WorldWideScience

Sample records for epri

  1. EPRI epidemiology

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    A fight is brewing within the electric power community over the fate of a proposed $5 to $8 million epidemiological study of the effects of radiation on US nuclear plant workers. Several industry experts, claiming the project would merely lead to confusion by producing no clear results, are trying to prevent the Electric Power Research Institute (EPRI) from funding what would be the largest ever occupational study of this kind, covering perhaps as many as 500,000 workers. Ralph Lapp, a well-known radiation physicist, says that EPRI is facing unprecedented technical dissent from within. He claims there is already plenty of evidence that nuclear utilities are among the safest places to work, at least in terms of cancer risk, and that the proposed EPRI study would raise new concerns without yielding any answers

  2. EPRI News

    International Nuclear Information System (INIS)

    Douglas, J.

    1991-01-01

    This paper reports that from instant sensation to virtual pariah, cold fusion has had a stormy history since two University of Utah researchers first announced its discovery in March 1989. Research into this mysterious phenomenon has been plagued both by technical difficulties in replicating experimental results and by sometimes bitter controversy over scientific standards and personal credibility. Now, in a somewhat calmer atmosphere, significant progress is being made through experiments that are reproducible over long periods of time and under a variety of conditions. These experiments indicate that nuclear reactions may indeed occur at room temperature in a crystal lattice in ways not understood before. It's time we stopped calling these reactions cold fusion, says David Worledge, EPRI coordinator of research in this area. There is now good evidence that cold nuclear reaction of some sort are taking place, but also growing indications that they aren't conventional deuterium-deuterium fusion, as first assumed. Also, the cold nuclear reactions inferred from the neutrons that have been detected are not numerous enough to be responsible for the excess heat production still being reported in some experiments. In their original work, University of Utah scientist Martin Fleischmann and Stanley Pons used a simple laboratory apparatus consisting of a palladium rod surrounded by a platinum coil and immersed in heavy water. They reported that when a small electric current was applied to the cells, deuterium nuclei from the heavy water were driven into the palladium rod, where they were held in the metal lattice and apparently fused, producing 4 watts of heat for each watt of electric power supplied

  3. EPRI waste processing projects

    International Nuclear Information System (INIS)

    Shaw, R.A.

    1987-01-01

    The Electric Power Research Institute (EPRI) manages research for its sponsoring electric utilities in the United States. Research in the area of low level radioactive waste (LLRW) from light water reactors focuses primarily on waste processing within the nuclear power plants, monitoring of the waste packages, and assessments of disposal technologies. Accompanying these areas and complimentary to them is the determination and evaluation of the sources of nuclear power plants radioactive waste. This paper focuses on source characterization of nuclear power plant waste, LLRW processing within nuclear power plants, and the monitoring of these wastes. EPRI's work in waste disposal technology is described in another paper in this proceeding by the same author. 1 reference, 5 figures

  4. EPRI steam generator programs

    International Nuclear Information System (INIS)

    Martel, L.J.; Passell, T.O.; Bryant, P.E.C.; Rentler, R.M.

    1977-01-01

    The paper describes the current overall EPRI steam generator program plan and some of the ongoing projects. Because of the recent occurrence of a corrosion phenomenon called ''denting,'' which has affected a number of operating utilities, an expanded program plan is being developed which addresses the broad and urgent needs required to achieve improved steam generator reliability. The goal of improved steam generator reliability will require advances in various technologies and also a management philosophy that encourages conscientious efforts to apply the improved technologies to the design, procurement, and operation of plant systems and components that affect the full life reliability of steam generators

  5. EPRI perspective of owner groups

    International Nuclear Information System (INIS)

    Dau, G.J.

    1988-01-01

    A survey was conducted to evaluate the utilities' perspective of the success of efforts of the Electric Power Research Institute (EPRI) and owner groups for the development and implementation of advanced technology. The source of the advanced technology was the result of a joint effort between EPRI and two utility owner groups. The former performs generic research and development (R and D) on behalf of its members drawn from the US electric utility industry. Owner groups are short-term associations of a group of utilities, all confronted with the same problem. Management implications for both EPRI and the utilities are drawn from the results and are summarized. They include recognition that EPRI's reputation for objectivity is an important asset that must be protected. Other implications include assessments of the merits and options for building better utility/NRC relations and strengthening the utility/EPRI relationship. Addressing the implications does not hinge on any major new development. Rather, it depends on EPRI and utility management making the commitment to support efforts to increase the intensity of communication on the baseline program. The resources needed are mainly provision of adequate staff time and attendant travel expenses

  6. EPRI research on accident management

    International Nuclear Information System (INIS)

    Oehlberg, R.N.; Chao, J.

    1991-01-01

    The paper discusses Nuclear Regulatory Commission (NRC) efforts regarding severe reactor accident management and the Nuclear Management and Resources Council (NUMAEX), activities. (EPRI) Electric Power Research Institute accident management program consists of the two products just mentioned plus one related to severe accident plant status information and the MAAP 4.0 computer code. These are briefly discussed

  7. Computerized materials data at EPRI

    International Nuclear Information System (INIS)

    Gilman, J.

    1985-01-01

    In this paper an overview of the development of materials database systems is given as well as brief descriptions of several databases built by the Electric Power Research Institute (EPRI) for the Nuclear Power Industry. A number of important lessons about databases have been learned by EPRI and will be discussed. A schematic outline of the major steps in developing a database is given in figure 6. For materials properties in general, the process begins with raw data from laboratory tests which are recorded by a variety of media which may or may not be machine-readable. After compilation, which often requires manual transcription, checking, and reformatting, the assembled data are loaded into a database. Associated with the database is computer software that allows for sorting, searching, etc., and is called the database management system. In addition, other software can provide statistical analysis and graphical displays

  8. EPRI instruments reach commercial market

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    The Electric Power Research Institute has developed instruments capable of verifying time responses of power plant pressure sensors and temperature sensors. A patent is pending on the pressure-sensor device, and the temperature-sensor device is already commercially available. The devices, EPRI's first hardware products to be marketed, are the result of research to find technological solutions to the problems of knowing the time period when temperature and pressure changes occur in light water reactors. The hydraulic pressure-sensor device is a portable unit that can conveniently test equipment in place. Utilities can obtain detailed information from EPRI's project report to construct their own. The loop current step response (LCSR), measuring resistance temperature, is also a compact system suitable for in-plant testing

  9. EPRI MOV performance prediction program

    International Nuclear Information System (INIS)

    Hosler, J.F.; Damerell, P.S.; Eidson, M.G.; Estep, N.E.

    1994-01-01

    An overview of the EPRI Motor-Operated Valve (MOV) Performance Prediction Program is presented. The objectives of this Program are to better understand the factors affecting the performance of MOVs and to develop and validate methodologies to predict MOV performance. The Program involves valve analytical modeling, separate-effects testing to refine the models, and flow-loop and in-plant MOV testing to provide a basis for model validation. The ultimate product of the Program is an MOV Performance Prediction Methodology applicable to common gate, globe, and butterfly valves. The methodology predicts thrust and torque requirements at design-basis flow and differential pressure conditions, assesses the potential for gate valve internal damage, and provides test methods to quantify potential for gate valve internal damage, and provides test methods to quantify potential variations in actuator output thrust with loading condition. Key findings and their potential impact on MOV design and engineering application are summarized

  10. Review of EPRI Nuclear Human Factors Program

    International Nuclear Information System (INIS)

    Hanes, L.F.; O'Brien, J.F.

    1996-01-01

    The Electric Power Research Institute (EPRI) Human Factors Program, which is part of the EPRI Nuclear Power Group, was established in 1975. Over the years, the Program has changed emphasis based on the shifting priorities and needs of the commercial nuclear power industry. The Program has produced many important products that provide significant safety and economic benefits for EPRI member utilities. This presentation will provide a brief history of the Program and products. Current projects and products that have been released recently will be mentioned

  11. EPRI research on soil-structure interaction

    International Nuclear Information System (INIS)

    Tang, H.T.

    1986-01-01

    The paper briefly discusses the background of soil-structure interaction research and identifies the nuclear industry's need for a realistic, experimentally qualified soil-structure interaction analysis methodology for nuclear power plant design to reduce excessive conservatism and stabilize the licensing process. EPRI research and joint research efforts between EPRI and Niagara Mohawk Power Corporation, Taiwan Power Company, and the Japanese Century Research Institute for Electric Power Industry are outlined. As a result of these and other research efforts, improvement in soil-structure interactions methodologies is being realized

  12. Operation of the EPRI Nondestructive Evaluation Center

    International Nuclear Information System (INIS)

    Stone, R.M.; Ammirato, F.V.; Becker, F.L.

    1989-11-01

    This report describes the Electric Power Research Institute (EPRI) funded nondestructive evaluation (NDE) and life assessment project activities carried out at the EPRI NDE Center in 1988. The primary support for this program is provided through contract RP 1570-2 with the EPRI Nuclear Division. Supplementary funding is provided by other contracts with the EPRI Nuclear, Coal Combustion, and Electrical Systems Divisions. The major objective of this program is to provide improved and field-qualified NDE equipment, procedures, and personnel training to the electric utility industry. A second program objective involves the validation, provision, and maintenance of life assessment codes for selected plant components. Significant assistance has been provided to the utility industry under this project in the form of improved, field-ready equipment and procedures; critically needed assessments of inspection method capability; demonstrations of effectiveness of examination methods; rapid response for critical, short-term problems; assistance with selected life assessment computer codes; and training for specific utility industry needs. These efforts have specifically involved heat exchanger, piping, steam turbine, generator, and heavy section problems. Certain components of both nuclear and fossil plants have been addressed. 56 refs., 48 figs., 13 tabs

  13. SAI/EPRI Albedo Information Library

    International Nuclear Information System (INIS)

    Simmons, G.L.

    1979-03-01

    The SAI/EPRI Albedo Information Library (SAIL) is described. This description included the techniques used to develop the data and comparisons with albedo data. Albedo data are presented for Type 04 Concrete and Low Carbon Steel, the most common materials encountered in radiation streaming analysis. Applications of the SAIL data are presented and compared with experimental results

  14. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

    Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

    2011-01-01

    The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

  15. Report of the 1992 EPRI Fusion Panel

    International Nuclear Information System (INIS)

    Hirsch, R.L.; Culler, F.; Hingorani, N.G.; Taylor, J.J.; Schneider, T.R.; Spencer, D.F.

    1992-01-01

    Fusion is one of only a few very long-term (multi-century) options for the central station generation of electric power. As such, an informed awareness of the status of fusion development is important to the electric utilities and to EPRI. In its recent open-quotes National Energy Strategyclose quotes report, the U.S. Department of Energy states that it intends to carry out a goal-oriented fusion development strategy, with the aim of operating a demonstration plant by about 2025 and a commercial power plant by about 2040. Around the time the DOE was preparing this strategy, budget pressures caused them to narrow their civilian development program to the tokamak magnetic confinement concept. A significant research program on inertial confinement fusion is maintained primarily for defense purposes but with possible civilian application also. Many in the utility and engineering communities have raised questions about the suitability of both the tokamak and inertial confinement as commercial power sources, while recognizing their unquestioned pre-eminence in achieving fusion plasma conditions. These questions, coupled with a possible interest in becoming more involved in the development of fusion power, led EPRI senior management to establish a panel of senior executives to consider a wide range of conceivable fusion reactor opportunities. The purposes of the 1992 EPRI Fusion Study were as follows: 1. To evaluate a wide range of fusion concepts from a utility desirability standpoint. 2. To enhance EPRI's perspective in fusion. 3. To provide guidance to DOE on fusion concept characteristics important to utilities. 4. To provide a basis for re-establishing DOE-EPRI communication and cooperation in fusion

  16. Industry upheaval drives changes at EPRI

    International Nuclear Information System (INIS)

    Zink, J.C.

    1996-01-01

    This article describes how the Electric Power Research Institute (EPRI) is rethinking and modifying its program and business relationships with its members to reflect the significant changes occurring in the utility business. They are in the midst of changes as profound as any the (electric utility) industry has ever seen, according to Kurt Yeager, EPRI's new president and CEO. The renewed availability of natural gas for power generation, along with the development of more efficient gas turbines, have been important factors. The ability to better manage the delivery system has contributed to the arguments in favor of increased competition, although the application of the management tools, such as flexible ac transmission systems (FACTS), is not coming as quickly as many had expected. And new digitally controlled electrotechnologies have made electricity a growth business again, creating a third wave of growth driven by technologies that allow more precise and efficient control of industrial processes

  17. Proceedings: 2001 ASME/EPRI Radwaste Workshop

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear utilities continually evaluate methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has increased the emphasis on this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technology and management improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

  18. Proceedings: 2000 ASME/EPRI Radwaste Workshop

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear utilities are continually evaluating methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has added increased emphasis to this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technological and managerial improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

  19. Pressurized thermal shock program sponsored by EPRI

    International Nuclear Information System (INIS)

    Stahlkopf, K.E.

    1983-01-01

    The potential for long term neutron embrittlement of reactor vessels has been recognized for a number of years. Reactor vessel thermal shock is not a new concern, but with a growing number of plants approaching their mid-lives, it is a concern that must be understood and dealt with. Recent attention has focused on the performance of vessels during overcooling transients. This concern was designated as Unresolved Safety Issue A-49 by the Nuclear Regulatory Commission in December 1981. The USNRC staff has identified eight overcooling events of concern in U.S. PWRs. The concern is currently limited to Pressurized Water Reactors. The Electric Power Research Institute (EPRI) has supported research on reactor vessel integrity for a number of years and has supported an extensive effort on reactor vessel pressurized thermal shock (PTS) over the last three years. In addition, EPRI has developed a linked set of computer codes to simulate the pressurized thermal shock transients and assess the integrity of the nuclear reactor vessels for various overcooling transients. This paper focuses on the integrated analysis approach being used by EPRI in performing such analysis. (orig.)

  20. EPRI root cause advisory workstation 'ERCAWS'

    International Nuclear Information System (INIS)

    Singh, A.; Chiu, C.; Hackman, R.B.

    1993-01-01

    EPRI and its contractor FPI International are developing Personal Computer (PC), Microsoft Windows based software to assist power plant engineers and maintenance personnel to diagnose and correct root causes of power plant equipment failures. The EPRI Root Cause Advisory Workstation (ERCAWS) is easy to use and able to handle knowledge bases and diagnostic tools for an unlimited number of equipment types. Knowledge base data is based on power industry experience and root cause analysis from many sources - Utilities, EPRI, US government, FPI, and International sources. The approach used in the knowledge base handling portion of the software is case-study oriented with the engineer selecting the equipment type and symptom identification using a combination of text, photographs, and animation, displaying dynamic physical phenomena involved. Root causes, means for confirmation, and corrective actions are then suggested in a simple, user friendly format. The first knowledge base being released with ERCAWS is the Valve Diagnostic Advisor module; covering six common valve types and some motor operator and air operator items. More modules are under development with Heat Exchanger, Bolt, and Piping modules currently in the beta testing stage. A wide variety of diagnostic tools are easily incorporated into ERCAWS and accessed through the main screen interface. ERCAWS is designed to fulfill the industry need for user-friendly tools to perform power plant equipment failure root cause analysis, and training for engineering, operations and maintenance personnel on how components can fail and how to reduce failure rates or prevent failure from occurring. In addition, ERCAWS serves as a vehicle to capture lessons learned from industry wide experience. (author)

  1. EPRI program in water reactor safety

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Gelhaus, F.; Gopalakrishnan, A.

    1975-01-01

    The basis for EPRI's water reactor safety program is twofold. First is compilation and development of fundamental background data necessary for quantified light-water reactor (LWR) safety assurance appraisals. Second is development of realistic and experimentally bench-marked analytical procedures. The results are expected either to confirm the safety margins in current operating parameters, and to identify overly conservative controls, or, in some cases, to provide a basis for improvements to further minimize uncertainties in expected performance. Achievement of these objectives requires the synthesis of related current and projected experimental-analytical projects toward establishment of an experimentally-based analysis for the assurance of safety for LWRs

  2. EPRI's pumped storage planning and evaluation guide

    International Nuclear Information System (INIS)

    Chen, H.H.

    1991-01-01

    EPRI's Hydropower Pumped Storage Planning and Evaluation Guide was published in 1990. The Guide provides step-by-step procedures to: evaluate pumped-storage operation in a utility system, establish site development concept, estimate capital cost, and conduct economic analysis. The Guide provides a floppy diskette containing a production costing model simulating the chronologic operation of pumped storage in a generating system. It provides a series of estimating curves for the preparation of capital cost estimates. The paper presents how the Guide was organized and prepared, and highlights its contents

  3. USDOE/EPRI BIOMASS COFIRING COOPERATIVE AGREEMENT

    International Nuclear Information System (INIS)

    D. Tillman; E. Hughes

    1999-01-01

    During the period of April 1, 1999 through June 30, 1999, wood cofiring testing at both Seward Generating Station of GPU Genco and Bailly Generating Station of Northern Indiana Public Service Company provided the focus for all activities. In both cases, the testing was directed at the impacts of cofiring on efficiency, operability, and NO(sub x) emissions. This report summarizes the activities during the second calendar quarter in 1999 of the USDOE/EPRI Biomass Cofiring Cooperative Agreement. It focuses upon reporting the results of testing activities at both generating stations

  4. Overview of EPRI's human factors research program

    International Nuclear Information System (INIS)

    O'Brien, J.F.; Parris, H.L.

    1981-01-01

    The human factors engineering program in the Nuclear Power Division, EPRI is dedicated to the resolution of man-machine interface problems specific to the nuclear power industry. Particularly emphasis is placed on the capabilities and limitations of the people who operate and maintain the system, the tasks they must perform, and what they need to accomplish those tasks. Six human factors R and D projects are being conducted at the present time. In addition, technical consultation is being furnished to a study area, operator aids, being funded by another program area outside the human factors program area. All of these activities are summarized

  5. USDOE/EPRI BIOMASS COFIRING COOPERATIVE AGREEMENT

    Energy Technology Data Exchange (ETDEWEB)

    D. Tillman; E. Hughes

    1999-04-01

    During the period of January 1, 1999 through March 31, 1999, construction was performed in support of two major demonstrations. Major progress was made on several projects including cofiring at Seward (GPU Genco), and Bailly (NIPSCO). Most of the work was focused on construction and system commissioning activities at the Seward and Bailly Generating Stations. Additionally, petroleum coke cofiring testing was completed at the Bailly Generating Station. This report summarizes the activities during the first calendar quarter in 1999--the fourth contract quarter in 1998--of the USDOE/EPRI Biomass Cofiring Cooperative Agreement. It focuses upon reporting the results of construction activities and related events.

