in equilibrium and affects the sensitivity. The temperature sensitivity of the p-p chain for different values of hydrogen abundance, when different constituents come into equilibrium is presented, as well as its variation with 3 He abundance. The temperature sensitivity is drastically different from n 11 , the temperature sensitivity of the proton-proton reaction, unless the time-scale of temperature perturbation is long enough for 3 He to remain in equilibrium. Even in this case the sensitivity of the p-p chain differs significantly from n 11 , unless the temperature is so low that PP II and PP III chains can be neglected. The variation of the sensitivity of CN energy generation is small for different time-scales of temperature variation, because the temperature sensitivities of individual reactions are so similar. The combined sensitivity to temperature of energy generation by hydrogen burning is presented and shown to have a maximum of 16.4 at T 6 = 24.5. For T 6 > 25 the temperature sensitivity is given by the sensitivity of 14 N + p reaction. (author)

  15. 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)

  16. Next Generation Nuclear Plant Materials Research and Development Program Plan

    International Nuclear Information System (INIS)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-01-01

    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. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R and D) Program is responsible for performing R and D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R and D Program includes the following elements: (1) Developing a specific approach, program plan and other project management

  17. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    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. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  18. 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)

  19. 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)

  20. Steam generator maintenance and life management at Embalse Nuclear Station

    International Nuclear Information System (INIS)

    Sainz, R.; Diaz, G.; Sveruga, H.; Ramakrishnan, T.K.; Azeez, S.

    2004-01-01

    The Embalse Nuclear Station has four steam generators (SGs) with inverted vertical U tubes manufactured by Babcock and Wilcox Canada (B and W). These are main components, both from the operative point of view as the heat transfer from the Primary Heat Transport System (PHTS) to the Secondary System, and from the point of view of safety, as they are the part of the PHTS and its radioactive inventory pressure barrier. In addition, they are one of the most important cost-related elements for potential life extensions. Maintenance and inspections are carried out in order to maintain a high availability of the SGs, as they have had a positive impact on the operational availability of the plant, and to reduce the tube failure probabilities, thus minimizing the amount of radioactive effluents and taking care of the condition of the main components in order to enable the plant life management and the planning of the plant life extension. The most relevant maintenance activities performed have been the inspections performed on 100% of the tubes every 3 years. the mechanical cleaning of the inside of the tubes, the sludge removal from the secondary side tubesheet, the divider plate replacement, and the inspection of internals of the secondary side.Thanks to the latter and to the eddy current inspections, the degradation in the U-bend supports was detected early and every effort is being made to repair them shortly. Besides, a life management program has been started covering the entire plant starting with this important component. The Embalse Nuclear Station's SGs show a low percentage of plugged tubes compared to other stations in similar conditions, but they must be monitored continually and systematically if a life extension is intended. (author)

  1. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    International Nuclear Information System (INIS)

    Chadwick, M.B.; Oblozinsky, P.; Herman, M.

    2006-01-01

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes, based on experimental data and theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, 6 Li, 10 B, Au and for 235,238 U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced evaluations up to 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; (10) New methods for uncertainties and covariances, together with covariance evaluations for some sample cases; and (11) New actinide fission energy deposition. The paper provides an overview of this library, consisting of 14 sublibraries in the same ENDF-6 format as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched uranium thermal assemblies is removed; (b) The 238 U and 208 Pb reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good

  2. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

  3. Nuclear power plants: 2004 atw compact statistics

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    In late 2004, nuclear power plants were available for power supply or were under construction in 32 countries worldwide. A total of 441 nuclear power plants, i.e. two plants more than in late 2003, were in operation with an aggregate gross power of approx. 386 GWe and an aggregate net power, respectively, of 362 GWe, in 31 countries. The available capacity of nuclear power plants increased by approx. 5 GWe as a result of the additions by the six units newly commissioned: Hamaoka 5 (Japan), Ulchin 6 (Korea), Kalinin 3 (Russia), Khmelnitski 2 (Ukraine), Qinshan II-2 (People's Republic of China), and Rowno 4 (Ukraine). In addition, unit 3 of the Bruce A nuclear power plant in Canada with a power of 825 MWe was restarted after an outage of many years. Contrary to earlier plans, a recommissioning program was initiated for the Bruce A-1 and A-2 units, which are also down at present. Five plants were decommissioned for good in 2004; Chapelcross 1 to 4 with 50 MWe each in the United Kingdom, and Ignalina 1 with 1 300 MWe in Lithuania. 22 nuclear generating units with an aggregate gross power of 19 GWe in nine countries were under construction in late 2004. In India, construction work was started on a new project, the 500 MWe PFBR prototype fast breeder reactor. In France, the EDF utility announced its intention to build an EPR on the Flamanville site beginning in 2007. (orig.)