  6. Operator support systems activities at EPRI

    International Nuclear Information System (INIS)

    Naser, J.A.

    1993-01-01

    The integration of operator support systems supports the nuclear power plant goals of improved availability and reliability, enhanced safety, reduced operations and maintenance costs, and improved productivity. Two major aspects which supports this integration are discussed in this paper. The first is the plant communications and computing architecture which provides the infrastructure that allows the integration to exist in a easy to implement manner. Open systems concepts are utilized to guarantee interoperability of systems and interchangeability of equipment. The second is the EPRI Plant-Window System which supplies the interface between the human and the plant systems. It implements common human-machine interfaces amongst systems and supports the implementation of diagnostic and decision aids. Work in both of these areas is being done as part of the EPRI Instrumentation and Control Upgrade Program. A number of operator support systems have been developed and are in various stages of implementation, testing and utilization. Two of these, the RWCU and the EOPTS, are described here. 5 refs, 14 figs

  7. Training activities at the EPRI NDE Center

    International Nuclear Information System (INIS)

    Pherigo, G.

    1986-01-01

    The Electric Power Research Institute (EPRI), through its Nondestructive Examination (NDE) Center in Charlotte, North Carolina, has identified two specific categories of NDE training to best serve the industry's need for enhanced personnel qualification programs. These categories include in-service inspection (ISI) training and technical skills training. The ISI training provides operator training in new NDE technology areas that are ready for field application. The technical skills training is developed as part of a long-range plan to support all basic NDE methods typical to the electric power industry. The need for specific training and better documentation of NDE personnel qualifications is becoming more evident. ASME Section XI requirements for the qualification and certification of visual examiners and the recognition by the US Nuclear Regulatory Commission (NRC) of the importance of the ultrasonic (UT) operator in finding intergranular stress corrosion cracking (IGSCC) are two of the major issues being addressed by the training task of the EPRI NDE Center. The overall intent of the center's training is to meet the most critical utility needs with quality training that can be used by the trainee's employer as a part of their certification of that individual. To do this, the center has organized and activated a carefully maintained documentation and records systems built around the continuing education unit

  8. The EPRI NDE center after five years

    International Nuclear Information System (INIS)

    Dau, G.J.; Nemzek, T.A.

    1985-01-01

    In 1979, the Electric Power Research Institute (EPRI) established a Nondestructive Evaluation (NDE) Center. The purpose of the Center is to provide the electric utility industry with a dedicated NDE development and field-use-qualification capability. Later, the scope of activities at the NDE Center was expanded. Beginning in 1980, the BWR Owners Group (IGSCC) provided funding necessary to operate the BWR Pipe Remedy Demonstration and Training Facility. In 1984, the Maintenance Equipment Applications Center was established by EPRI. Both functions are co-located within the NDE Center. All three functions share common objectives of providing the electric utility industry with a capability dedicated to assuring reduction to practice of new or improved technology, proof testing, qualification for field use, and obtaining code and regulatory acceptance of qualified methods and training. The purpose of this paper is to describe typical activities of the Center and some of the benefits that have accrued. The next section describes the Center organization, operation, and facility, while the remaining sections discuss the technology transfer thrust and benefits

  9. EPRI's zebra mussel monitoring and control guidelines

    International Nuclear Information System (INIS)

    Mussalli, Y.G.; Armor, A.; Edwards, R.; Mattice, J.; Miller, M.; Nott, B.; Tsou, J.L.

    1992-01-01

    The Electric Power Research Institute (EPRI) Zebra Mussel Monitoring and Control Guidelines is a comprehensive compilation of US and European practices. The zebra mussel has infested all the Great Lakes and is positioned to spread to the adjoining river basins. The impact of the zebra mussel on power plants is as a biofouler clogging water systems and heat exchangers. The EPRI guidelines discuss the distribution of the zebra mussel in the US, identification of the zebra mussel, potential threats to power plants, and methods to initiate the monitoring and control program. Both preventive and corrective measures are presented. Preventive measures include various monitoring methods to initiate control techniques. The control techniques include both chemical and nonchemical together with combining techniques. Corrective methods include operational considerations, chemical cleaning, and mechanical/physical cleaning. It may also be possible to incorporate design changes, such as open to closed-loop backfit, backflushing, or pretreatment for closed systems. Table 1 shows a matrix of the monitoring methods. Table 2 presents a control matrix related to nuclear, fossil, and hydro raw water systems. Table 3 is a summary of the applicability of treatments to the various raw water systems. Appendixes are included that contain specifications to aid utilities in implementing several of the control technologies

  10. Proceedings of the Third EPRI Phased Array Ultrasound Seminar

    International Nuclear Information System (INIS)

    2003-01-01

    Phased array technology for ultrasonic examination is providing innovative solutions for nuclear in-service examination applications. EPRI has been a prime mover in the development and deployment of phased array ultrasound applications in the domestic nuclear market over the past decade. As part of this strategic effort, EPRI has hosted a series of seminars on phased array technology and its applications

  11. Concrete containment integrity program at EPRI

    International Nuclear Information System (INIS)

    Winkleblack, R.K.; Tang, Y.K.

    1984-01-01

    Many in the nuclear power plant business believe that the catastrophic failure mode for reactor containment structures is unrealistic. One of the goals of the EPRI containment integrity program is to demonstrate that this is true. The objective of the program is to provide the utility industry with an experimental data base and a test-validated analytical method for realistically evaluating the actual over-pressure capability of concrete containment buildings and to predict leakage behavior if higher pressures were to occur. The ultimate goal of this research effort is to characterize the containment leakage mode and rate as a function of internal pressure and time so that the risk can be realistically assessed for hypothetical degraded core accidents. Progress in the first and second phases of the three-phase analytical and testing efforts is discussed

  12. Evaluation of leak rate by EPRI code

    International Nuclear Information System (INIS)

    Isozaki, Toshikuni; Hashiguchi, Issei; Kato, Kiyoshi; Miyazono, Shohachiro

    1987-08-01

    From 1987, a research on the leak rate from a cracked pipe under BWR or PWR operating condition is going to be carried out at the authors' laboratory. This report describes the computed results by EPRI's leak rate code which was mounted on JAERI FACOM-M380 machine. Henry's critical flow model is used in this program. For the planning of an experimental research, the leak rate from a crack under BWR or PWR operating condition is computed, varying a crack length 2c, crack opening diameter COD and pipe diameter. The COD value under which the minimum detectable leak rate of 5 gpm is given is 0.22 mm or 0.21 mm under the BWR or PWR condition with 2c = 100 mm and 16B pipe geometry. The entire lists are shown in the appendix. (author)

  13. EPRI PWR primary water chemistry guidelines revision

    International Nuclear Information System (INIS)

    McElrath, Joel; Fruzzetti, Keith

    2014-01-01

    EPRI periodically updates the PWR Primary Water Chemistry Guidelines as new information becomes available and as required by NEI 97-06 (Steam Generator Program Guidelines) and NEI 03-08 (Guideline for the Management of Materials Issues). The last revision of the PWR water chemistry guidelines identified an optimum primary water chemistry program based on then-current understanding of research and field information. This new revision provides further details with regard to primary water stress corrosion cracking (PWSCC), fuel integrity, and shutdown dose rates. A committee of industry experts, including utility specialists, nuclear steam supply system (NSSS) and fuel vendor representatives, Institute of Nuclear Power Operations (INPO) representatives, consultants, and EPRI staff collaborated in reviewing the available data on primary water chemistry, reactor water coolant system materials issues, fuel integrity and performance issues, and radiation dose rate issues. From the data, the committee updated the water chemistry guidelines that all PWR nuclear plants should adopt. The committee revised guidance with regard to optimization to reflect industry experience gained since the publication of Revision 6. Among the changes, the technical information regarding the impact of zinc injection on PWSCC initiation and dose rate reduction has been updated to reflect the current level of knowledge within the industry. Similarly, industry experience with elevated lithium concentrations with regard to fuel performance and radiation dose rates has been updated to reflect data collected to date. Recognizing that each nuclear plant owner has a unique set of design, operating, and corporate concerns, the guidelines committee has retained a method for plant-specific optimization. Revision 7 of the Pressurized Water Reactor Primary Water Chemistry Guidelines provides guidance for PWR primary systems of all manufacture and design. The guidelines continue to emphasize plant

  14. A review of the EPRI hydroloads program

    International Nuclear Information System (INIS)

    Oehlberg, R.N.

    1983-01-01

    For a large, rapid, close-to-the-vessel break of a pressurized water reactor (PWR) inlet pipe, hydrodynamic loads in the primary system were speculated by the U.S. Nuclear Regulatory Commission (NRC) to have licensing significance during the subcooled portions of a hypothetical loss-of-coolant accident (LOCA). The analytical methods which are used to analyze hydroloads for licensing submittals rely on one-dimensional modeling techniques and require significant engineering judgement to couple the internal structures, such as the core support barrel, and the adjacent fluid. These analysis methods are expected to overestimate the acceleration and impact forces on primary system components. Methodology enhancements were made in a stepwise fashion, (1D, 2D, then 3D). The modified computer programs were then assessed by comparing calculated results with analytical solutions and experimental data. The calculated results compared favorably with the analytical and experimental results. Furthermore, the calculation of HDR tests V31.3 and V32 proved to be valuable for understanding the fundamental mechanics of fluid-structure interaction in large-scale systems during subcooled blowdown. The final stage of the EPRI program was to apply the coupled, 3D fluid-structure interaction methodology to the calculation of the hydrodynamic loads in a modified HDR model having a dynamic axially distributed core. EPRI's fluid-structure interaction program has resulted in state-of-the-art technology which can be applied to both nuclear licensing and engineering problems without the significant engineering judgment required of less sophisticated methods. Realistics loads can be obtained to quantify conservatisms in current licensing approaches. (orig./GL)

  15. EPRI depletion benchmark calculations using PARAGON

    International Nuclear Information System (INIS)

    Kucukboyaci, Vefa N.

    2015-01-01

    Highlights: • PARAGON depletion calculations are benchmarked against the EPRI reactivity decrement experiments. • Benchmarks cover a wide range of enrichments, burnups, cooling times, and burnable absorbers, and different depletion and storage conditions. • Results from PARAGON-SCALE scheme are more conservative relative to the benchmark data. • ENDF/B-VII based data reduces the excess conservatism and brings the predictions closer to benchmark reactivity decrement values. - Abstract: In order to conservatively apply burnup credit in spent fuel pool criticality analyses, code validation for both fresh and used fuel is required. Fresh fuel validation is typically done by modeling experiments from the “International Handbook.” A depletion validation can determine a bias and bias uncertainty for the worth of the isotopes not found in the fresh fuel critical experiments. Westinghouse’s burnup credit methodology uses PARAGON™ (Westinghouse 2-D lattice physics code) and its 70-group cross-section library, which have been benchmarked, qualified, and licensed both as a standalone transport code and as a nuclear data source for core design simulations. A bias and bias uncertainty for the worth of depletion isotopes, however, are not available for PARAGON. Instead, the 5% decrement approach for depletion uncertainty is used, as set forth in the Kopp memo. Recently, EPRI developed a set of benchmarks based on a large set of power distribution measurements to ascertain reactivity biases. The depletion reactivity has been used to create 11 benchmark cases for 10, 20, 30, 40, 50, and 60 GWd/MTU and 3 cooling times 100 h, 5 years, and 15 years. These benchmark cases are analyzed with PARAGON and the SCALE package and sensitivity studies are performed using different cross-section libraries based on ENDF/B-VI.3 and ENDF/B-VII data to assess that the 5% decrement approach is conservative for determining depletion uncertainty

  16. EPRI releases strategic plan for hydroelectric R and D

    International Nuclear Information System (INIS)

    Fickett, A.P.

    1993-01-01

    The Electric Power Research Institute has published a report identifying important research needs and issues in the hydroelectric industry. The report is based on results from a survey of representatives of the 1992 North American hydroelectric community. EPRI conducted the survey to expand upon recommendations of the North American Hydroelectric R ampersand D Forum and to develop EPRI's agenda. The report, an EPRI Strategy for Hydropower Research and Development: Rethinking our Water Resource Management Strategies, outlines an agenda for improving the use of water resources and expanding hydroelectric production at existing dams. It also proposes a new, expanded EPRI strategy within the context of the future energy needs of the US and the North American hydro research agenda

  17. DOE-EPRI On-Line Monitoring Implementation Guidelines

    International Nuclear Information System (INIS)

    E. Davis, R. Bickford

    2003-01-01

    Industry and EPRI experience at several plants has shown on-line monitoring to be very effective in identifying out-of-calibration instrument channels or indications of equipment-degradation problems. The EPRI implementation project for on-line monitoring has demonstrated the feasibility of on-line monitoring at several participating nuclear plants. The results have been very encouraging, and substantial progress is anticipated in the coming years

  18. Progress on EPRI electrical equipment qualification research

    International Nuclear Information System (INIS)

    Sliter, G.E.

    1983-01-01

    The objective of EPRI's electrical equipment qualification research program is to provide technical assistance to utilities in meeting nuclear plant safety requirements in a manner consistent with the state of the art. This paper reports progress on several research projects including: radiation effects studies, which compile data on degradation of organic materials in electrical equipment exposed to operational and accident radiation doses; the Equipment Qualification Data Bank, which is a remotely accessible computer system for disseminating qualification information on in-plant equipment, seismic data, and materials data; an aging/seismic correlation program, which is providing test data showing that, in many cases, age degradation has a negligibly small effect on the performance of electrical components under seismic excitation; a review of condition monitoring techniques, which has identified surveillance methods for measuring key performance parameters that have the potential for predicting remaining equipment life; and large-scale hydrogen burn equipment response tests, which are providing data to assess the ability of equipment to remain functional during and after hydrogen burning in postulated degraded core accidents

  19. USDOE/EPRI BIOMASS COFIRING COOPERATIVE AGREEMENT

    International Nuclear Information System (INIS)

    D. Tillman; E. Hughes

    1999-01-01

    The Eleventh Quarter of the USDOE-EPRI contract, April 1, 1999 through June 30, 1999, was characterized by extensive testing at the Seward cofiring demonstration of GPU Genco and the Bailly Unit No.7 demonstration of NIPSCO. Technical work that proceeded during the eleventh quarter of the contract included the following: Testing at up to(approx)15 percent cofiring on a mass basis ((approx)7 percent cofiring on a Btu basis) at the Seward Generating Station No.12 boiler, focusing upon the operability of the separate injection system and the combustion/emission formation characteristics of the cofiring process; and Testing at up to(approx)10 percent cofiring of waste wood on a mass basis ((approx)5 percent cofiring on a Btu basis) at the Bailly Generating Station No.7 boiler, focusing upon the impacts of urban wood waste blended with a mixture of eastern high sulfur coal and western low sulfur coal Both tests demonstrated the following general, and expected, results from cofiring at these locations: (1) Cofiring did not impact boiler capacity; (2) Cofiring did cause a modest reduction in boiler efficiency; (3) Cofiring did reduce NOx emissions; (4) Cofiring did reduce fossil CO2 emissions; and (5) Other impacts of cofiring were modest

  20. EDF/EPRI collaborative program on operator reliability experiments

    International Nuclear Information System (INIS)

    Villemeur, A.; Meslin, T.; Mosneron, F.; Worledge, D.H.; Joksimovich, V.; Spurgin, A.J.

    1988-01-01

    Electricite de France (EDF) and Electric Power Research Institute (EPRI) have been involved in human reliability studies over the last few years, in the context of improvements in human reliability assessment (HRA) methodologies, and have been following a systematic process since 1982 which consists of addressing the following five ingredients: - First, classify human interactions into a limited number of classes. - Second, introduce an acceptable framework to organize the application of HRA to PRA studies. - Third, select approach(es) to quantification. - Fourth, test promising models. - Fifth, establish an appropriate data base for tested model(s) with regard to specific applications. EPRI has just recently completed Phase I of the fourth topic. This primarily focused on testing the fundamental hypotheses behing the human cognitive reliability (HCR) correlation, using power plant simulators. EDF has been carrying out simulator studies since 1980, both for man-machine interface validation and HRA data collection. This background of experience provided a stepping stone for the EPRI project. On the other hand, before 1986, EDF had mainly been concentrating on getting qualitative insights from the tests and lacked experience in quantitative analysis and modeling, while EPRI had made advances in this latter area. Before the EPRI Operator Reliability Experiments (ORE) project was initiated, it was abundantly clear to EPRI and EDF that cooperation between the two could be useful and that both parties could gain from the cooperation

  1. EPRI's POWERCOACH trademark software development project

    International Nuclear Information System (INIS)

    Rost, S.; Leu, Kehshiou

    1993-01-01

    Today's complex bulk power market accounts for an estimated $35 billion in transactions a year, significantly more than a decade ago. With the increased levels of non-utility generation and changing strategies in the utility industry, it is anticipated that the trend toward rapid growth in the bulk power market will continue. This market has evolved from an ad hoc residual market to one that in some respects stands at par with the retail market in the plans of many utilities. The bulk power market is not based on the obligation to serve to the same extent as retail markets. Utility participation in this market is therefore purely voluntary. This freedom of action or inaction in the bulk power market actually renders corporate decision-making, investment related or operational, more complicated in many respects than in retail markets. Examples of the burgeoning uncertainties affecting the bulk power market include the rapid expansion of transactions undertaken through power pools, and the impact on utility planning and operations brought about by the abundance and price attractiveness of power available for flexible periods. These uncertainties present an ideal opportunity to employ state-of-the-art analytical models to facilitate the effective use of utility assets to foster the efficient functioning of the entire bulk power market. This paper will focus on the POWERCOACH methodology for short-term bulk power transaction analysis under conditions of uncertainty. In August 1992, UPMP began a seventeen month project to convert POWERCOACH from a methodology to a fully functional, commercial software package. UPMP is developing the POWERCOACH software with the extensive, direct involvement of thirty EPRI member utilities. A synopsis of POWERCOACH is presented

  2. EPRI/DOE nuclear plant life extension overview

    International Nuclear Information System (INIS)

    Carey, J.J.; Lapides, M.E.; Harrison, D.; Ducharme, A.

    1987-01-01

    Recognizing the major investment in current U.S. nuclear capacity and the excellent prospects that these units have a useful life substantially in excess of their 40 year license term, EPRI and DOE have jointly undertaken a comprehensive, multiyear, nuclear plant life extension program. The program, which has its antecedents in EPRI studies of 1978-9, aims to support U.S. utilities, first in verifying the requirements of extended operation and then in implementing a plan for achieving extended service and license renewal. The effort, begun in 1985, has already yielded numerous benefits and is expected to further aid in improving near-term performance of nuclear units. A utility LWR Plant Life Extension Committee has been established to provide overview and guidance to the DOE/EPRI research and development activities and also to develop and integrate utility responses to licensing and codes and standards issues. Pilot study projects, performed by Virginia Power and Northern States Power, were the initial EPRI/DOE focus. This base has gradually expanded to incorporate other utilities and generating units, as well as a broad base of technology support. The latter includes: a) economic and financial analysis methods applicable at the unit, region and national level, b) long-term materials deterioration analysis and sampling, c) component life prediction methods and d) refurbishment and repair evaluations. This paper presents the history and status of the overall EPRI/DOE program

  3. EPRI BWR Water Chemistry Guidelines Revision

    International Nuclear Information System (INIS)

    Garcia, Susan E.; Giannelli, Joseph F.

    2014-01-01

    BWRVIP-190: BWR Water Chemistry Guidelines – 2008 Revision has been revised. The revision committee consisted of U.S. and non-U.S. utilities (members of the BWR Vessel and Internals Protection (BWRVIP) Mitigation Committee), reactor system manufacturers, fuel suppliers, and EPRI and industry experts. The revised document, BWRVIP-190 Revision 1, was completely reformatted into two volumes, with a simplified presentation of water chemistry control, diagnostic and good practice parameters in Volume 1 and the technical bases in Volume 2, to facilitate use. The revision was developed in parallel and in coordination with preparation of the Fuel Reliability Guidelines Revision 1: BWR Fuel Cladding Crud and Corrosion. Guidance is included for plants operating under normal water chemistry (NWC), moderate hydrogen water chemistry (HWC-M), and noble metal application (GE-Hitachi NobleChem™) plus hydrogen injection. Volume 1 includes significant changes to BWR feedwater and reactor water chemistry control parameters to provide increased assurance of intergranular stress corrosion cracking (IGSCC) mitigation of reactor materials and fuel reliability during all plant conditions, including cold shutdown (≤200°F (93°C)), startup/hot standby (>200°F (93°C) and ≤ 10%) and power operation (>10% power). Action Level values for chloride and sulfate have been tightened to minimize environmentally assisted cracking (EAC) of all wetted surfaces, including those not protected by hydrogen injection, with or without noble metals. Chemistry control guidance has been enhanced to minimize shutdown radiation fields by clarifying targets for depleted zinc oxide (DZO) injection while meeting requirements for fuel reliability. Improved tabular presentations of parameter values explicitly indicate levels at which actions are to be taken and required sampling frequencies. Volume 2 provides the technical bases for BWR water chemistry control for control of EAC, flow accelerated corrosion

  4. DOE-EPRI distributed wind Turbine Verification Program (TVP III)

    Energy Technology Data Exchange (ETDEWEB)

    McGowin, C.; DeMeo, E. [Electric Power Research Institute, Palo Alto, CA (United States); Calvert, S. [Dept. of Energy, Washington, DC (United States)] [and others

    1997-12-31

    In 1992, the Electric Power Research Institute (EPRI) and the U.S. Department of Energy (DOE) initiated the Utility Wind Turbine Verification Program (TVP). The goal of the program is to evaluate prototype advanced wind turbines at several sites developed by U.S. electric utility companies. Two six MW wind projects have been installed under the TVP program by Central and South West Services in Fort Davis, Texas and Green Mountain Power Corporation in Searsburg, Vermont. In early 1997, DOE and EPRI selected five more utility projects to evaluate distributed wind generation using smaller {open_quotes}clusters{close_quotes} of wind turbines connected directly to the electricity distribution system. This paper presents an overview of the objectives, scope, and status of the EPRI-DOE TVP program and the existing and planned TVP projects.

  5. EPRI-USDOE COOPERATIVE AGREEMENT: COFIRING BIOMASS WITH COAL; FINAL

    International Nuclear Information System (INIS)

    David A. Tillman

    2001-01-01

    The entire Electric Power Research Institute (EPRI) cofiring program has been in existence of some 9 years. This report presents a summary of the major elements of that program, focusing upon the following questions: (1) In pursuit of increased use of renewable energy in the US economy, why was electricity generation considered the most promising target, and why was cofiring pursued as the most effective near-term technology to use in broadening the use of biomass within the electricity generating arena? (2) What were the unique accomplishments of EPRI before the development of the Cooperative Agreement, which made developing the partnership with EPRI a highly cost-effective approach for USDOE? (3) What were the key accomplishments of the Cooperative Agreement in the development and execution of test and demonstration programs-accomplishments which significantly furthered the process of commercializing cofiring?

  6. EPRI-USDOE COOPERATIVE AGREEMENT: COFIRING BIOMASS WITH COAL

    Energy Technology Data Exchange (ETDEWEB)

    David A. Tillman

    2001-09-01

    The entire Electric Power Research Institute (EPRI) cofiring program has been in existence of some 9 years. This report presents a summary of the major elements of that program, focusing upon the following questions: (1) In pursuit of increased use of renewable energy in the US economy, why was electricity generation considered the most promising target, and why was cofiring pursued as the most effective near-term technology to use in broadening the use of biomass within the electricity generating arena? (2) What were the unique accomplishments of EPRI before the development of the Cooperative Agreement, which made developing the partnership with EPRI a highly cost-effective approach for USDOE? (3) What were the key accomplishments of the Cooperative Agreement in the development and execution of test and demonstration programs-accomplishments which significantly furthered the process of commercializing cofiring?

  7. Operation of the EPRI nondestructive evaluation center: 1985 annual report

    International Nuclear Information System (INIS)

    Nemzek, T.A.; Stone, R.M.; Ammirato, F.V.; Becker, F.L.; Krzywosz, K.; Pherigo, G.L.; Wilson, G.H. III.

    1986-08-01

    This report describes the Electric Power Research Institute (EPRI) Nuclear Division funded nondestructive evaluation (NDE) project activities carried out at the EPRI NDE Center in 1985. The continuing objective of the Center is transfer of research and development results funded by EPRI and other related projects to useful field application. This is being accomplished by qualification and refinement of equipment and techniques, training under realistic conditions, and encouragement of greater involvement of the academic community in NDE education. Significant assistance has been provided to the nuclear utility industry under this project in the form of improved, field-ready equipment and procedures; critically needed assessments of inspection method capability; demonstrations of effectiveness of examination methods; rapid response for critical, short-term problems; and training for specific utility industry needs. This effort has specifically addressed steam generator, piping, steam turbine, and heavy section inspection problems

  8. EPRI'S low-level waste management R ampersand D program

    International Nuclear Information System (INIS)

    Hornibrook, C.

    1997-01-01

    The immediate challenges facing every organization today are to improve its productivity and increase customer satisfaction. The Electric Power Research Institute (EPRI) responded to this challenge by broadening the scope of its low-level waste (LLW) management program. EPRI offered utilities on-site assistance in evaluating and optimizing their liquid- and solid-waste management programs. The goal is to identify open-quotes cheaper, better, and easierclose quotes solutions, which are documented in a series of reports. These provide step-by-step evaluation processes and straightforward implementation methods. Utility professionals are provided with the necessary technical information and justification for informed waste management decisions. The resulting average annual savings is consistently in excess of $700,000 per facility. The program continues to grow and serves as a model for a number of existing and emerging EPRI programs

  9. EPRI activities in support of new nuclear plant deployment

    International Nuclear Information System (INIS)

    Mulford, T.

    2007-01-01

    This paper describes the challenges to new plant deployment in the United States and discusses the role of the Electric Power Research Institute (EPRI) in efforts to address these challenges. These technical challenges include completing remaining design work, licensing review, and standardization required to ensure that new LWRs are a competitive near-term option. The costs for construction, licensing, and operation of new nuclear plants are uncertain and this uncertainty, along with concerns about construction schedule form a financial challenge to investment. Because the new process for licensing nuclear power plants in the United States has not been fully demonstrated, regulatory concerns also serve as a challenge to near-term commitments to build new nuclear power plants. EPRI is working in concert with utilities and vendors to upgrade certified LWR designs and obtain certification of new LWR designs. Specific technical areas being addressed by EPRI projects include updating the Utility Requirements Document (URD), seismic resolution, radiation protection, radioactive waste management, the development of utility planning tools, and staff optimization. EPRI's key on-going project, the New Plant Deployment Program Model (NPDPM), is designed to help prospective and actual new nuclear plant managers and staff to identify schedule and resource requirements from the point of the decision to build a plant through to the start of commercial operation. This model will describe and organize key activities and assess schedule, activity duration, logic relationships and critical path analysis. The new plant licensing and deployment process is a five to ten year activity representing a significant financial investment that requires coordination with federal and state regulators, designers, architect engineers, and numerous other contributing organizations. Planning is crucial to schedule and budget control. EPRI has also supported projects to quantify the environmental

  10. Assessing coal combustion and sourcing strategies using EPRI`s CQIM{sup {trademark}}

    Energy Technology Data Exchange (ETDEWEB)

    Stallard, G.S.; Jennison, K.D. [Black & Veatch, Overland Park, KS (United States)

    1995-12-01

    Understanding the cost and performance issues associated with coal quality or, more precisely, specific constituents within coal is an important ingredient of engineering and planning processes. Such processes can cover a wide range of activities, including how to most cost-effectively burn local coal supplies, how to identify what technologies or designs should be employed for new facilities, and how to identify potentially viable {open_quotes}new{close_quotes} coal supplies. Selection of coals, coal blends, or coal benefication processes is a complex problem. Similarly, it is difficult for industry participants (ministries, regulators, distribution companies, etc.) To correlate fuel selection strategies to overall power system performance costs. The underlying need to understand coal quality impacts on the financial efficiency of a plant is increasingly important in light of economic and environmental pressures faced by today`s power industry. The Coal Quality Impact Model (CQIM{reg_sign}) offers an ideal platform for understanding and evaluating coal quality impacts. Developed by Black & Veatch for the electric Power Research Institute (EPRI), CQIM is a computer {open_quotes}tool{close_quotes} that is dedicated to maintaining state-of-the-art status by continually incorporating the latest technologies or modeling techniques as they become available. By taking advantage of research efforts and a sound engineering modeling approach, the CQIM is capable of predicting plant-wide performance impacts and translating them into costs.

  11. An EPRI methodology for determining and monitoring simulator operating limits

    International Nuclear Information System (INIS)

    Eichelberg, R.; Pellechi, M.; Wolf, B.; Colley, R.

    1989-01-01

    Of paramount concern to nuclear utilities today is whether their plant-referenced simulator(s) comply with ANSI/ANS 3.5-1985. Of special interest is Section 4.3 of the Standard which requires, in part, that a means be provided to alert the instructor when certain parameters approach values indicative of events beyond the implemented model or known plant behavior. EPRI established Research Project 2054-2 to develop a comprehensive plan for determining, monitoring, and implementing simulator operating limits. As part of the project, a survey was conducted to identify the current/anticipated approach each of the sampled utilities was using to meet the requirements of Section 4.3. A preliminary methodology was drafted and host utilities interviewed. The interview process led to redefining the methodology. This paper covers the objectives of the EPRI project, survey responses, overview of the methodology, resource requirements and conclusions

  12. EPRI research on component aging and nuclear plant life extension

    International Nuclear Information System (INIS)

    Sliter, G.E.; Carey, J.J.

    1985-01-01

    This paper first describes several research efforts sponsored by the Electric Power Research Institute (EPRI) that examine the aging degradation of organic materials and the nuclear plant equipment in which they appear. This research includes a compendium of material properties characterizing the effects of thermal and radiation aging, shake table testing to evaluate the effects of aging on the seismic performance of electrical components, and a review of condition monitoring techniques applicable to electrical equipment. Also described is a long-term investigation of natural versus artificial aging using reactor buildings as test beds. The paper then describes how the equipment aging research fits into a broad-scoped EPRI program on nuclear plant life extension. The objective of this program is to provide required information, technology, and guidelines to enable utilities to significantly extend operating life beyond the current 40-year licensed term

  13. EPRI spearheads generic PM recommendations for infrastructure equipment

    International Nuclear Information System (INIS)

    Worledge, David H.; Hinchcliffe, Glenn R.; Benak, Mark S.; Bridges, Martin

    2007-01-01

    All companies have at their core a vast amount of similar equipment that would benefit from solid preventive maintenance (PM) recommendations that are generic and easily adapted to meet operational conditions. The re-emergence of PM optimization methods like Reliability Centered Maintenance, further illustrates that companies in all industries recognize the positive influence that a well-focused maintenance program has on the corporate bottom line. The Electric Power Research Institute (EPRI) has long been a leader in providing universally adaptable maintenance solutions to meet the evolving needs of its membership. Nearly ten years ago, EPRI began developing the PM Basis Database, a one-of-a-kind repository of PM recommendations for basic infrastructure components (such as pumps, motors, valves, compressors), derived from equipment experts. EPRI has now made available this comprehensive body of knowledge to all industries. This paper will explore the origins and structure of the database, how these generic PM recommendations benefit every industry, and how they may be obtained. (author)

  14. EPRI training to support digital upgrades in nuclear plants

    International Nuclear Information System (INIS)

    Torok, R.; Naser, J.

    2006-01-01

    In response to the growing challenges of obsolescence and rising maintenance costs, utilities are increasingly upgrading or replacing their existing instrumentation and control (I and C) systems and components. In most cases, this involves analog-to-digital or digital-to-newer-digital replacements. However, the use of digital technology often raises new technical and licensing issues, particularly for safety-related applications. Examples include: new failure modes and the potential for common-mode failure of redundant components; electromagnetic compatibility (EMC); potential human-system interface problems; and software verification, validation, and configuration management. Successful implementation, operation and maintenance of digital systems depend to a great extent on having processes in place that are tailored for digital technology. Nuclear plants are therefore updating their processes as they start the migration to digital I and C. For several years, EPRI has been developing guidelines to address the key technical issues and interfacing with the U.S. NRC to ensure the acceptability of the approaches developed. A framework for implementing digital upgrades now exists, but practical experience under the current regulatory environment is sparse. Significant uncertainty exists in regard to both technical and licensing issues. Many utilities still need to prepare their staff and processes to properly handle the new technology. In recent years, this need has been exacerbated by staff reductions, changing job assignments, and declining training budgets. EPRI has responded by developing a training program to help utilities efficiently bring design and licensing engineers up to speed on the latest issues and guidance affecting the implementation of digital upgrades in nuclear plants. This paper describes the key technical issues in the context of the EPRI training program. (authors)

  15. EPRI fuel performance data base: user's manual. Final report

    International Nuclear Information System (INIS)

    Simpson, J.; Lee, S.; Rumble, E.

    1980-10-01

    This user's manual provides instructions for accessing the data in the EPRI fuel performance data base (FPDB) and manipulating that data to solve specific problems that the user wishes to specify. The user interacts with the FPDB through the Relational Information Management System (RIMS) computer program. The structure and format of the FPDB and the general syntax of the data base commands are described. Instructions follow for the use of each command. Appendixes provide more detailed information about the FPDB and its software. The FPDB currently resides on a PRIME-750 computer

  16. EPRI expert system activities for nuclear utility industry application

    International Nuclear Information System (INIS)

    Naser, J.A.

    1990-01-01

    This paper reports on expert systems which have reached a level of maturity where they offer considerable benefits for the nuclear utility industry. The ability of expert systems to enhance expertise makes them an important tool for the nuclear utility industry in the areas of engineering, operations and maintenance. Benefits of expert system applications include comprehensive and consistent reasoning, reduction of time required for activities, retention of human expertise and ability to utilize multiple experts knowledge for an activity. The Electric Power Research Institute (EPRI) has been performing four basic activities to help the nuclear industry take advantage of this expert system technology. The first is the development of expert system building tools which are tailored to nuclear utility industry applications. The second is the development of expert system applications. The third is work in developing a methodology for verification and validation of expert systems. The last is technology transfer activities to help the nuclear utility industry benefit from expert systems. The purpose of this paper is to describe the EPRI activities

  17. NDE training activities at the EPRI NDE Center

    International Nuclear Information System (INIS)

    Pherigo, G.L.

    1988-01-01

    The three principal categories of training activity at the EPRI NDE Center are in-service inspection (ISI) training, technical skills training, and human resource development. The ISI training category, which addresses recently developed NDE technologies that are ready for field application, is divided into two areas. One area provides ongoing training and qualification service to boiling water reactor (BWR) utilities in accordance with the Coordination Plan for NRC/EPRI/BWROG Training and Qualification Activities of NDE Personnel. This plan specifically addresses the detection and sizing of intergranular stress corrosion cracking (IGSCC). The second area includes training activities for other recently developed NDE technologies. Courses in this area include weld overlay examination and advanced eddy current data analysis. The technical skills training is developed and offered to support the basic NDE technology needs of the utilities, with emphasis on utility applications. These programs are provided in direct response to generic or specific needs identified by the utility NDE community. The human resource development activities are focused on long-term utility needs through awareness programs for high schools, technical schools, and universities. These training programs are described

  18. Piping inspection activities at the EPRI NDE Center

    International Nuclear Information System (INIS)

    Ammirato, F.V.