  4. Primary Water Chemistry Control during a Planned Outage at Bruce Power

    International Nuclear Information System (INIS)

    Ma, Guoping; Nashiem, Rod; Matheson, Shane; Yabar, Berman; Harper, Bill; Roberts, John G.

    2012-09-01

    Bruce Power has developed a comprehensive outage water chemistry program, which includes both primary and secondary chemistry requirements during planned outages. The purpose of the program is to emphasize the chemistry requirements during outages and subsequent start-ups in order to maintain the integrity of the systems, minimise activity transport and radiation fields, reduce the Carbon-14 release, and to ensure that the requirements are integrated with the outage management program. Prior to a planned outage, Station Chemical Technical Sections identify outage chemistry requirements to Operations and Outage Planning and ensure that work necessary to correct system chemistry issues is within outage work scope. The outage water chemistry program provides direction for establishing alternative sampling locations as demanded by the system configuration during the outage and identifies outage prerequisites for nuclear system purification capabilities. These requirements are contained in an outage checklist. The paper mainly highlights the primary water chemistry issues and chemistry control strategies during planned outages and discusses challenges and successes. (authors)

  5. 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

  6. Next Generation Nuclear Plant Methods Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  7. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  8. Recycling of concrete waste generated from nuclear power plant dismantling

    International Nuclear Information System (INIS)

    Ogawa, Hideo; Nagase, Takahiro; Tanaka, Hiroaki; Nawa, Toyoharu

    2012-01-01

    Non-radioactive concrete waste generated from dismantling of a standard large nuclear power plant is estimated to be about 500,000 tons in weight. Using such waste as recycled aggregate within the enclosure of the plant requires a new manufacturing technology that generates a minimal amount of by-product powder. Recycled aggregate has brittle parts with defects such as cracks, pores, and voids in residual paste from original concrete. This study presents a method of selectively removing the defective parts during manufacture to improve the quality of the recycled fine aggregate. With this selective removal method used, the amount of by-product powder can be reduced by half as compared to that by a conventional method. The influences of the characteristics of the recycled fine aggregate on the flowability and strength of the mortar using recycled fine aggregate were evaluated by multiple linear regression analysis. The results clearly showed that the flowability was primarily affected by the filling fraction of recycled fine aggregate, while the compressive strength of mortar was primarily affected by the fraction of defects in the aggregate. It was also found that grains produced by a granulator have more irregularities in the surfaces than those produced by a ball mill, providing an increased mortar strength. Using these findings from this study, efforts are also being made to develop a mechanical technology that enables simultaneous processing of decontamination and recycling. The granulator under consideration is capable of grinding the surfaces of irregularly shaped particles and may be used successfully, under optimal conditions, for the surface decontamination of concrete waste contaminated with radioactive materials. (author)

  9. Recycling of concrete generated from Nuclear Power Plant dismantling

    International Nuclear Information System (INIS)

    Ogawa, Hideo; Nawa, Toyoharu; Ishikura, Takeshi; Tanaka, Hiroaki

    2013-01-01

    Reactor decommissioning required various technologies such as dismantling of facilities, decontamination, radioactivity measurement and recycling of dismantling wastes. This article discussed recycling of demolished concrete wastes. Dismantling of reactor building of large one unit of nuclear power plants would generate about 500 K tons of concrete wastes, about 98% of which was non-radioactive and could be used as base course material or backfill material after crushed to specified particle size. Since later part of 1990s, high quality recycled aggregate with specified limit of bone-dry density, water absorptivity and amount of fine aggregate had been developed from demolished concrete with 'Heat and rubbing method', 'Eccentric rotor method' and 'Screw grinding method' so as to separate cements attached to aggregate. Recycled aggregates were made from concrete debris with 'Jaw crusher' to particle size less than 40 mm and then particle size control or grinded by various grinding machines. Recycled fine aggregates made from crushing would have fragile site with cracks, air voids and bubbles. The author proposed quality improvement method to selectively separate fragile defects from recycled aggregates using weak grinding force, leaving attached pastes much and preventing fine particle generation as byproducts. This article outlined experiments to improve quality of recycled fine aggregates and their experimental results confirmed improvement of flow ability and compressive strength of mortal using recycled fine aggregates using 'Particle size selector' and 'Ball mill' so as to remove their fragile parts less than 2%. Mortal made from recycled fine aggregate could also prevent permeation of chloride ion. Recycled aggregate could be used for concrete instead of natural aggregate. (T. Tanaka)

  10. 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.