    1988-01-01

    Intergranular stress corrosion cracking (IGSCC) in the primary system of boiling water reactors (BWRs) has been a major reliability issue in recent years. BWR pipe cracking was first reported in 1974 with a low percentage of only small-diameter lines affected. However, with increased plant operating time, the number of reported cracking incidents has risen significantly and in 1982 and 1983 included the large-diameter recirculation lines. With the advent of cracking in large-diameter piping, innovative repair remedies were developed, such as weld overlay for repair (WOR). Although these remedies are effective in extending the service life of piping, they also present challenging NDE problems. The EPRI program for improving piping examination has aimed at systematically resolving the difficulties by optimizing techniques and procedures as well as by developing field-qualified automated examination equipment. The EPRI NDE Center's role has been the evaluation and transfer of the technology necessary to address the current piping examination problems of the nuclear utility industry. These activities normally include the following: technology assessment and improvement; validation through demonstrations and field trials; technology transfer reports, workshops, training, and qualification testing; and acquisition of relevant samples. The activities of the NDE Center are discussed

  19. An Overview of the EPRI PWR Primary Chemistry Program

    International Nuclear Information System (INIS)

    Perkins, David; Fruzzetti, Keith; Haas, Carey; Wells, Dan

    2012-09-01

    Primary chemistry controls continue to evolve, impacting long term equipment reliability goals, optimized core designs, and radiation dose management practices. Chemistry initiatives include increased primary system pH (T) , zinc injection, and optimization of primary system hydrogen concentration. Nevertheless, utilities are faced with ever changing challenges as fuel vendors continue to optimize core power densities coupled with longer operating cycles and material replacement efforts. These challenges must be collaboratively addressed by the plant chemists, engineers, and operators. Operational chemistry has changed dramatically over the years with increased primary pH (T) programs requiring some utilities to operate with up to 6 ppm lithium or slightly higher. Coupled with primary pH (T) program optimization, are ongoing EPRI research efforts attempting to develop an optimized hydrogen control program balancing material issues associated with primary water stress corrosion cracking (PWSCC) crack growth rate against fuel concerns associated with increased hydrogen concentrations. One of the most significant primary chemistry changes that effectively balances the demands of materials, fuels, chemistry and dose management strategies is zinc injection into the primary coolant. Since 1994 when Farley initiated zinc injection, zinc injection has been successfully injected at over 70 pressurized water reactors world-wide. Combining operational chemistry with shutdown chemistry controls provides the plant chemist with a technically based and balanced approach to fuel and material integrity as well as dose management strategies. Shutdown chemistry has continually evolved since the 1970's when the chemist was primarily concerned with fission products. Now the chemist must manage corrosion product release, and support Outage Management and Radiation Protection through the performance of a controlled shutdown. In part, this change was driven as plant materials evolved

  20. Review of EPRI's steam generator R and D program

    International Nuclear Information System (INIS)

    Millett, P.J.; Welty, C.J.

    1998-01-01

    EPRI has carried out an extensive R and D program on SG technology since the mid 1970's. Very early efforts under the auspices of the Steam Generator Owners Group (SGOG) focused on developing remedial actions for the critical SG corrosion issues of denting, wastage and pitting. Fundamental work was also carried out in the development of thermal hydraulic models for vibration and wear, chemical cleaning and tube repair techniques. In the late 1980's and continuing through today, the program has shifted emphasis towards management of steam generator degradation, primarily stress corrosion cracking of the SG tubes on both the primary and secondary sides. The current Steam Generator Management Program (SGMP) carries out R and D in four areas; materials, chemistry, thermal hydraulics and non-destructive testing. The strategic goals of this program and projects put in place to achieve these goals will be reviewed in detail in this paper. (author)

  1. Extended used Fuel Storage: EPRI Perspective and Collaboration Initiatives

    International Nuclear Information System (INIS)

    Kessler, John; Waldrop, Keith

    2014-01-01

    This paper describes three main activities the Electric Power Research Institute (EPRI) is undertaking to establish the technical bases for extended (long-term) storage: the Extended Storage Collaboration Program (ESCP); inspection of stainless steel (SS) used fuel dry storage canisters currently in service; and a proposed data collection from a full-scale, bolted lid, metal cask containing high burnup (>45 GWd/MTU) used fuel (the 'Demo'). ESCP is a voluntary organization focused on information sharing and providing the opportunity for more formal collaboration. The SS canister inspection program involves visual examination, canister surface temperature measurements, and collection of contaminants accumulating on the canister surfaces during operation. The Demo program involves the use of a specially instrumented lid allowing for the introduction of thermocouples inside the loaded cask as was as providing the ability to collect cask cavity gas samples. (authors)

  2. Organics in the power plant cycle. An EPRI perspective

    Energy Technology Data Exchange (ETDEWEB)

    Mathews, James A. [EPRI, Charlotte, NC (United States)

    2008-11-15

    Irrespective of past practices and prejudices, the use of organic treatment chemicals to address new and ongoing concerns in the operation of power plant cycles is increasing. Electric Power Research Institute (EPRI) guidelines currently do not advocate the use of organic additives, citing that these additives should not be needed and that breakdown products pose problems with analytical measurement of cation conductivity and operation of condensate polishers. Some of the concerns about organic treatment are hidden in the association of ''organics'' with naturally occurring organic compounds from contamination sources such as cooling water, lubrication systems, or make-up water treatment and cleaning agents. However, conditions in the 2-phase fluid regions of low pressure heat recovery steam generators (HRSGs), feedwater heaters, the turbine phase transition zone (PTZ), and air-cooled condensers remain problematic and warrant investigation of conditioning with some complex amine type organic treatments. Nuclear plants have employed advanced organic amines such as ethanolamine to address concerns of low pH in condensing steam. Increasing understanding of the formation, morphology and dynamics of boiler deposits may demonstrate the capability to modify the deposit nature and restrict the accumulation of contaminants; what role potential organic treatments may have in this is unclear at this time. The aim of EPRI in the assessment of organics in the fossil power plant cycle is to accomplish a greater understanding of the role, risks and benefits of organic treatment and to more fully engage the technical community in adoption of best practices for the optimum use of these treatments. (orig.)

  3. EPRI Guidance for Transition from Operations to Decommissioning

    International Nuclear Information System (INIS)

    McGrath, Richard; Reid, Richard; Snyder, Michael

    2016-01-01

    A wide range of key activities are necessary after permanent shutdown of a nuclear power plant before active dismantlement of the plant can begin. This period is typically referred to as the transition period. In some cases these activities are prescribed by regulation and in others they may be more practically driven or even optional. In either case, planning for transition activities should optimally take place prior to final shutdown. Additionally, execution of some transition period activities, such as filing required regulatory submittals, may be performed prior to plant shut down. In addition to general transition period activities such as defueling, management of operational wastes, fulfilling regulatory requirements and changes to plant technical specifications, there are a number of optional activities that may have a long-range impact on future decommissioning activities. This includes activities such as the timing of staff reductions and performance of chemical decontamination. EPRI is nearing completion of a project to develop guidance for transitioning a nuclear power plant to decommissioning. This project includes the following elements: - A review of required and recommended transition period activities. For countries where a clear regulatory framework exists, this includes country-specific requirements; - A review of pending regulatory activities in the US and other countries where there is currently no clear regulatory framework for transitioning to decommissioning; - A summary of activities that have been performed during the transition period for past and current decommissioning sites, as well as current sites that are actively planning decommissioning activities; and - Guidance for development of a transition plan for changing from an operational to decommissioning status. Informed planning of the transition period activities will provide immediate benefits in reducing costs and minimizing the duration of the transition period, as well as longer

  4. EPRI Guide to Managing Nuclear Utility Protective Clothing Programs

    International Nuclear Information System (INIS)

    Kelly, J.J.; Kelly, D.M.

    1993-10-01

    The Electric Power Research Institute (EPRI) commissioned a radioactive waste related project (RP2414-34) in 1989 to produce a guide for developing and managing nuclear plant protective clothing programs. Every nuclear facility must coordinate some type of protective clothing program for its radiation workers to ensure proper and safe protection for the wearer and to maintain control over the spread of contamination. Yet, every nuclear facility has developed its own unique program for managing such clothing. Accordingly, a need existed for a reference guide to assist with standardizing protective clothing programs and in controlling the potentially escalating economics of such programs. The initial Guide to Managing Nuclear Utility Protective Clothing Programs, NP-7309, was published in May 1991. Since that time, a number of utilities have reviewed and/or used the report to enhance their protective clothing programs. Some of these utilities requested that a computer program be developed to assist utilities in evaluating the economics of protective clothing programs consistent with the guidance in NP-7309. The PCEVAL computer code responds to that industry need. This report, the PCEVAL User's Manual, provides detailed instruction on use of the software

  5. EPRI/Alberta Research Council Clean Soil Process

    International Nuclear Information System (INIS)

    Spear, C.E.

    1992-12-01

    The EPRI/Alberta Research Council Clean Soil Process can remove hydrocarbon contamination from waste material from manufactured gas plants. The process uses coal as an absorbent to remove hydrocarbons. For petroleum contaminated soils, the process can bring residual concentration of petroleum below 0.1 percent and polycyclic aromatic hydrocarbon (PAH) concentration to 1--5 ppM. For coal tar contaminated soils, the process can reduce tar concentrations to about 0.05-0.5 percent and the PAH concentration to about 10--60 ppM. Additional post-treatment may be required for some precleaned soils. The process yields by-product agglomerates suitable for combustion in industrial boilers. Light hydrocarbons such as benzene are vaporized from the soil, condensed and collected in the Process and disposed of off-site. The Clean Soil Process has been tested at pilot-plant scale. A conceptual design for a 200-tons-per-day plant yielded a capital cost estimated at $3.1 million with a per-ton operating cost of $40

  6. EPRI-LATTICE: a multigroup neutron transport code for light water reactor lattice physics calculations

    International Nuclear Information System (INIS)

    Jones, D.B.

    1986-01-01

    EPRI-LATTICE is a multigroup neutron transport computer code for the analysis of light water reactor fuel assemblies. It can solve the two-dimensional neutron transport problem by two distinct methods: (a) the method of collision probabilities and (b) the method of discrete ordinates. The code was developed by S. Levy Inc. as an account of work sponsored by the Electric Power Research Institute (EPRI). The collision probabilities calculation in EPRI-LATTICE (L-CP) is based on the same methodology that exists in the lattice codes CPM-2 and EPRI-CPM. Certain extensions have been made to the data representations of the CPM programs to improve the overall accuracy of the calculation. The important extensions include unique representations of scattering matrices and fission fractions (chi) for each composition in the problem. A new capability specifically developed for the EPRI-LATTICE code is a discrete ordinates methodology. The discrete ordinates calculation in EPRI-LATTICE (L-SN) is based on the discrete S/sub n/ methodology that exists in the TWODANT program. In contrast to TWODANT, which utilizes synthetic diffusion acceleration and supports multiple geometries, only the transport equations are solved by L-SN and only the data representations for the two-dimensional geometry are treated

  7. Status of NRC approval of EPRI electromagnetic interference susceptibility testing guidelines for digital equipment

    International Nuclear Information System (INIS)

    James, R.W.; Shank, J.W.; Yoder, C.

    1996-01-01

    Historically, nuclear power plants installing digital equipment have been required to conduct expensive, site-specific electromagnetic interference (EMI) surveys to demonstrate that EMI will not affect the operation of sensitive electronic equipment. Consequently, EPRI formed a Utility Working Group which developed a set of generic EMI susceptibility testing guidelines, which were published as an EPRI report in September 1994. These guidelines are based upon EMI survey data obtained from several different plants and include criteria for determining their applicability. The Working Group interacted with NRC staff to obtain NRC approval. In April 1996, the NRC issued a Safety Evaluation Report (SER) endorsing the guidelines as a valid means of demonstrating EMI compatibility. The issuance of this SER was conditional on issuing a revision to the EPRI EMI Guidelines. This paper summarizes the guidelines, the NRC SER, and the current status of Revision 1 to the report

  8. EPRI research program NDE techniques for crack initiation of steam turbine rotor

    International Nuclear Information System (INIS)

    Goto, T.; Kimura, J.; Kawamoto, K.; Kadoya, Y.; Viswanathan, R.

    1990-01-01

    EPRI RP 2481-8 aims at the development of nondestructive methods for the life assessment of steam turbine rotor for its crack initiation caused by creep and/or fatigue. As a part of the research project, the demonstration of the state of the art NDE techniques was conducted during June to August of 1988 at EPRI NDE Center, Charlotte, N.C. by Mitsubishi Heavy Industries, Ltd. using four rotors retired after long term service (16-22x10 4 hr). This paper introduces the results of the demonstration

  9. Improvements to the COBRA-TF (EPRI) computer code for steam generator analysis. Final report

    International Nuclear Information System (INIS)

    Stewart, C.W.; Barnhart, J.S.; Koontz, A.S.

    1980-09-01

    The COBRA-TF (EPRI) code has been improved and extended for pressurized water reactor steam generator analysis. New features and models have been added in the areas of subcooled boiling and heat transfer, turbulence, numerics, and global steam generator modeling. The code's new capabilities are qualified against selected experimental data and demonstrated for typical global and microscale steam generator analysis

  10. Progress in EPRI-programs on the inspection of cast austenitic stainless steel

    Energy Technology Data Exchange (ETDEWEB)

    Dau, G; Behravesh, M; Amirato, P; Stone, R [Electric Power Research Inst., Charlotte, NC (United States). Nondestructive Evaluation Center

    1988-12-31

    This document presents the progress in EPRI programs on in-service inspection of Cast austenitic Stainless Steel (CSS). The CSS examination strategy is presented, together with results concerning thermal fatigue cracks and mechanical fatigue cracks. A statistical analysis method is provided, in order to estimate the crack detectability and the false call (a non-crack called crack). (TEC).

  11. The comparison between layout and design of APR1400 MCR and EPRI requirement

    International Nuclear Information System (INIS)

    Suharyo Widagdo; Darlis; Sigit Santoso; T J Suryono

    2013-01-01

    A good man-machine interface system is needed by a nuclear power reactor because of its complexity and high safety factor. The man-machine interface system is centralized in the main control room (MCR). All of monitoring and controlling activity to keep the installation operation safety can be done from this place. In order to increase its ability in monitoring and controlling a hard effort to raise the interface system to the highest possible level is done not only by using the latest computer technology and instrumentation system but also using Human Engineering, as well. The paper aims to compare the lay out and design the APR1400 MCR and the requirement from EPRI about main control room lay out and design as response of TMI-2 accident. We can see from the discussion that the design of the MCR of APR1400 have been applied the request of EPRI. (author)

  12. Study of heat transfer in 3D fuel rods of the EPRI-9R reactor modified

    International Nuclear Information System (INIS)

    Affonso, Renato Raoni Werneck; Lava, Deise Diana; Borges, Diogo da Silva; Sampaio, Paulo Augusto Berquo de; Moreira, Maria de Lourdes

    2014-01-01

    This paper aims to conduct a case study of the fuel rods that have the highest and the lowest average power of the EPRI-9R 3D reactor modified , for various positions of the control rods banks. For this, will be addressed the verification of computer code, comparing the results obtained with analytical solutions. This check is important so that, subsequently, it is possible use the program to understand the behavior of the fuel rods and the coolant channel of the EPRI-9R 3D reactor modified. Thus, in view of the scope of this paper, first a brief introducing on the heat transfer is done, including the rod equations and the equation of energy in the channel to allow the analysis of the results

  13. FETC/EPRI Biomass Cofiring Cooperative Agreement. Quarterly technical report, April 1-June 30, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, E.; Tillman, D.

    1997-12-01

    The FETC/EPRI Biomass Cofiring Program has accelerated the pace of cofiring development by increasing the testing activities plus the support activities for interpreting test results. Past tests conducted and analyzed include the Allen Fossil Plant and Seward Generating Station programs. On-going tests include the Colbert Fossil Plant precommercial test program, the Greenidge Station commercialization program, and the Blount St. Station switchgrass program. Tests in the formative stages included the NIPSCO cofiring test at Michigan City Generating Station. Analytical activities included modeling and related support functions required to analyze the cofiring test results, and to place those results into context. Among these activities is the fuel availability study in the Pittsburgh, PA area. This study, conducted for Duquesne Light, supports their initial investigation into reburn technology using wood waste as a fuel. This Quarterly Report, covering the third quarter of the FETC/EPRI Biomass Cofiring Program, highlights the progress made on the 16 projects funded under this cooperative agreement.

  14. Assessment of EPRI water chemistry guidelines for new nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, K.; Fruzzetti, K.; Garcia, S. [Electric Power Research Inst., Palo Alto, California (United States); Eaker, R. [Richard W. Eaker, LLC, Matthews, North Carolina (United States); Giannelli, J.; Tangen, J. [Finetech, Inc., Parsippany, New Jersey (United States); Gorman, J.; Marks, C. [Dominion Engineering, Inc., Reston, Virginia (United States); Sawochka, S. [NWT Corp., San Jose, California (United States)

    2010-07-01

    Water chemistry control technologies for nuclear power plants have been significantly enhanced over the past few decades to improve material and equipment reliability and fuel performance, and to minimize radionuclide production and transport. Chemistry Guidelines have been developed by the Electric Power Research Institute (EPRI) for current operating plants and have been intermittently revised over the past twenty-five years for the protection of systems and components and for radiation management. As new plants are being designed for improved safety and increased power production, it is important to ensure that the designs consider implementation of industry approved water chemistry controls. In parallel, the industry will need to consider and develop updated water chemistry guidelines as well as plant startup and operational strategies based on the advanced plant designs. In 2010, EPRI began to assess chemistry control strategies at advanced plants, based on the Design Control Documents (DCDs), Combined Construction and Operating License Applications (COLA), and operating experiences (where they exist) against current Water Chemistry Guidelines. Based on this assessment, differences between planned chemistry operations at new plants and the current Guidelines will be identified. This assessment will form the basis of future activities to address these differences. The project will also assess and provide, as feasible, water chemistry guidance for startup and hot functional testing of the new plants. EPRI will initially assess the GE-Hitachi/Toshiba ABWR and the Westinghouse AP1000 designs. EPRI subsequently plans to assess other plant designs such as the AREVA U.S. EPR, Mitsubishi Heavy Industries (MHI) U.S. APWR, and GE-Hitachi (GE-H) ESBWR. This paper discusses the 2010 assessments of the ABWR and AP1000. (author)

  15. Proceedings: 1991 EPRI workshop on secondary-side intergranular corrosion mechanisms

    International Nuclear Information System (INIS)

    Partridge, M.J.; Zemitis, W.S.

    1992-08-01

    A workshop on ''Secondary-Side Intergranular Corrosion Mechanisms'' was organized by EPRI as an effort to give those working in this area an opportunity to share their results, ideas, and plans. Topics covered included: (1) caustic induced intergranular attack/stress corrosion cracking (IGA/IGSCC), (2) plant experience, (3) boric acid as an IGA/IGSCC remedial measure, (4) lead induced IGA/IGSCC, and (5) acid induced IGA/IGSCC

  16. Decision-making aid for operational crews. Status of the EPRI DASS project

    International Nuclear Information System (INIS)

    Spurgin, A.J.; Cain, D.G.; Long, A.B.