  11. 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.

  12. Quality assured technical documentation for nuclear power generation

    International Nuclear Information System (INIS)

    Ault, M.P.

    1992-01-01

    Present day large scale industry in general is made up of highly complex technology subjected to many rigorous external controls and constraints. This is particularly so in the nuclear power industry where it is essential that materials and services provided during the phases of construction, commissioning and operations, conform precisely to requirements as specified. Failure to do this could lead to unit shut-down and loss of income. For over 25 years, a central unit within the Central Electricity Generating Board (CEGB) developed an enviable reputation for the production of high class technical documentation essential during power station commissioning and operations phases. Following privatization of the electricity supply industry in 1991 the unit became a stand-alone organization and since 1989 has been known as Technical Publications Management Services (TPMS). TPMS with its many years of experience now offers its services to industry in general as well as to the electricity supply industry. Work currently being undertaken by TPMS is described here. Recent contracts obtained for work at Sizewell and for Severn Trent Water indicate the continuing and expanding need for specialist documentation services. (author)

  13. Concentration processes under tubesheet sludge piles in nuclear steam generators

    International Nuclear Information System (INIS)

    Gonzalez, F.; Spekkens, P.

    1987-01-01

    The process by which bulk water solutes are concentrated under tubesheet sludge piles in nuclear steam generators was investigated in the laboratory under simulated CANDU operating conditions. Concentration rates were found to depend on the tube heat flux and pile depth, although beyond a critical depth the concentration efficiency decreased. This efficiency could be expressed by a concentration coefficient, and was found to depend also on the sludge pile porosity. Solute concentration profiles in the sludge pile suggested that the concentration mechanism in a high-porosity/permeability pile is characterized by boiling mainly near or at the tube surface, while in low-porosity piles, the change of phase may also become important in the body of the sludge pile. In all cases, the full depth of the pile was active to some extent in the concentration process. As long as the heat transfer under the pile was continued, the solute remained under the pile and slowly migrated toward the bottom. When the heat transfer was stopped, the solute diffused back into the bulk solution at a rate slower than that of the concentration process

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

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Doh; Kil, Chung Sub [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    Data testing of ENDF/B-VI.2 was performed and ACE-format continuous point-wise cross section library from ENDF/B-VI.2 for MCNP was validated through CSEWG benchmark and power plant mockup experiments. The calculated k-effective of ORNL-1, -2, -3, -4 and -10 with ENDF/B-VI are low by about 0.5% but those of L-7, -8, -9, -10 and -11 show good agreement with experiments. Overall results for uranium core with ENDF/B-VI is low in critically than with ENDF/B-V. The calculated results with ENDF/B-VI for PNL-6 {approx} 12 of plutonium core and PNL-30 {approx} 35 of mixed oxide core show good agreement with the experiments. The results of critically calculation for fast core benchmark do not show large difference between ENDF/B-VI and -V. But the calculated results of reaction rate ratio with ENDF/B-VI are improved, compared with ENDF/B-V. The calculated power distribution for VENUS PWR mockup core and typical BWR core of GE with both of ENDF/B-VI and -V agree well with measured values. From the above results, newly generated MCNP library from ENDF/B-VI is useful for nuclear and shielding design and analysis. 5 figs, 13 tabs, 11 refs. (Author).

  15. Steam generator management at Ontario Hydro Nuclear Stations

    International Nuclear Information System (INIS)

    Nickerson, J.; Maruska, C.C.

    1998-01-01

    Managing ageing steam generators involves costly decisions for the utility, both in terms of the cost of the maintenance activities and in terms of having the unit shutdown and consequent power loss while performing these activities. The benefits of these activities are seldom guaranteed and are sometimes very intangible. For nuclear utilities the most pertinent questions that arise are have we identified all the problem(s), can we predict the risk due to these problems? Can we implement corrective and preventive activities to manage the problem and what is the optimum timing of implementation? Is the money spent worthwhile, i.e. has it given us a return in production and safety? Can we avoid surprises? How can we tangibly measure success? This paper touches briefly on all the questions mentioned above but it mainly addresses the last question: 'how can we tangibly measure success?' by using several success indicators proposed by EPRI and by applying them to actual Ontario Hydro experience. The appropriateness of these success indicators as the means to assess the success of these programs, to feed back the results, and to enhance or revise the programs will be discussed. (author)

  16. Strain measurement on a compact nuclear reactor steam generator

    International Nuclear Information System (INIS)

    Scaldaferri, Denis Henrique Bianchi; Gomes, Paulo de Tarso Vida; Mansur, Tanius Rodrigues; Pozzo, Renato del; Mola, Jairo

    2011-01-01

    This work presents the strain measurement procedures applied to a compact nuclear reactor steam generator, during a hydrostatic test, using strain gage technology. The test was divided in two steps: primary side test and secondary side test. In the primary side test twelve points for strain measurement using rectangular rosettes, three points (two external and one internal) for temperature measurement using special strain gages and one point for pressure measurement using a pressure transducer were monitored. In the secondary side test 18 points for strain measurement using rectangular rosettes, four points (two external and two internal) for temperature measurement using special strain gages and one point for pressure measurement using a pressure transducer were monitored. The measurement points on both internal and external pressurizer walls were established from pre-calculated stress distribution by means of numerical approach (finite elements modeling). Strain values using a quarter Wheatstone bridge circuit were obtained. Stress values, from experimental strain were determined, and to numerical calculation results were compared. (author)

  17. Parametric utility comparison of coal and nuclear electricity generation

    International Nuclear Information System (INIS)

    Maurer, K.M.

    1977-02-01

    The advantages and limitations of an explicit quantitative model for decision making are discussed. Several different quantitative models are presented, noting that the use of an expected utility maximization decision rule allows both the direct incorporation of multidimensional descriptions of the possible outcomes, and considerations of risk averse behavior. A broad class of utility functions, characterized by linear risk tolerance, was considered and extended to a multidimensional form. Choosing a multivariate risk neutral extension, using constant absolute risk aversion utility functions for monetary effects and for increased mortality, the author indicated how the parameters of this utility function can be selected to represent the decision maker's preferences, and suggest a reasonable range of values for the parameters. After describing an illustrative set of data on the risks inherent in coal burning and nuclear electricity generation facilities, the author used the chosen utility model to compare the overall risks associated with each technology, observing the effect of variations in the utility parameters and in the risk distributions on the implied preferences

  18. Steam generator management at Ontario Hydro Nuclear Stations

    Energy Technology Data Exchange (ETDEWEB)

    Nickerson, J. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Maruska, C.C. [Ontario Hydro, Toronto, Ontario (Canada)

    1998-07-01

    Managing ageing steam generators involves costly decisions for the utility, both in terms of the cost of the maintenance activities andin terms of having the unit shutdown and consequent power loss while performing these activities. The benefits of these activities are seldom guaranteed and are sometimes very intangible. For nuclear utilities the most pertinent questions that arise are have we identified all the problem(s), can we predict the risk due to these problems? Can we implement corrective and preventive activities to manage the problem and what is the optimum timing of implementation? Is the money spent worthwhile, i.e. has it given us a return in production and safety? Can we avoid surprises? How can we tangibly measure success? This paper touches briefly on all the questions mentioned above but it mainly addresses the last question: 'how can we tangibly measure success?' by using several success indicators proposed by EPRI and by applying them to actual Ontario Hydro experience. The appropriateness of these success indicators as the means to assess the success of these programs, to feed back the results, and to enhance or revise the programs will be discussed. (author)

  19. Generation 4 International Forum. 2009 GIF R and D outlook for generation 4 nuclear energy systems

    International Nuclear Information System (INIS)

    2009-01-01

    This document presents the state, at mid 2009, of research and development of the 6 reactor types that were selected in the framework of the GIF (Generation 4 International Forum): VHTR (Very High Temperature Reactor), SFR (Sodium-cooled Fast Reactor), SCWR (Super-Critical Water Reactor), GFR (Gas-cooled Fast Reactor), LFR (Lead-cooled reactor), and MSR (Molten Salt Reactor). Regarding each type of reactors, the state of advancement is reported for the reactor itself, its specific components and materials, its nuclear fuel, and its fuel cycle. The outlook of development and research work is also given for the next 5 years for the 6 types of reactors. (A.C.)