    1983-01-01

    The paper covers recent work on the development of the Disturbance Analysis and Surveillance System (DASS) of the Electric Power Research Institute (EPRI), Palo Alto. The work at EPRI covered a BWR application and the development of advance concepts as applied to a PWR. The paper starts by considering the environment in which the DASS developments are taking place, especially the effect of observations resulting from evaluations of the Safety Parameter Display System (SPDS) in actual control rooms. It is pointed out that insights are being gained into the behaviour of reactor control room crews. The DASS group at EPRI has designed the control room operator aids for the process manager or systems manager. The paper covers the work on DASS in 1981 and 1982. The foundation of the work done in 1982 was established in 1981 when the DASS user and the functional design of software were defined, a working DASS was demonstrated and a portable test vehicle which could be used for dynamic evaluation of displays was developed. Both the philosophy and characteristics of the displays for the PWR and BWR DASS applications are discussed and pictures of the actual displays are included. The development and execution of a human factors plan is an integral part of the EPRI DASS programme and some discussion of the plan is included in the paper. It is concluded that there is a need for DASS-type systems and that such systems might be developed from an enhanced SPDS which would include the newly proposed emergency procedures based on identification of symptoms rather than events. (author)

  17. INEL design studies in support of the Westinghouse EPRI small plant study

    International Nuclear Information System (INIS)

    Burtt, J.D.; Kullberg, C.M.

    1986-03-01

    In support of the design effort of a Westinghouse EPRI small plant study, several analyses were performed at the Idaho National Engineering Laboratory. An analysis was performed to study fuel behavior under conditions of a limiting flow coastdown transient. Depressurization capabilities for the reactor coolant system were studied. The post-accident heat removal for the current containment design was studied. The results of all three studies are reported. 31 figs

  18. EPRI/NRC-RES fire PRA guide for nuclear power facilities. Volume 1, summary and overview

    International Nuclear Information System (INIS)

    2004-01-01

    This report documents state-of-the-art methods, tools, and data for the conduct of a fire Probabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application. The methods have been developed under the Fire Risk Re-quantification Study. This study was conducted as a joint activity between EPRI and the U. S. NRC Office of Nuclear Regulatory Research (RES) under the terms of an EPRI/RES Memorandum of Understanding (RS.1) and an accompanying Fire Research Addendum (RS.2). Industry participants supported demonstration analyses and provided peer review of this methodology. The documented methods are intended to support future applications of Fire PRA, including risk-informed regulatory applications. The documented method reflects state-of-the-art fire risk analysis approaches. The primary objective of the Fire Risk Study was to consolidate recent research and development activities into a single state-of-the-art fire PRA analysis methodology. Methodological issues raised in past fire risk analyses, including the Individual Plant Examination of External Events (IPEEE) fire analyses, have been addressed to the extent allowed by the current state-of-the-art and the overall project scope. Methodological debates were resolved through a consensus process between experts representing both EPRI and RES. The consensus process included a provision whereby each major party (EPRI and RES) could maintain differing technical positions if consensus could not be reached. No cases were encountered where this provision was invoked. While the primary objective of the project was to consolidate existing state-of-the-art methods, in many areas, the newly documented methods represent a significant advancement over previously documented methods. In several areas, this project has, in fact, developed new methods and approaches. Such advances typically relate to areas of past methodological debate.

  19. Assessment of EPRI water chemistry guidelines for new nuclear power plants

    International Nuclear Information System (INIS)

    Kim, K.; Fruzzetti, K.; Garcia, S.; Eaker, R.; Giannelli, J.; Tangen, J.; Gorman, J.; Marks, C.; Sawochka, S.

    2010-01-01

    Water chemistry control technologies for nuclear power plants have been significantly enhanced over the past few decades to improve material and equipment reliability and fuel performance, and to minimize radionuclide production and transport. Chemistry Guidelines have been developed by the Electric Power Research Institute (EPRI) for current operating plants and have been intermittently revised over the past twenty-five years for the protection of systems and components and for radiation management. As new plants are being designed for improved safety and increased power production, it is important to ensure that the designs consider implementation of industry approved water chemistry controls. In parallel, the industry will need to consider and develop updated water chemistry guidelines as well as plant startup and operational strategies based on the advanced plant designs. In 2010, EPRI began to assess chemistry control strategies at advanced plants, based on the Design Control Documents (DCDs), Combined Construction and Operating License Applications (COLA), and operating experiences (where they exist) against current Water Chemistry Guidelines. Based on this assessment, differences between planned chemistry operations at new plants and the current Guidelines will be identified. This assessment will form the basis of future activities to address these differences. The project will also assess and provide, as feasible, water chemistry guidance for startup and hot functional testing of the new plants. EPRI will initially assess the GE-Hitachi/Toshiba ABWR and the Westinghouse AP1000 designs. EPRI subsequently plans to assess other plant designs such as the AREVA U.S. EPR, Mitsubishi Heavy Industries (MHI) U.S. APWR, and GE-Hitachi (GE-H) ESBWR. This paper discusses the 2010 assessments of the ABWR and AP1000. (author)

  20. The impact of changing computing technology on EPRI [Electric Power Research Institute] nuclear analysis codes

    International Nuclear Information System (INIS)

    Breen, R.J.

    1988-01-01

    The Nuclear Reload Management Program of the Nuclear Power Division (NPD) of the Electric Power Research Institute (EPRI) has the responsibility for initiating and managing applied research in selected nuclear engineering analysis functions for nuclear utilities. The computer systems that result from the research projects consist of large FORTRAN programs containing elaborate computational algorithms used to access such areas as core physics, fuel performance, thermal hydraulics, and transient analysis. This paper summarizes a study of computing technology trends sponsored by the NPD. The approach taken was to interview hardware and software vendors, industry observers, and utility personnel focusing on expected changes that will occur in the computing industry over the next 3 to 5 yr. Particular emphasis was placed on how these changes will impact engineering/scientific computer code development, maintenance, and use. In addition to the interviews, a workshop was held with attendees from EPRI, Power Computing Company, industry, and utilities. The workshop provided a forum for discussing issues and providing input into EPRI's long-term computer code planning process

  1. Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I)

    International Nuclear Information System (INIS)

    Jackson, J.H.; Teysseyre, S.P.

    2012-01-01

    The Advanced Test Reactor National Scientific User Facility (ATR NSUF) and Electric Power Research Institute (EPRI) formed an agreement to test representative alloys used as reactor structural materials as a pilot program toward establishing guidelines for future ATR NSUF research programs. This report contains results from the portion of this program established as Phase I (of three phases) that entails baseline fracture toughness, stress corrosion cracking (SCC), and tensile testing of selected materials for comparison to similar tests conducted at GE Global Research. The intent of this Phase I research program is to determine baseline properties for the materials of interest prior to irradiation, and to ensure comparability between laboratories using similar testing techniques, prior to applying these techniques to the same materials after having been irradiated at the Advanced Test Reactor (ATR). The materials chosen for this research are the nickel based super alloy X-750, and nitrogen strengthened austenitic stainless steel XM-19. A spare core shroud upper support bracket of alloy X-750 was purchased by EPRI from Southern Co. and a section of XM-19 plate was purchased by EPRI from GE-Hitachi. These materials were sectioned at GE Global Research and provided to INL.

  2. Assessment of EPRI water chemistry guidelines for new nuclear power plants

    International Nuclear Information System (INIS)

    Reid Richard; Kim Karen; McCree, Anisa; Eaker, Richard; Sawochka, Steve; Giannelli, Joe

    2012-09-01

    Water chemistry control technologies for nuclear power plants have been significantly enhanced over the past few decades to improve material and equipment reliability and fuel performance, and to minimize radionuclide production and transport. Chemistry Guidelines have been developed by the Electric Power Research Institute (EPRI) for currently operating plants and have been intermittently revised over the past twenty-five years for the protection of systems and components and for radiation management. As new plants are being designed for improved safety and increased power production, it is important to ensure that the designs consider implementation of state-of-the-art, industry developed water chemistry controls. In parallel, the industry will need to consider and update water chemistry guidelines as well as plant startup and operational strategies based on the advanced plant designs. EPRI has performed assessments of water chemistry control guidance or assumptions provided in design and licensing documents for several advanced plant designs. These designs include: Westinghouse AP1000 Pressurized Water Reactor AREVA US-EPR Pressurized Water Reactor Mitsubishi Nuclear Energy Systems/Mitsubishi Heavy Industries Advanced Pressurized Water Reactor Korea Hydro and Nuclear Power APR1400 Pressurized Water Reactor Toshiba Advanced Boiling Water Reactor (ABWR) General Electric-Hitachi Economic Simplified Boiling Water Reactor (ESBWR) The intent of these assessments was to identify key design differences in each of the new plant designs relative to the current operating fleet and to identify differences in water chemistry specifications or design assumptions provided in design and licensing documents for the plants in comparison to current EPRI Water Chemistry Guidelines. This paper provides a summary of the key results of these assessments. The fundamental design and operation of the advanced plants is similar to the currently operating fleet. As such, the new plants are

  3. EPRI steam turbine and generator NDE, life assessment, and maintenance workshop

    International Nuclear Information System (INIS)

    Nottingham, L.D.; Sabourin, P.F.

    1992-10-01

    On July 16--19, 1991, the EPRI NDE Center hosted the second EPRI Steam Turbine and Generator NDE, Life Assessment and Maintenance Workshop. This workshop was co-sponsored by the Nuclear Power and the Generation and Storage Divisions of EPRI. Attendees represented all sectors of the industry including utilities, equipment manufacturers, forging suppliers, service organizations, government organizations, insurancecarriers, and consultants from the United States and abroad. Domestic utility presence was again strong, with 105 representatives from 44 utilities in attendance. Australia, Canada, England, Finland, France, Germany, Italy, Japan, Korea, New Zealand, Spain, Sweden and Switzerland were represented in the international contingent. A key and integral part of the workshop was a vendor equipment fair, in which some 23 organizations displayed and demonstrated equipment and services that they offer. Formal presentation of 53 technical papers made up the technical portion of the agenda, which also included two breakout discussion sessions on topical subjects. To provide optimum opportunity for participants to hear all presentations on closely related topics, the sessions were set such that a NDE session ran parallel to the life assessment session. The first NDE session included turbine related topics while the first life assessment session addressed generator issues. The last sessions of the workshop were just reversed with turbine topics being addressed in the life assessment session while generator issues were presented in the NDE session. Presentations on maintenance topics and on monitoring and diagnostics topics were also presented in parallel sessions. These proceedings contain the texts of the papers presented at the workshop. Individual papers in indexed separately

  4. Applications of EPRI database on environmentally assisted cracking in the nuclear industry

    International Nuclear Information System (INIS)

    Rungta, R.; Mindlin, H.; Gilman, J.D.

    1986-01-01

    A computerized database, EPRI Database on Environmentally Assisted Cracking (EDEAC), has been established to assemble stress-corrosion cracking and corrosion fatigue crack growth data on materials of interest to nuclear power generation. The database is being used to review the basis for the existing ASME reference fatigue crack growth curves for low alloy ferritic steels used for reactor pressure vessels. Correlations between fatigue crack growth rate and stress intensity factor range with corrections for frequency, stress ratio, and temperature for austenitic stainless steels in air are also being developed

  5. Initialization of the Euler model MODIS with field data from the 'EPRI plume model validation project'

    International Nuclear Information System (INIS)

    Petersen, G.; Eppel, D.; Lautenschlager, M.; Mueller, A.

    1985-01-01

    The program deck MODIS (''MOment DIStribution'') is designed to be used as operational tool for modelling the dispersion of a point source under general atmospheric conditions. The concentration distribution is determined by calculating its cross-wind moments on a vertical grid oriented in the main wind direction. The model contains a parametrization for horizontal and vertical coefficients based on a second order closure model. The Eulerian time scales, preliminary determined by fitting measured plume cross sections, are confirmed by comparison with data from the EPRI plume model validation project. (orig.) [de

  6. List of BMFT, USNRC, EPRI, and STA reports on reactor safety research

    International Nuclear Information System (INIS)

    1980-07-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Nuclear Regulatory Commission (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order : Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig./HP) [de

  7. List of reports in reactor safety research by BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1981-01-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Nuclear Regulatory Commission (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig.) [de

  8. Hydrogen-migration modeling for the EPRI/HEDL standard problems

    International Nuclear Information System (INIS)

    Travis, J.R.

    1982-01-01

    A numerical technique has been developed for calculating the full three-dimensional time-dependent Navier-Stokes equations with multiple species transport. The method is a modified form of the Implicit Continuous-fluid Eulerian (ICE) technique to solve the governing equations for low Mach number flows where pressure waves and local variations in compression and expansion are not significant. Large density variations, due to thermal and species concentration gradients, are accounted for without the restrictions of the classical Boussinesq approximation. Calculations of the EPRI/HEDL standard problems verify the feasibility of using this finite-difference technique for analyzing hydrogen dispersion within LWR containments

  9. EPRI compact analyzer: A compact, interactive and color-graphics based simulator for power plant analysis

    International Nuclear Information System (INIS)

    Ipakchi, A.; Khadem, M.; Chen, H.; Colley, R.W.

    1986-01-01

    This paper presents the results of an EPRI sponsored project (RP2395-2) for design and development of an interactive, and color graphics based simulator for power plant analysis. The system is called Compact Analyzer and can be applied to engineering and training applications in the utility industry. The Compact Analyzer's software and system design are described. Results of two demonstration system for a nuclear plant, and a fossil plant are presented, and the applications of the Compact Analyzer to operating procedures evaluation are discussed

  10. Applications of EPRI database on environmentally assisted cracking in the nuclear industry

    International Nuclear Information System (INIS)

    Rungta, R.; Mindlin, H.; Gilman, J.D.

    1986-01-01

    A computerized database, EPRI Database on Environmentally Assisted Cracking (EDEAC), has been established to assemble stress corrosion cracking (SCC) and corrosion fatigue crack growth data on nuclear power generation industry materials. The database is currently used to review the basis for the existing ASME reference fatigue crack growth curves for low alloy ferritic steels used for reactor pressure vessels. Also, correlations between fatigue crack growth rate and stress intensity factor range with corrections for frequency, stress ratio, and temperature for austenitic stainless steels in air are being developed using the EDEAC

  11. Compressed-air energy storage: Commercialization potential and EPRI roles in the commercialization process

    Science.gov (United States)

    Boyd, D. W.; Buckley, O. E.; Clark, C. E.

    1982-12-01

    This report describes an assessment of potential roles that EPRI might take to facilitate the commercial acceptance of compressed air energy storage (CAES) systems. The assessment is based on (1) detailed analyses of the market potential of utility storage technologies, (2) interviews with representatives of key participants in the CAES market, and (3) a decision analysis synthesizing much of the information about market and technology status. The results indicate a large potential market for CAES systems if the overall business environment for utilities improves. In addition, it appears that EPRI can have a valuable incremental impact in ensuring that utilities realize the potential of CAES by (1) continuing an aggressive information dissemination and technology transfer program, (2) working to ensure the success of the first United States CAES installation at Soyland Power Cooperative, (3) developing planning methods to allow utilities to evaluate CAES and other storage options more effectively and more realistically, and (4) supporting R and D to resolve residual uncertainties in first-generation CAES cost and performance characteristics.

  12. Hydrogen water chemistry for BWRs: A status report on the EPRI development program

    International Nuclear Information System (INIS)

    Jones, R.L.; Nelson, J.L.

    1990-01-01

    Many BWRs have experienced extensive intergranular stress corrosion cracking (IGSCC) in their austenitic stainless steel coolant system piping, resulting in serious adverse impacts on plant capacity factors, O and M costs, and personnel radiation exposures. A major research program to provide remedies for BWR pipe cracking was co-funded by EPRI, GE, and the BWR Owners Group for IGSCC Research between 1979 and 1988. Results from this program show that the likelihood of IGSCC depends on reactor water chemistry (particularly on the concentrations of ionic impurities and oxidizing radiolysis products) as well as on material condition and the level of tensile stress. Tests have demonstrated that the concentration of oxidizing radiolysis products in the recirculating water of a BWR can be reduced substantially by injecting hydrogen into the feedwater. Recent plant data show that the use of hydrogen injection can reduce the rate of IGSCC to insignificant levels if the concentration of ionic impurities in the reactor water is kept sufficiently low. This approach to the control of BWR pipe cracking is called hydrogen water chemistry (HWC). This paper presents a review of the results of EPRI's HWC development program from 1980 to the present. In addition, plans for additional work to investigate the feasibility of adapting HWC to protect the BWR vessel and major internal components from potential stress corrosion cracking problems are summarized. (orig.)

  13. EPRI tailored collaboration 3 Calvert Cliffs cost and volume reduction program

    International Nuclear Information System (INIS)

    Rigsby, M.D.; Watson, B.A.

    1995-01-01

    Baltimore Gas ampersand Electric's (BGE) Calvert Cliffs Nuclear Power Plant (CCNPP) is a two unit PWR located approximately 60 miles south of Baltimore, Maryland on the Chesapeake Bay. Both units are of Combustion Engineering design, Unit 1 began commercial operation is 1975 and Unit 2 in 1978. BGE contracted with EPRI to participate in the industry initiative to reduce low-level waste volumes with the expectation to: (1) Reduce O ampersand M costs through LLRW reduction by lowering the volume requiring processing, transportation, and storage/disposal. (2) Manage responsibility available resources; i.e., material, equipment, personnel, etc., through segregation. decontamination, recycling and worker awareness. (3) Improve Calvert Cliff's positive image in the community by minimizing the impact on the environment through generating less LLRW. Baltimore Gas ampersand Electric is committed to effective management of low-level radioactive waste (LLRW) at the Calvert Cliffs Nuclear Power Plant. Established Nuclear Program Policies and Procedures support CCNPP's commitment to minimizing generation of low-level radioactive waste (LLRW). Since the mid 1980's, CCNPP has made progress in reducing the volume of LLRW generated and disposed. EPRI's onsite assessment and subsequent assistance pointed out several areas for improvement

  14. Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    Energy Technology Data Exchange (ETDEWEB)

    O' Regan, Patrick (Electric Power Research Inst., Knoxville, TN (United States)); Moody, Jim (JHM Consulting, Strafford (United States)); Loetman, Jan (Forsmarks Kraftgrupp AB (Sweden)); Sandstedt, Johan (Risk Pilot AB, Stockholm (Sweden))

    2010-12-15

    The objective of this project was a pilot plant demonstration of the EPRI RI-ISI Methodology to selected systems at Forsmark, Unit 3 (F3). This scope of this study encompasses five systems and is based upon F3 implementation of SKIFs guidance as well as other consideration as documented in the PMT program. As described in section 2, five systems were selected for evaluation. These systems were selected because they allow this project to focus on a number of issues of interest in developing a RI-ISI methodology and RI-ISI program. This includes the following: - Several different types of degradation may be identified, - Several different types of 'consequence of failure' may be identified, - Different types of safety systems are evaluated - Non-safety systems are evaluated Using the results of this application, insights and comparisons between SKIFS and the EPRI methodologies' are provided including the following: - Consequence of pressure boundary failure (PBF) as described in Section 3.14. - Degradation mechanism evaluation as described in Section 4.8. - Risk ranking as described in Section 5. - Element selection for inspection as described in Section 6. - Risk impact as described in Section 7

  15. Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    International Nuclear Information System (INIS)

    O'Regan, Patrick; Moody, Jim; Loetman, Jan; Sandstedt, Johan

    2010-12-01

    The objective of this project was a pilot plant demonstration of the EPRI RI-ISI Methodology to selected systems at Forsmark, Unit 3 (F3). This scope of this study encompasses five systems and is based upon F3 implementation of SKIFs guidance as well as other consideration as documented in the PMT program. As described in section 2, five systems were selected for evaluation. These systems were selected because they allow this project to focus on a number of issues of interest in developing a RI-ISI methodology and RI-ISI program. This includes the following: - Several different types of degradation may be identified, - Several different types of 'consequence of failure' may be identified, - Different types of safety systems are evaluated - Non-safety systems are evaluated Using the results of this application, insights and comparisons between SKIFS and the EPRI methodologies' are provided including the following: - Consequence of pressure boundary failure (PBF) as described in Section 3.14. - Degradation mechanism evaluation as described in Section 4.8. - Risk ranking as described in Section 5. - Element selection for inspection as described in Section 6. - Risk impact as described in Section 7

  16. 'EPRI tailored collaboration 2, Crystal River cost and volume reduction program'

    International Nuclear Information System (INIS)

    Genoa, P.H.