  20. Next Generation Nuclear Plant Pre-Conceptual Design Report

    International Nuclear Information System (INIS)

    Larry Demick; Doug Vandel

    2007-01-01

    The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear based technology can provide high-temperature process heat (up to 950 C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications. The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively1 safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to current and advanced light water reactors (LWRs). In the Energy Policy Act of 2005 (EPAct), the Department of Energy (DOE) was tasked with providing a demonstration of this HTGR technology to economically and reliably produce electricity and hydrogen by the year 2021. As the lead nuclear technology development laboratory of the DOE, the Idaho National Laboratory (INL) has initiated the work necessary to complete this task. The EPAct also stipulated that the task should be undertaken in partnership with the industrial end users of the technology. To that end, a working group has been assembled consisting of suppliers of the technology, nuclear plant owner/operators, other supportive technology companies, and potential end users. The objective of the working group is to form an Alliance that would provide the private sector perspective and direction for completion of the NGNP in partnership with the DOE. The Alliance will support the selection of the specific operating conditions and configuration for NGNP to ensure it meets private sector expectations, commence

  1. Next Generation Nuclear Plant Project Preliminary Project Management Plan

    International Nuclear Information System (INIS)

    Dennis J. Harrell

    2006-01-01

    This draft preliminary project management plan presents the conceptual framework for the Next Generation Nuclear Plant (NGNP) Project, consistent with the authorization in the Energy Policy Act of 2005. In developing this plan, the Idaho National Laboratory has considered three fundamental project planning options that are summarized in the following section. Each of these planning options is literally compliant with the Energy Policy Act of 2005, but each emphasizes different approaches to technology development risks, design, licensing and construction risks, and to the extent of commercialization support provided to the industry. The primary focus of this draft preliminary project management plan is to identify those activities important to Critical Decision-1, at which point a decision on proceeding with the NGNP Project can be made. The conceptual project framework described herein is necessary to establish the scope and priorities for the technology development activities. The framework includes: A reference NGNP prototype concept based on what is judged to be the lowest risk technology development that would achieve the needed commercial functional requirements to provide an economically competitive nuclear heat source and hydrogen production capability. A high-level schedule logic for design, construction, licensing, and acceptance testing. This schedule logic also includes an operational shakedown period that provides proof-of-principle to establish the basis for commercialization decisions by end-users. An assessment of current technology development plans to support Critical Decision-1 and overall project progress. The most important technical and programmatic uncertainties (risks) are evaluated, and potential mitigation strategies are identified so that the technology development plans may be modified as required to support ongoing project development. A rough-order-of-magnitude cost evaluation that provides an initial basis for budget planning. This

  2. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    P. E. MacDonald

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

  3. 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.

  4. 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

  5. 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)

  6. 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)

  7. Hydraulic Testing of Silurian and Ordovician Strata at the Bruce Site

    Science.gov (United States)

    Beauheim, R. L.; Avis, J. D.; Chace, D. A.; Roberts, R. M.; Toll, N. J.

    2009-05-01

    Ontario Power Generation is proposing a Deep Geologic Repository (DGR) for the long-term management of its Low and Intermediate Level Radioactive Waste (L&ILW) within a Paleozoic-age sedimentary sequence beneath the Bruce Site near Tiverton, Ontario, Canada. The concept envisions that the DGR would be excavated at a depth of approximately 680 m within the Ordovician Cobourg Formation, a massive, dense, argillaceous limestone. A key attribute of the Bruce site is the extremely low permeabilities associated with the thick Ordovician carbonate and argillaceous bedrock formations that will host and enclose the DGR. Such rock mass permeabilities are thought sufficiently low to contribute toward or govern a diffusion-dominated transport regime. To support this concept, hydraulic testing was performed in 2008 and 2009 in two deep boreholes at the proposed repository site, DGR-3 and DGR-4. The hydraulic testing was performed using a straddle-packer tool with a 30.74-m test interval. Sequential tests were performed over the entire open lengths of the boreholes from the F Unit of the Silurian Salina Formation into the Ordovician Gull River Formation, a distance of approximately 635 m. The tests consisted primarily of pressure-pulse tests, with a few slug tests performed in several of the higher permeability Silurian units. The tests are analyzed using the nSIGHTS code, which allows the entire pressure history a test interval has experienced since it was penetrated by the drill bit to be included in the test simulation. nSIGHTS also allows the model fit to the test data to be optimized over an n-dimensional parameter space to ensure that the final solution represents a true global minimum rather than simply a local minimum. The test results show that the Ordovician-age strata above the Coboconk Formation (70+ m below the Cobourg) have average horizontal hydraulic conductivities of 1E-13 m/s or less. Coboconk and Gull River hydraulic conductivities are as high as 1E-11 m