    1995-01-01

    During the fall of 1993. Florida Power Corporation joined the EPRI tailored collaboration on the low-level radioactive waste cost and volume reduction. In conjunction with an existing Radwaste Task Force, the EPRI team reviewed past and current waste management practices and developed a prioritized list of opportunities for improvement. In the first quarter of 1994, these opportunities were converted into Action Plans with responsibilities and due dates assigned to support a 60-day refueling outage beginning on April 7, 1994. The Action Plans focussed on: (1) Visible management support in the form of specific plant, department, and worker level radwaste reduction goals. (2) Heightened worker awareness in the form of training (formal and informal), signs, bulletins, and a radwaste awareness video. (3) Material changes from disposable to recyclables, non-incinerables to incinerables, liquid waste processing media replacements and filter use criteria. (4) Work practice changes to reduce valve leaks, reduce contaminated areas, reduce entries to contaminated areas, further segregation of waste streams including 'green is clean' wastes

  17. Applicability of EPRI Decommissioning Pre-Planning Manual to International Decommissioning Projects

    International Nuclear Information System (INIS)

    Lessard, Leo; Kay, Jim; Lefrancois, Donald; Furr, Richard; Lucas, Matthieu; Schauer, Konrad

    2016-01-01

    Industry models for planning the efficient decommissioning of a nuclear power plant continue to evolve. Effective planning is a key to cost control, a critical aspect of decommissioning. In 2001, the Electric Power Research Institute (EPRI) published the 'Decommissioning Pre-Planning Manual', referred to as the 'Manual'. The goal of the Manual was to develop a framework for use in pre-planning the decommissioning of a nuclear power plant. The original research was based on information collected during the active decommissioning of power reactors in New England, and the ongoing decommissioning planning of another reactor still in operation. The research team identified thirty-two (32) major Decommissioning Tasks that support the strategic and tactical planning that can be conducted in advance of plant shutdown. The Decommissioning Tasks were organized in a logical sequence of execution, and sorted in common discipline groupings. Owners of U.S. nuclear plants that have shut down prematurely during the past 5 years have found the EPRI Decommissioning Pre-Planning Manual useful in developing their transition plans from an operating to shutdown facility. Concurrently, during the past 15 years, the IAEA has published numerous technical and safety reports on nuclear reactor decommissioning planning and execution. IAEA's goal is to provide its global members with useful and timely guidance for the planning and execution of nuclear decommissioning projects. This information has been used extensively by international nuclear plant operators. One of the key objectives will be to develop a road-map linking the 32 EPRI Decommissioning Tasks with the comparable (or equivalent) topics covered in the IAEA library of decommissioning knowledge. The logical and convenient structure of the Manual will be cross-referenced to the IAEA topics to aid in organizing the development of decommissioning plans. The road-map will serve to provide a basis for improved

  18. A combined positron emission tomography (PET)- electron paramagnetic resonance imaging (EPRI) system: initial evaluation of a prototype scanner.

    Science.gov (United States)

    Tseytlin, Mark; Stolin, Alexander V; Guggilapu, Priyaankadevi; Bobko, Andrey A; Khramtsov, Valery V; Tseytlin, Oxana; Raylman, Raymond R

    2018-04-20

    The advent of hybrid scanners, combining complementary modalities, has revolutionized imaging; enhancing clinical practice and biomedical research. In this project, we investigated the melding of two complementary, functional imaging methods: positron emission tomography (PET) and electron paramagnetic resonance imaging (EPRI). The PET radiotracers can provide important information about cellular parameters, such as glucose metabolism. While EPR probes can provide assessment of tissue microenvironment, measuring parameters such as oxygenation and pH, for example. A combined PET/EPRI scanner has the promise to provide new insights not attainable with current imagers by simultaneous acquisition of multiple components of tissue microenvironments. In this investigation, a prototype system was created by combing two existing scanners, modified for simultaneous imaging. Specifically, a silicon photomultiplier (SiPM) based PET scanner ring designed as a portable scanner was combined with an EPRI scanner designed for the imaging of small animals. The ability of the system to obtain simultaneous images was assessed with a small phantom consisting of four cylinders containing both PET and EPR tracers. The resulting images demonstrated the ability to obtain contemporaneous PET and ERP images without cross-modality interference. The next step in this project is the construction of pre-clinical PET/EPRI scanner for multi-parametric assessment of physiologically important parameters of tissue microenvironments. . © 2018 Institute of Physics and Engineering in Medicine.

  19. A combined positron emission tomography (PET)-electron paramagnetic resonance imaging (EPRI) system: initial evaluation of a prototype scanner

    Science.gov (United States)

    Tseytlin, Mark; Stolin, Alexander V.; Guggilapu, Priyaankadevi; Bobko, Andrey A.; Khramtsov, Valery V.; Tseytlin, Oxana; Raylman, Raymond R.

    2018-05-01

    The advent of hybrid scanners, combining complementary modalities, has revolutionized the application of advanced imaging technology to clinical practice and biomedical research. In this project, we investigated the melding of two complementary, functional imaging methods: positron emission tomography (PET) and electron paramagnetic resonance imaging (EPRI). PET radiotracers can provide important information about cellular parameters, such as glucose metabolism. While EPR probes can provide assessment of tissue microenvironment, measuring oxygenation and pH, for example. Therefore, a combined PET/EPRI scanner promises to provide new insights not attainable with current imagers by simultaneous acquisition of multiple components of tissue microenvironments. To explore the simultaneous acquisition of PET and EPR images, a prototype system was created by combining two existing scanners. Specifically, a silicon photomultiplier (SiPM)-based PET scanner ring designed as a portable scanner was combined with an EPRI scanner designed for the imaging of small animals. The ability of the system to obtain simultaneous images was assessed with a small phantom consisting of four cylinders containing both a PET tracer and EPR spin probe. The resulting images demonstrated the ability to obtain contemporaneous PET and EPR images without cross-modality interference. Given the promising results from this initial investigation, the next step in this project is the construction of the next generation pre-clinical PET/EPRI scanner for multi-parametric assessment of physiologically-important parameters of tissue microenvironments.

  20. Proceedings: 1996 EPRI conference on innovative approaches to electricity pricing: Managing the transition to market-based pricing

    International Nuclear Information System (INIS)

    1996-03-01

    This report presents the proceedings from the EPRI conference on innovative approaches to electricity pricing. Topics discussed include: power transmission pricing; retail pricing; price risk management; new pricing paradigms; changes from cost-based to a market-based pricing scheme; ancillary services; retail market strategies; profitability; unbundling; and value added services. This is the leading abstract. Papers are processed separately for the databases

  1. 4-th EPRI International conference on the water chemistry of the organic-fuel thermal power plants

    International Nuclear Information System (INIS)

    Petrova, T.I.; Martynova, O.I.

    1995-01-01

    Most actual problems on thermal power engineering are discussed at EPRI conferences on organic fuel, conducted every two years. Experience in realization of economically beneficial, ecologically feasible modes and their monitoring, accumulated in recent years, was formulated at the 4-th conference with wide participation

  2. Proceedings: EPRI Workshop 2 -- Technical basis for EPA HLW disposal criteria

    International Nuclear Information System (INIS)

    Rogers, V.

    1993-03-01

    The Electric Power Research Institute (EPRI) sponsored this workshop to address the scientific and technical issues underlying the regulatory criteria, or standard, for the disposal of spent nuclear fuel, high-level radioactive waste, and transuranic waste, commonly referred to collectively as high-level waste (HLW). These regulatory criteria were originally promulgated by the US Environmental Protection Agency (EPA) in 40 CFR Part 191 in 1985. However, significant portions of the regulation were remanded by the Ninth Circuit Court of Appeals in 1987. This is the second of two workshops. Topics discussed include: gas pathway; individual and groundwater protection; human intrusion; population protection; performance; TRU conversion factors and discussions. Individual projects re processed separately for the databases

  3. List of reactor safety research reports from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1982-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  4. Proceedings of EPRI/DOE workshop on nuclear industry valve problems

    International Nuclear Information System (INIS)

    Sprung, J.L.

    1981-01-01

    Representatives from 29 nuclear industry organizations (11 valve manufacturers, 4 nuclear steam supply system vendors, 5 utilities, 3 national laboratories, 2 architect/engineering firms, the Department of Energy (DOE), EPRI, and 2 others) attended the workshop. Working sessions on key valves and on valve stem and seat leakage developed the following recommendations: (1) establish a small permanent expert staff to collect, analyze, and disseminate information about nuclear valve problems; (2) perform generic key valve programs for pressurized water reactors and for boiling water reactors, and several plant specific key valve programs, the latter to demonstrate the cost-effectiveness of such studies; (3) confirm the identity of, define, and initiate needed longer term research and development programs dealing with seat and stem leakage; and (4) establish an industry working group to review and advise on these efforts. Separate abstracts were prepared for three papers which are included in the appendix

  5. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Federal Ministry for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available from the Society for Reactor Safety (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  6. List of reports from reactor safety research of BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1979-01-01

    This list reviews reports from the Federal Republic of Germany, from the USA and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the USNRC, the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be adressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig./HP) [de

  7. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l' Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  8. List of reports on reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1984-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual points of view have to be considered for the distribitution of the reports. (orig.) [de

  9. Verification of the pollutant transport model 'MODIS' using EPRI plains site data from a tall stack

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, G; Eppel, D; Grassl, H

    1988-01-01

    A comprehensive numerical model for the simulation of pollutant dispersion from a point source into the mixing layer of the atmosphere over flat terrain is described. A moment reduction technique is used (MODIS = Moment Distribution) to combine the simplicity of the Gaussian plume description with the versatility of Eulerian grid formulations. Turbulent dispersion coefficients are parameterized in terms of mean square wind variances which in turn are obtained by a simplified second order closure model. The data base of the 'EPRI Plume Model Validation and Development Project' is used to validate the model for wind velocities above 0.5 m/s and for horizontal scales up to about one hundred kilometers. The model describes the three-dimensional structure of a plume also for stable conditions including a nighttime low level jet. For a convective planetary boundary layer it underestimates maximum ground concentration as do other models. However, it is capable of approaching measured maximum ground concentration under stable conditions.

  10. EPRI/DOE High-Burnup Fuel Sister Rod Test Plan Simplification and Visualization

    Energy Technology Data Exchange (ETDEWEB)

    Saltzstein, Sylvia J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sorenson, Ken B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hanson, B. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Shimskey, R. W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Klymyshyn, N. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Webster, R. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, P. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); MacFarlan, P. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Billone, Mike [Argonne National Lab. (ANL), Argonne, IL (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Rose [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bevard, Bruce [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-09-15

    The EPRI/DOE High-Burnup Confirmatory Data Project (herein called the “Demo”) is a multi-year, multi-entity test with the purpose of providing quantitative and qualitative data to show if high-burnup fuel mechanical properties change in dry storage over a ten-year period. The Demo involves obtaining 32 assemblies of high-burnup PWR fuel of common cladding alloys from the North Anna Nuclear Power Plant, loading them in an NRC-licensed TN-32B cask, drying them according to standard plant procedures, and then storing them on the North Anna dry storage pad for ten years. After the ten-year storage time, the cask will be opened and the mechanical properties of the rods will be tested and analyzed.

  11. List of reports from reactor safety research of BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1978-12-01

    This list reviews reports from the Federal Republic of Germany, from the USA and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the USNRC, the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig./HP) [de

  12. Experience gained in running the EPRI MMS code with an in-house simulation language

    International Nuclear Information System (INIS)

    Weber, D.S.

    1987-01-01

    The EPRI Modular Modeling System (MMS) code represents a collection of component models and a steam/water properties package. This code has undergone extensive verification and validation testing. Currently, the code requires a commercially available simulation language to run. The Philadelphia Electric Company (PECO) has been modeling power plant systems for over the past sixteen years. As a result, an extensive number of models have been developed. In addition, an extensive amount of experience has been developed and gained using an in-house simulation language. The objective of this study was to explore the possibility of developing an MMS pre-processor which would allow the use of the MMS package with other simulation languages such as the PECO in-house simulation language

  13. List of reports concerning reactor safety research from BMFT, CEA, EPRI, JSTA, and USNRC

    International Nuclear Information System (INIS)

    1982-12-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  14. List of reports from the BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1981-09-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA) the Japan Science and Technology Agency (JSTA) the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Saftety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  15. KBTAC: EPRI's center to assist the nuclear industry to apply the knowledge-based technology

    International Nuclear Information System (INIS)

    Lin, Chinglu; Naser, J.A.; Sun, B.K.H.

    1993-01-01

    The nuclear utility industry's complex engineering and procedure systems offer many opportunities for use of the knowledge-based technology such as expert systems and neural networks. The ability of expert systems to enhance human experts makes them an important tool in the areas of engineering, operations and maintenance. However, many current industry applications are research projects or turnkey systems supplied by vendors. These often do not impart to utility technical staff a clear understanding of the capabilities of knowledge-based systems (KBS). More importantly, simply using completed applications does not meet utilities' need to acquire the capabilities to build their own knowledge-based systems. Thus, EPRI is supporting its member utilities utilization of knowledge-based technology for power plant engineering, operations, and maintenance applications through the establishment of the Knowledge-Based Technology Application Center (KBTAC)

  16. EPRI (Electric Power Research Institute) operator reliability experiments program - Training implications

    International Nuclear Information System (INIS)

    Joksimovich, V.; Spurgin, A.J.; Orvis, D.D.; Moieni, P.; Worledge, D.H.

    1990-01-01

    The primary purpose of the EPRI Operator Reliability Experiments (ORE) Program is to collect data for use in reliability and safety studies of nuclear power plant operation to more realistically take credit for operator performance in preventing core damage. The two objectives for fulfilling this purpose are: (1) to obtain quantitative/qualitative performance data on operating crew responses in the control room for potential accident sequences by using plant simulators, and (2) to test the Human Cognitive Reliability (HCR) correlation. This paper briefly discusses the background to this program, data collection and analysis, the results and quantitative/qualitative insights stemming from phase one which might be of interest to simulator operators and trainers

  17. Update on the EPRI power generation risk-based inservice inspection pilot plant studies

    International Nuclear Information System (INIS)

    Gosselin, S.R.

    1997-01-01

    The scope for ASME Section XI ISI programs is largely based on deterministic results contained in design stress reports. These reports are normally very conservative and may not be an accurate representation of failure potential. Service experience has shown that failures are due to either corrosion or fatigue and typically occur in areas not included in the plant's ISI program. Consequently, nuclear plants are devoting significant resources to inspection programs that provide minimum benefit. As an alternative, significant industry attention has been devoted to the application of risked-based selection criteria in order to determine the scope of inservice inspection (ISI) programs at nuclear power plants. Preliminary EPRI studies indicate that the application of these techniques will allow operating nuclear plants to reduce the examination scope of current ISI programs by as much as 60 to 80%, significantly reduce costs, and continue to maintain high nuclear plant safety standards

  18. Development of improved methods for the LWR lattice physics code EPRI-CELL

    International Nuclear Information System (INIS)

    Williams, M.L.; Wright, R.Q.; Barhen, J.

    1982-07-01

    A number of improvements have been made by ORNL to the lattice physics code EPRI-CELL (E-C) which is widely used by utilities for analysis of power reactors. The code modifications were made mainly in the thermal and epithermal routines and resulted in improved reactor physics approximations and more efficient running times. The improvements in the thermal flux calculation included implementation of a group-dependent rebalance procedure to accelerate the iterative process and a more rigorous calculation of interval-to-interval collision probabilities. The epithermal resonance shielding methods used in the code have been extensively studied to determine its major approximations and to examine the sensitivity of computed results to these approximations. The study has resulted in several improvements in the original methodology

  19. Comparison of EPRI safety valve test data with analytically determined hydraulic results

    International Nuclear Information System (INIS)

    Smith, L.C.; Howe, K.S.

    1983-01-01

    NUREG-0737 (November 1980) and all subsequent U.S. NRC generic follow-up letters require that all operating plant licensees and applicants verify the acceptability of plant specific pressurizer safety valve piping systems for valve operation transients by testing. To aid in this verification process, the Electric Power Research Institute (EPRI) conducted an extensive testing program at the Combustion Engineering Test Facility. Pertinent tests simulating dynamic opening of the safety valves for representative upstream environments were carried out. Different models and sizes of safety valves were tested at the simulated operating conditions. Transducers placed at key points in the system monitored a variety of thermal, hydraulic and structural parameters. From this data, a more complete description of the transient can be made. The EPRI test configuration was analytically modeled using a one-dimensional thermal hydraulic computer program that uses the method of characteristics approach to generate key fluid parameters as a function of space and time. The conservative equations are solved by applying both the implicit and explicit characteristic methods. Unbalanced or wave forces were determined for each straight run of pipe bounded on each side by a turn or elbow. Blowdown forces were included, where appropriate. Several parameters were varied to determine the effects on the pressure, hydraulic forces and timings of events. By comparing these quantities with the experimentally obtained data, an approximate picture of the flow dynamics is arrived at. Two cases in particular are presented. These are the hot and cold loop seal discharge tests made with the Crosby 6M6 spring-loaded safety valve. Included in the paper is a description of the hydraulic code, modeling techniques and assumptions, a comparison of the numerical results with experimental data and a qualitative description of the factors which govern pipe support loading. (orig.)