  8. New U.S. Nuclear Generation: 2010-2030

    OpenAIRE

    Geoffrey Rothwell

    2010-01-01

    The report's key finding is that new nuclear capacity in NEMS-RFF from 2015 to 2020 under the current levels of U.S. Department of Energy (DOE) loan guarantees is similar to the marginal increase in new capacity from lowering the nominal return-on-equity (ROE) in NEMS-RFF for new nuclear power from 17 to 14 percent. This equivalence allows for an analysis of the costs and benefits of increasing DOE loan guarantees to new nuclear plants.

  9. 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.)

  10. 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

  11. 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)

  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. 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)

  14. Membranes for H2 generation from nuclear powered thermochemical cycles

    International Nuclear Information System (INIS)

    Nenoff, Tina Maria; Ambrosini, Andrea; Garino, Terry J.; Gelbard, Fred; Leung, Kevin; Navrotsky, Alexandra; Iyer, Ratnasabapathy G.; Axness, Marlene

    2006-01-01

    In an effort to produce hydrogen without the unwanted greenhouse gas byproducts, high-temperature thermochemical cycles driven by heat from solar energy or next-generation nuclear power plants are being explored. The process being developed is the thermochemical production of Hydrogen. The Sulfur-Iodide (SI) cycle was deemed to be one of the most promising cycles to explore. The first step of the SI cycle involves the decomposition of H 2 SO 4 into O 2 , SO 2 , and H 2 O at temperatures around 850 C. In-situ removal of O 2 from this reaction pushes the equilibrium towards dissociation, thus increasing the overall efficiency of the decomposition reaction. A membrane is required for this oxygen separation step that is capable of withstanding the high temperatures and corrosive conditions inherent in this process. Mixed ionic-electronic perovskites and perovskite-related structures are potential materials for oxygen separation membranes owing to their robustness, ability to form dense ceramics, capacity to stabilize oxygen nonstoichiometry, and mixed ionic/electronic conductivity. Two oxide families with promising results were studied: the double-substituted perovskite A x Sr 1-x Co 1-y B y O 3-δ (A=La, Y; B=Cr-Ni), in particular the family La x Sr 1-x Co 1-y Mn y O 3-δ (LSCM), and doped La 2 Ni 1-x M x O 4 (M = Cu, Zn). Materials and membranes were synthesized by solid state methods and characterized by X-ray and neutron diffraction, SEM, thermal analyses, calorimetry and conductivity. Furthermore, we were able to leverage our program with a DOE/NE sponsored H 2 SO 4 decomposition reactor study (at Sandia), in which our membranes were tested in the actual H 2 SO 4 decomposition step

  15. Retrofitting alarm prioritization at Bruce A: strategy development and implementation experience

    International Nuclear Information System (INIS)

    Davey, E.; Hickey, D.; Babcock, B.

    1997-01-01

    A prioritization strategy for computer-displayed control room alarms has been developed for Bruce A to better assist operations staff in visually identifying key alarms and judging the relative importance of alarms. The strategy consists of assigning each alarm indicative of a problem to be addressed to one of five priority categories. Each alarm is assigned to an alarm category based on an off-line analysis of the consequence and response characteristics applicable to the alarm for three plant operating contexts. The colour of the alarm message is used to convey the priority category of each alarm in computer-based alarm displays. In addition, alarms indicative of non-problematic changes in the state of plant equipment and processes are given a separate colour assignment to visually differentiate them from alarms indicative of problems. This paper outlines the user-based approach employed in the prioritization strategy development, describes the key features of the prioritization strategy adopted, and discusses the initial experience in systematically determining the priority assignments for all 6000 computer-based alarms associated with each generating unit. (author)

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. 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)