  20. Study of heat transfer in 3D fuel rods of the EPRI-9R reactor modified; Estudo da transferencia de calor em varetas combustiveis 3D do reator EPRI-9R 3D modificado

    Energy Technology Data Exchange (ETDEWEB)

    Affonso, Renato Raoni Werneck; Lava, Deise Diana; Borges, Diogo da Silva; Sampaio, Paulo Augusto Berquo de; Moreira, Maria de Lourdes, E-mail: raoniwa@yahoo.com.br, E-mail: deisedy@gmail.com, E-mail: diogosb@outlook.com, E-mail: sampaio@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2014-07-01

    This paper aims to conduct a case study of the fuel rods that have the highest and the lowest average power of the EPRI-9R 3D reactor modified , for various positions of the control rods banks. For this, will be addressed the verification of computer code, comparing the results obtained with analytical solutions. This check is important so that, subsequently, it is possible use the program to understand the behavior of the fuel rods and the coolant channel of the EPRI-9R 3D reactor modified. Thus, in view of the scope of this paper, first a brief introducing on the heat transfer is done, including the rod equations and the equation of energy in the channel to allow the analysis of the results.

  1. Reactor pressure vessel embrittlement management through EPRI-Developed material property databases

    International Nuclear Information System (INIS)

    Rosinski, S.T.; Server, W.L.; Griesbach, T.J.

    1997-01-01

    Uncertainties and variability in U.S. reactor pressure vessel (RPV) material properties have caused the U.S. Nuclear Regulatory Commission (NRC) to request information from all nuclear utilities in order to assess the impact of these data scatter and uncertainties on compliance with existing regulatory criteria. Resolving the vessel material uncertainty issues requires compiling all available data into a single integrated database to develop a better understanding of irradiated material property behavior. EPRI has developed two comprehensive databases for utility implementation to compile and evaluate available material property and surveillance data. RPVDATA is a comprehensive reactor vessel materials database and data management program that combines data from many different sources into one common database. Searches of the data can be easily performed to identify plants with similar materials, sort through measured test results, compare the ''best-estimates'' for reported chemistries with licensing basis values, quantify variability in measured weld qualification and test data, identify relevant surveillance results for characterizing embrittlement trends, and resolve uncertainties in vessel material properties. PREP4 has been developed to assist utilities in evaluating existing unirradiated and irradiated data for plant surveillance materials; PREP4 evaluations can be used to assess the accuracy of new trend curve predictions. In addition, searches of the data can be easily performed to identify available Charpy shift and upper shelf data, review surveillance material chemistry and fabrication information, review general capsule irradiation information, and identify applicable source reference information. In support of utility evaluations to consider thermal annealing as a viable embrittlement management option, EPRI is also developing a database to evaluate material response to thermal annealing. Efforts are underway to develop an irradiation

  2. Signal validation of SPDS variables for Westinghouse and Combustion Engineering plants - an EPRI project

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    Signal validation in the context of this project is the process of combining information from multiple plant sensors to produce highly reliable information about plant conditions. High information reliability is achieved by the use of redundant sources of information and by the inherent detection, identification, and isolation of faulty signals. The signal validation methodology that has been developed in previous EPRI-sponsored projects has been enhanced and applied toward validation of critical safety-related SPDS signals in the Northeast Utilities Millstone 3 Westinghouse PWR plant and the Millstone 2 Combustion Engineering PWR plant. The designs were implemented in FORTRAN software and tested off-line using recorded plant sensor data, RETRAN-generated simulation data, and data to exercise software logic branches and the integration of software modules. Designs and software modules have been developed for 15 variables to support six PWR SPDS critical safety functions as required by a utility advisory group attached to the project. The signal validation process automates a task currently performed by plant operators and does so with consistent, verified logic regardless of operator stress and training level. The methodology uses a simple structure of generic software blocks, a modular implementation, and it performs effectively within the processor and memory constraints of modern plant process computers. The ability to detect and isolate sensor failures with greater sensitivity, robustness, and coverage of common-cause failures should ultimately lead to improved plant availability, efficiency, and productivity

  3. EPRI's nuclear power plant instrumentation and control program and its applicability to advanced reactors

    International Nuclear Information System (INIS)

    Naser, J.; Torok, R.; Wilkinson, D.

    1997-01-01

    I ampersand C systems in nuclear power plants need to be upgraded over the lifetime of the plant in a reliable and cost-effective manner to replace obsolete equipment, to reduce O ampersand M costs, to improve plant performance, and to maintain safety. This applies to operating plants now and will apply to advanced reactors in the future. The major drivers for the replacement of the safety, control, and information systems in nuclear power plants are the obsolescence of the existing hardware and the need for more cost-effective power production. Competition between power producers is dictating more cost-effective power production. The increasing O ampersand M costs to maintain systems experiencing obsolescence problems is counter to the needs for more cost-effective power production and improved competitiveness. This need for increased productivity applies to government facilities as well as commercial plants. Increasing competition will continue to be a major factor in the operation of both operating plants and advanced reactors. It will continue to dictate the need for improved productivity and cost-effectiveness. EPRI and its member nuclear utilities are working together on an industry wide I ampersand C Program to address I ampersand C issues and to develop cost-effective solutions. A majority of the I ampersand C products and demonstrations being developed under this program will benefit advanced reactors in both the design and operational phases of their life cycle as well as it will benefit existing plants. 20 refs

  4. EPRI-DOE Conference on Environmentally-Enhanced Hydropower Turbines: Technical Papers

    Energy Technology Data Exchange (ETDEWEB)

    Hogan, T. [Alden Research Laboratory, Inc., Holden, MA (United States)

    2011-12-01

    The EPRI-DOE Conference on Environmentally-Enhanced Hydropower Turbines was a component of a larger project. The goal of the overall project was to conduct the final developmental engineering required to advance the commercialization of the Alden turbine. As part of this effort, the conference provided a venue to disseminate information on the status of the Alden turbine technology as well as the status of other advanced turbines and research on environmentally-friendly hydropower turbines. The conference was also a product of a federal Memorandum of Understanding among DOE, USBR, and USACE to share technical information on hydropower. The conference was held in Washington, DC on May 19 and 20, 2011 and welcomed over 100 attendees. The Conference Organizing Committee included the federal agencies with a vested interest in hydropower in the U.S. The Committee collaboratively assembled this conference, including topics from each facet of the environmentally-friendly conventional hydropower research community. The conference was successful in illustrating the readiness of environmentally-enhanced hydropower technologies. Furthermore, the topics presented illustrated the need for additional deployment and field testing of these technologies in an effort to promote the growth of environmentally sustainable hydropower in the U.S. and around the world.

  5. Experience and benefits from using the EPRI MOV Performance Prediction Methodology in nuclear power plants

    International Nuclear Information System (INIS)

    Walker, T.; Damerell, P.S.

    1999-01-01

    The EPRI MOV Performance Prediction Methodology (PPM) is an effective tool for evaluating design basis thrust and torque requirements for MOVs. Use of the PPM has become more widespread in US nuclear power plants as they close out their Generic Letter (GL) 89-10 programs and address MOV periodic verification per GL 96-05. The PPM has also been used at plants outside the US, many of which are implementing programs similar to US plants' GL 89-10 programs. The USNRC Safety Evaluation of the PPM and the USNRC's discussion of the PPM in GL 96-05 make the PPM an attractive alternative to differential pressure (DP) testing, which can be costly and time-consuming. Significant experience and benefits, which are summarized in this paper, have been gained using the PPM. Although use of PPM requires a commitment of resources, the benefits of a solidly justified approach and a reduced need for DP testing provide a substantial safety and economic benefit. (author)

  6. Performance demonstration testing at the EPRI NDE center for intergranular stress corrosion cracking in BWR piping

    International Nuclear Information System (INIS)

    Pherigo, G.

    1986-01-01

    Intergranular stress corrosion cracking (IGSCC) has become a significant concern for the commercial electric utility industry during the past four years. As the IGSCC problem manifested itself, the Nuclear Regulatory Commission (NRC) responded by issuing Inspection and Enforcement (I and E) Bulletin 82-03 which required that ultrasonic inspection procedures be demonstrated on service- removed samples. The ability to reliably detect and discriminate IGSCC was recognized by the industry as a very difficult task, at best. Concurrent with the NRC bulletin, state-of-the-art yet practical techniques for the detection and discrimination of IGSCC had to be developed, demonstrated, and transferred to the field in a relatively short time. With the release of I and E Bulletin 83-02, procedures as well as personnel had to be qualified on service-removed samples. This paper reports how the EPRI Nondestructive Evaluation (NDE) Center developed the necessary technology and a formal training and qualification program to meet these needs on behalf of the industry

  7. Benchmarking of epithermal methods in the lattice-physics code EPRI-CELL

    International Nuclear Information System (INIS)

    Williams, M.L.; Wright, R.Q.; Barhen, J.; Rothenstein, W.; Toney, B.

    1982-01-01

    The epithermal cross section shielding methods used in the lattice physics code EPRI-CELL (E-C) have been extensively studied to determine its major approximations and to examine the sensitivity of computed results to these approximations. The study has resulted in several improvements in the original methodology. These include: treatment of the external moderator source with intermediate resonance (IR) theory, development of a new Dancoff factor expression to account for clad interactions, development of a new method for treating resonance interference, and application of a generalized least squares method to compute best-estimate values for the Bell factor and group-dependent IR parameters. The modified E-C code with its new ENDF/B-V cross section library is tested for several numerical benchmark problems. Integral parameters computed by EC are compared with those obtained with point-cross section Monte Carlo calculations, and E-C fine group cross sections are benchmarked against point-cross section descrete ordinates calculations. It is found that the code modifications improve agreement between E-C and the more sophisticated methods. E-C shows excellent agreement on the integral parameters and usually agrees within a few percent on fine-group, shielded cross sections

  8. Demonstration for the Applicability of the EPRI ETSS on the SG Tube Wear Defects Formed at the Tube Support Structure

    International Nuclear Information System (INIS)

    Shin, Ki Seok; Cheon, Keun Young; Nam, Min Woo; Min, Kyong Mahn

    2013-01-01

    In this paper, the authorized EPRI ETSS 27906.2 applied to the detection of tapered wear volumetric indications and depth sizing within the free span area, loose part not present was reviewed and applied to the site SG tubes for getting the actual value of the wear depth and providing structural integrity interpretation based on engineering evaluation. The experiment to demonstrate the applicability of EPRI ETSS was performed by the employment of the newly prepared STD tube and resulted in ensuring the effectiveness and equivalency of the EPRI ETSS as well. The authorized EPRI ETSS 27906.2 for getting the actual value of the wear depth and providing structural integrity interpretation based on engineering evaluation was reviewed and applied to the site SG tubes. The testing results were reviewed with the influences of SG tube material and the support structure. The impact of the tube materials was insignificant and that of the tube support structure showed somewhat conservative results. The testing resulted in successful demonstration of applicability of the EPRI ETSS on the SG tube wear defects at the tube support. One of the major flaw mechanisms detected in the currently operating domestic OPR-1000 pressurized water reactors(PWR's) steam generator(SG) tubes is wear defect. In general, wear defect has been constantly detected in the upper tube bundle imposed to the flow induced vibration interaction between tube and its support structure, and the quantity of the affected tubes has also shown the tendency to increase as plant operation life is added. In order to take appropriate measures and maintain the structural integrity for the SG tubes, wear defect is currently categorized as active damage mechanism and the tubes containing 40% or greater wear depth of the nominal tube wall thickness shall be plugged per SGMP(SG Management Program) Recently, a fairly large amplitude of wear defects on the Batwing(BW), one of the upper tube support structures in the SG tubes

  9. Demonstration for the Applicability of the EPRI ETSS on the SG Tube Wear Defects Formed at the Tube Support Structure

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Ki Seok; Cheon, Keun Young; Nam, Min Woo [Korea Hydro and Nuclear Power Co. Ltd, Daejeon (Korea, Republic of); Min, Kyong Mahn [Universal Monitoring and Inspection Inc., Daejeon (Korea, Republic of)

    2013-10-15

    In this paper, the authorized EPRI ETSS 27906.2 applied to the detection of tapered wear volumetric indications and depth sizing within the free span area, loose part not present was reviewed and applied to the site SG tubes for getting the actual value of the wear depth and providing structural integrity interpretation based on engineering evaluation. The experiment to demonstrate the applicability of EPRI ETSS was performed by the employment of the newly prepared STD tube and resulted in ensuring the effectiveness and equivalency of the EPRI ETSS as well. The authorized EPRI ETSS 27906.2 for getting the actual value of the wear depth and providing structural integrity interpretation based on engineering evaluation was reviewed and applied to the site SG tubes. The testing results were reviewed with the influences of SG tube material and the support structure. The impact of the tube materials was insignificant and that of the tube support structure showed somewhat conservative results. The testing resulted in successful demonstration of applicability of the EPRI ETSS on the SG tube wear defects at the tube support. One of the major flaw mechanisms detected in the currently operating domestic OPR-1000 pressurized water reactors(PWR's) steam generator(SG) tubes is wear defect. In general, wear defect has been constantly detected in the upper tube bundle imposed to the flow induced vibration interaction between tube and its support structure, and the quantity of the affected tubes has also shown the tendency to increase as plant operation life is added. In order to take appropriate measures and maintain the structural integrity for the SG tubes, wear defect is currently categorized as active damage mechanism and the tubes containing 40% or greater wear depth of the nominal tube wall thickness shall be plugged per SGMP(SG Management Program) Recently, a fairly large amplitude of wear defects on the Batwing(BW), one of the upper tube support structures in the SG

  10. EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization

    Energy Technology Data Exchange (ETDEWEB)

    Saltzstein, Sylvia J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sorenson, Ken B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hanson, Brady [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Billone, Mike [Argonne National Lab. (ANL), Argonne, IL (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Rose [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bevard, Bruce [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-07-01

    The EPRI/DOE High Burnup Confirmatory Data Project (herein called the "Demo") is a multi-year, multi-entity confirmation demonstration test with the purpose of providing quantitative and qualitative data to show how high-burnup fuel ages in dry storage over a ten-year period. The Demo involves obtaining 32 assemblies of high-burnup PWR fuel of four common cladding alloys from the North Anna Nuclear Power Plant, drying them according to standard plant procedures, and then storing them in an NRC-licensed TN-3 2B cask on the North Anna dry storage pad for ten years. After the ten-year storage time, the cask will be opened and the rods will be examined for signs of aging. Twenty-five rods from assemblies of similar claddings, in-reactor placement, and burnup histories (herein called "sister rods") have been shipped from the North Anna Nuclear Power Plant and are currently being nondestructively tested at Oak Ridge National Laboratory. After the non-destructive testing has been completed for each of the twenty-five rods, destructive analysis will be performed at ORNL, PNNL, and ANL to obtain mechanical data. Opinions gathered from the expert interviews, ORNL and PNNL Sister Rod Test Plans, and numerous meetings has resulted in the Simplified Test Plan described in this document. Some of the opinions and discussions leading to the simplified test plan are included here. Detailed descriptions and background are in the ORNL and PNNL plans in the appendices . After the testing described in this simplified test plan h as been completed , the community will review all the collected data and determine if additional testing is needed.

  11. Skin injuries from discrete radioactive particles: A summary of EPRI-sponsored experiments. Final report

    International Nuclear Information System (INIS)

    Owen, D.E.; Reece, W.D.; Poston, J.W. Sr.; McFarlane, D.L.

    1994-12-01

    In recent years there has been the debate over the risk to nuclear power plant workers from beta radiation-emitting discrete radioactive particles (or DRPs). DRPs-sometimes called open-quotes hot particlesclose quotes-are small, often microscopic, radioactive particles that can adhere to the skin and protective clothing of plant workers. They can potentially produce high radiation doses to very small areas of the skin. Concern is based on the knowledge that various types of nonstochastic skin injuries can result from sufficiently high beta radiation doses. While the effects for large-area irradiations (several square centimeters and larger) are generally well understood, the effects for doses to very small areas are less clear. However, the evidence is clear that the doses required to produce skin injuries from DRP irradiations are significantly larger than the dose limits prescribed in existing regulations for large-area skin exposures. One concern is that nuclear power plant efforts to comply with skin dose limits causes workers to receive unnecessary whole-body radiation exposure. In addition, DRP protection measures focus radiation protection resources on very low risk hazards, and may not be an optimum use of radiation protection resources. EPRI sponsored a series of irradiation experiments to address some of the DRP exposure issues. This report summarizes the results of experiments using sources covering a range of sizes and beta energies, simulating both activation product and fuel-bearing DRPS. NCRP Publication 106 states that all of these small skin injuries are minor, but that acute deep ulceration should be avoided. Accordingly, this research focused on open sores or scabs that remain unhealed for very long times. The ED 50 dose for these injuries was determined to be about 5 krad (50 Gy). A revised guideline might lower whole-body exposures associated with DRP control measures, while not significantly increasing the likelyhood of DRP injuries

  12. Analytical study for frequency effects on the EPRI/USNRC piping component tests. Part 1: Theoretical basis and model development

    International Nuclear Information System (INIS)

    Adams, T.M.; Branch, E.B.; Tagart, S.W. Jr.

    1994-01-01

    As part of the engineering effort for the Advanced Light Water Reactor the Advanced Reactor Corporation formed a Piping Technical Core Group to develop a set of improved ASME Boiler and Pressure Vessel Code, Section III design rules and approaches for ALWR plant piping and support design. The technical basis for the proposed changes to the ASME Boiler and Pressure Vessel Code developed by Technical Core Group for the design of piping relies heavily on the failure margins determined from the EPRI/USNRC piping component test program. The majority of the component tests forming the basis for the reported margins against failure were run with input frequency to natural frequency ratios (Ω/ω) in the range of 0.74 to 0.87. One concern investigated by the Technical Core Group was the effect which could exist on measured margins if the tests had been run at higher or lower frequency ratios than those in the limited frequency ratio range tested. Specifically, the concern investigated was that the proposed Technical Core Group Piping Stress Criteria will allow piping to be designed in the low frequency range (Ω/ω ≥ 2.0) for which there is little test data from the EPRI/USNRC test program. The purpose of this analytical study was to: (1) evaluate the potential for margin variation as a function of the frequency ratio (R ω = Ω/ω, where Ω is the forcing frequency and ω is the natural component frequency), (2) recommend a margin reduction factor (MRF) that could be applied to margins determined from the EPRI/USNRC test program to adjust those margins for potential margin variation with frequency ratio. Presented in this paper is the analytical approach and methodology, which are inelastic analysis, which was the basis of the study. Also, discussed is the development of the analytical model, the procedure used to benchmark the model to actual test results, and the various parameter studies conducted

  13. DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program. Joint Research and Development Plan

    International Nuclear Information System (INIS)

    Williams, Don

    2014-01-01

    Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's electrical generation capability. By the end of 2014, about one-third of the existing domestic fleet will have passed their 40th anniversary of power operations, and about one-half of the fleet will reach the same 40-year mark within this decade. Recognizing the challenges associated with pursuing extended service life of commercial nuclear power plants, the U.S. Department of Energy's (DOE) Office of Nuclear Energy [NE] and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs (DOE-NE's Light Water Reactor Sustainability [LWRS] Program and EPRI's Long-Term Operations [LTO] Program) to address these challenges. To ensure that a proper linkage is maintained between the programs, DOE-NE and EPRI executed a memorandum of understanding in late 2010 to @@@establish guiding principles under which research activities (between LWRS and LTO) could be coordinated to the benefit of both parties.@@@ This document represents the third annual revision to the initial version (March 2011) of the plan as called for in the memorandum of understanding.

  14. Characterization of the EPRI Differential Absorption Lidar (DIAL) System. Final report. [For remote sensing of air pollutants

    Energy Technology Data Exchange (ETDEWEB)

    Baumgartner, R.A.; Depp, J.G.; Evans, W.E.; Grant, W.B.; Hawley, J.G.; March, R.G.; Murray, E.R.; Proctor, E.K.

    1979-12-01

    SRI International designed and constructed a DIfferential Absorption Lidar (DIAL) to provide EPRI with a mobile field system for remote measurements of SO/sub 2/, NO/sub 3/, and O/sub 3/. After field testing the lidar was prepared for the sytem calibration testing where lidar measurements were compared to in situ profiles of SO/sub 2/, NO/sub 2/, and O/sub 3/. This two-week field program determined overall system accuracy and reliability in measuring varying ambient gas concentrations. The lidar was then returned to SRI for detailed subsystem performance evaluations. Improvements were made wherever possible, and the lidar was prepared for further systems tests. Tests were made using an NO/sub 2/ sample chamber to simulate a calibrated NO/sub 2/ plume, and ambient measured NO/sub 2/ concentrations were compared with values from a regional air pollutant monitoring station. Following the local calibration and the systems field tests, SRI evaluated the performance and reliability of the EPRI lidar. Based on that evaluation, SRI undertook a major analysis of possible system improvements. Although the remote measuring capability had been successfully demonstrated in the field program, SRI makes several recommendations for systems improvements which would increase the lidar accuracy and reliability.

  15. KBTAC [Knowledge-Based Technology Application Center] - The EPRI [Electric Power Research Institute]-sponsored knowledge-based technology application center

    International Nuclear Information System (INIS)

    Meyer, W.; Wood, R.M.; Scherer, J.

    1990-01-01

    The Electric Power Research Institute (EPRI) has announced the establishment of the Knowledge-Based Technology Application Center (KBTAC), whose goal is to assist member utilities with expert system technology and applications. The center, established November 7, 1989, is located on the campus of Syracuse University, Syracuse, New York, and will be operated jointly by Kaman Sciences Corporation and the university. The mission of the KBTAC is to assist EPRI member utilities to develop, test, and transfer expert systems into nuclear power plant operations, maintenance, and administration

  16. PWR water chemistry controls: a perspective on industry initiatives and trends relative to operating experience and the EPRI PWR water chemistry guidelines

    International Nuclear Information System (INIS)

    Fruzzetti, K.; Choi, S.; Haas, C.; Pender, M.; Perkins, D.

    2010-01-01

    An effective PWR water chemistry control program must address the following goals: Minimize materials degradation (e.g., PWSCC, corrosion of fuel, corrosion damage of steam generator (SG) tubes); Maintain fuel integrity and good performance; Minimize corrosion product transport (e.g., transport and deposition on the fuel, transport into the SGs where it can foul tube surfaces and create crevice environments for the concentration of corrosive impurities); Minimize dose rates. Water chemistry control must be optimized to provide overall improvement considering the sometimes variant constraints of the goals listed above. New technologies are developed for continued mitigation of materials degradation, continued fuel integrity and good performance, continued reduction of corrosion product transport, and continued minimization of plant dose rates. The EPRI chemistry program, in coordination with other EPRI programs, strives to improve these areas through application of chemistry initiatives, focusing on these goals. This paper highlights the major initiatives and issues with respect to PWR primary and secondary system chemistry and outlines the recent, on-going, and proposed work to effectively address them. These initiatives are presented in light of recent operating experience, as derived from EPRI's PWR chemistry monitoring and assessment program, and EPRI's water chemistry guidelines. (author)

  17. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  18. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  19. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1991-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  20. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  1. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  2. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1989-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  3. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA und USNRC

    International Nuclear Information System (INIS)

    1989-11-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Engergie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  4. List of reports of BMFT, CEA, EPRI, JSTA and USNRC in the field of reactor safety research

    International Nuclear Information System (INIS)

    1985-04-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commisariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electrical Power Research Institute (EPRI) and the United States Nuclear Regulatory Commision, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quaterly. (orig./HP) [de

  5. Fission product data for thermal reactors. Final report. Part 2. Users manual for EPRI-CINDER code and data

    International Nuclear Information System (INIS)

    England, T.R.; Wilson, W.B.; Stamatelatos, M.G.

    1976-12-01

    A four-group fission-product absorption chain library using ENDF/B-IV decay data and cross sections processed with a typical light water reactor spectrum for a modified version of the original CINDER code has been developed as described in Part 1. CINDER is a general point-depletion and fission product code based on an analytical solution of the equations describing nuclides coupled in any linear sequence of radioactive decays and neutron absorptions. The basic code has been in wide use for a number of years. Previously, the user was required to specify all physical data. This report describes the chain library in detail and a modified version of the basic CINDER code (EPRI-CINDER) that is still compatible with existing libraries

  6. DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program. Joint Research and Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Williams, Don

    2014-04-01

    Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation’s electrical generation capability. By the end of 2014, about one-third of the existing domestic fleet will have passed their 40th anniversary of power operations, and about one-half of the fleet will reach the same 40-year mark within this decade. Recognizing the challenges associated with pursuing extended service life of commercial nuclear power plants, the U.S. Department of Energy’s (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs (DOE-NE’s Light Water Reactor Sustainability [LWRS] Program and EPRI’s Long-Term Operations [LTO] Program) to address these challenges. To ensure that a proper linkage is maintained between the programs, DOE-NE and EPRI executed a memorandum of understanding in late 2010 to “establish guiding principles under which research activities (between LWRS and LTO) could be coordinated to the benefit of both parties.” This document represents the third annual revision to the initial version (March 2011) of the plan as called for in the memorandum of understanding.

  7. Material shielding of power frequency magnetic fields: Research and testing results from the EPRI Power Delivery Center-Lenox. Final report

    International Nuclear Information System (INIS)

    Anderson, C.B.

    1998-06-01

    Extensive investigations of a variety of material shielding methods have been performed at the EPRI Power Delivery Center--Lenox, Massachusetts. This work is part of a larger shielding investigation being done for EPRI by Electric Research and Management, Inc. (ERM) as part of the Magnetic Field Management Target in the EPRI Environment Group. Part of this work, involving cylinders of material, is to be included in a shielding handbook being prepared by ERM. Material shielding tests, not included in the handbook, as well as additional material shielding research, including testing, analyses, and computer simulations performed at the EPRI Power Delivery Center--Lenox are documented here. One of the major complications of using materials to shield magnetic fields is the mathematical complexity of the phenomenon involved. The result is that analytical solutions exist only for a very small number of simple geometries such as spheres, infinitely long cylinders, and infinite sheets. In practice, the materials typically come in the form of sheets. At present, there are no analytical methods for directly determining the shielding effectiveness of finite sheets of material, however, EPRI is sponsoring work in this area. There are some methods based on conformal mapping which can provide a solution for simple two-dimensional sheets. While such methods are useful in gaining insight into the mechanisms of shielding, they are not realistic enough to provide accurate shielding estimates. Empirical techniques are still required to determine the shielding effectiveness of material sheets. The material shielding tests and computer simulations are described in the report. The results of these tests and simulations have been used to develop a number of material shielding design rules for use in practical applications

  8. Near-term objectives of the works on the EUR document, comparison with the EPRI-URD

    International Nuclear Information System (INIS)

    Berbey, P.; Lopez, P. T. L.

    2010-01-01

    18 years after its foundation, the EUR organization is still quite active. During the last 3 years, the EUR products have mainly been evaluations of the Gen 3 LWR designs. The evaluations of the AP1000 and of the AES92 designs have been concluded in 2007 and a revised version of the evaluation of the EPR completed in 2009. Other LWR projects of potential interest for the EUR utilities, such as MHI's APWR are being reviewed before starting a full-scope assessment. Last, a revision C of the EUR volume 4 has been published in 2007. Coordinated actions with the other industry groups and the other stakeholders have been a centerpiece of the recent EUR strategy. In particular, the EUR and ENISS organizations have joined their efforts to coordinate their actions in nuclear safety, in particular vs. IAEA and WENRA. Also EUR and WNA/CORDEL have coordinated their efforts, in relation with the MDEP initiative of the safety regulators. Meanwhile, the EUR organization has kept enlarging: CEZ and MVM now are associated members and Gen-Energija from Slovenia has been invited to participate. Education and training has been dealt with actively. The EUR organization strongly supported WNU in setting up their successful 2009 'forum on harmonization'. A more technical course about the EUR requirements is being organized under the aegis of ENEN. Finally, preparatory material for a revision D of the EUR volumes 1 and 2 has been gathered. Out of this material, the update of the comparison between the EUR document and the EPRI-URD is of specific importance. In 1995-1997 a first analysis of the differences between the two documents had been carried out by the EUR organization and a synthesis report focused on 35 'macro issues' had been produced. Ten years later, this work was felt deserving a thorough update. Thus a specific organization has been set out between EUR and EPRI to update the old synthesis report. The 'macro issues' have been re-analyzed by a specific EUR working group leaded

  9. EDF feedback on recent EPRI SGOG SG chemical cleanings applications for TSP blockage reduction and heat transfer recover

    International Nuclear Information System (INIS)

    Dijoux, M.; De Bouvier, O.; Mercier, S.; Pages, D.; Bretelle, J.-L.; Leclercq, P.; Mermillod, A.

    2010-01-01

    Between 2007 and 2008, six Steam Generators Chemical Cleanings (SGCC) with the inhibitor free high temperature process were applied on EDF PWR units. The main goal was to reduce the excessive Tube Support Plate blockages observed on several units of the EDF fleet and the consequences on wide range levels and the risk of tube cracks. The heat transfer recovery was the second objective. Despite the correct results obtained, the corrosion impact of the high temperature process on internal metallic surfaces, higher than expected, and the environmental issues led EDF to move to a new cleaning process. The low temperature process developed by EPRI SGOG and applied for many years was selected for the same purpose. Some qualification laboratory tests were performed by Dominion Engineering Inc (DEI) to demonstrate the innocuousness an the efficiency of the process to achieve these goals. The EPRI SGOG process was then applied seven times by Westinghouse on the EDF units Cruas 3, Cruas 2, Belleville 1, Cattenom 1, Cattenom 3, Chinon B3 and Cattenom 4 between 2008 and 2010. All these units operate from the initial start at low AVT pH 25 o C (9,2) in the secondary circuit. Due to copper presence in the deposits to remove, the cleaning sequence 'Copper - Iron - Copper steps' was performed each time. After a short description of the process, including the specific adaptation in France, lessons learned are reported in this paper in the following areas: process monitoring, corrosion, efficiency, liquid and gaseous wastes, chemical pollution during start-up. Based on the 3 first applications in 2008, some modifications of the process were implemented, particularly for the copper step. For the units cleaned, 1100 to 4500 kg of deposits per SG have been removed, including TS sludge lancing. The reduction of TSP blockages was satisfying. The effect on steam pressure improvement and the wide range level is then discussed. The paper concludes on EDF perspectives for soft

  10. Validation of seismic soil-structure interaction analysis methods: EPRI [Electric Power Research Institute]/NRC [Nuclear Regulatory Commission] cooperation in Lotung, Taiwan, experiments

    International Nuclear Information System (INIS)

    Kot, C.A.; Srinivasan, M.G.; Hsieh, B.J.; Tang, Y.K.; Kassawara, R.P.

    1986-01-01

    The cooperative program between NRC/ANL and EPRI on the validation of soil-structure interaction analysis methods with actual seismic response data is described. A large scale-model of a containment building has been built by EPRI/Taipower in a highly seismic region of Taiwan. Vibration tests were performed, first on the basemat before the superstructure was built and then on the completed structure. Since its completion, the structure has experienced many earthquakes. The site and structural response to these earthquakes have been recorded with field (surface and downhole) and structural instrumentation. The validation program involves blind predictions of site and structural response during vibration tests and a selected seismic event, and subsequent comparison between the predictions and measurements. The predictive calculations are in progress. The results of the correlation are expected to lead to the evaluation of the methods as to their conservatisms and sensitivities

  11. Fuel model studies. Comparison of our present version of GAPCON-THERMAL-2 with results from the EPRI code comparison study. Partial report

    International Nuclear Information System (INIS)

    Malen, K.; Jansson, L.

    1978-08-01

    Runs with our present version of GAPCON-THERMAL-2 have been compared to results from the EPRI code comparison study. Usually also our version of GAPCON predicts high temperatures, 100-300 K or 10-15% higher than average code predictions and experimental results. The well-known temperaturegas release instablility is found also with GAPCON. In this case one identifies the gas release limits 1400 deg C and 1700 deg C as instablility points. (author)

  12. A new high-strength iron base austenitic alloy with good toughness and corrosion resistance (GE-EPRI alloy-TTL)

    International Nuclear Information System (INIS)

    Ganesh, S.

    1989-01-01

    A new high strength, iron based, austenitic alloy has been successfully developed by GE-EPRI to satisfy the strength and corrosion resistance requirements of large retaining rings for high capacity generators (>840Mw). This new alloy is a modified version of the EPRI alloy-T developed by the University of California, Berkeley, in an earlier EPRI program. It is age hardenable and has the nominal composition (weight %): 34.5 Ni, 5Cr, 3Ti, 1Nb, 1Ta, 1Mo, .5Al, .3V, .01B. This composition was selected based on detailed metallurgical and processing studies on modified versions of alloy-T. These studies helped establish the optimum processing conditions for the new alloy and enabled the successful scale-up production of three large (50-52 inch dia) test rings from a 5,000 lb VIM-VAR billet. The rings were metallurgically sound and exhibited yield strength capabilities in the range 145 to 220 ksi depending on the extent of hot/cold work induced. The test rings met or exceeded all the property goals. The above alloy can provide a good combination of strength, toughness and corrosion resistance and, through an suitable modification of chemistry or processing conditions, could be a viable candidate for high strength LWR internal applications. 3 figs

  13. Application of the NUREG/CR-6850 EPRI/NRC Fire PRA Methodology to a DOE Facility

    International Nuclear Information System (INIS)

    Elicson, Tom; Harwood, Bentley; Yorg, Richard; Lucek, Heather; Bouchard, Jim; Jukkola, Ray; Phan, Duan

    2011-01-01

    The application NUREG/CR-6850 EPRI/NRC fire PRA methodology to DOE facility presented several challenges. This paper documents the process and discusses several insights gained during development of the fire PRA. A brief review of the tasks performed is provided with particular focus on the following: Tasks 5 and 14: Fire-induced risk model and fire risk quantification. A key lesson learned was to begin model development and quantification as early as possible in the project using screening values and simplified modeling if necessary. Tasks 3 and 9: Fire PRA cable selection and detailed circuit failure analysis. In retrospect, it would have been beneficial to perform the model development and quantification in 2 phases with detailed circuit analysis applied during phase 2. This would have allowed for development of a robust model and quantification earlier in the project and would have provided insights into where to focus the detailed circuit analysis efforts. Tasks 8 and 11: Scoping fire modeling and detailed fire modeling. More focus should be placed on detailed fire modeling and less focus on scoping fire modeling. This was the approach taken for the fire PRA. Task 14: Fire risk quantification. Typically, multiple safe shutdown (SSD) components fail during a given fire scenario. Therefore dependent failure analysis is critical to obtaining a meaningful fire risk quantification. Dependent failure analysis for the fire PRA presented several challenges which will be discussed in the full paper.

  14. EPRI's on-site soil-structure interaction research and its application to design/analysis verification

    Energy Technology Data Exchange (ETDEWEB)

    Stepp, J C; Tang, H T [Seismic Center, Electric Power Research Institute, Palo Alto, CA (United States)

    1988-07-01

    Soil structure, interaction (SSI) research at the Electric Power Research Institute (EPRI) is focused on validating modeling and computational procedures. A data base has been obtained with instrumented scale models of stiff structures founded both on unsaturated alluvial soils and on rock. Explosives were used to induce strong ground-motion for two experiments, one on rock and the other on alluvium. A third experiment, a one-fourth scale containment structure on saturated alluvium, relies on earthquakes as the energy source. Analysis of the explosion-induced SSI data shows a marked shift in the fundamental frequency of the soil-structure system to a lower frequency. The magnitude of the shift is a function of foundation conditions and level of excitation. Analytical simulation was found to require more sophisticated soil constitutive models and computer codes than are used in current practice. The current phase of the program concentrates on evaluating SSI models used in current design practice by comparing predicted with recorded data at points in the soil-structure system. (author)

  15. Framing scenarios of electricity generation and gas use: EPRI report series on gas demands for power generation. Final report

    International Nuclear Information System (INIS)

    Thumb, S.; Glover, W.; Hughes, W.R.

    1996-07-01

    Results of three EPRI projects have been combined to analyze power industry consumption of gas and other generating fuels. The report's capstone is a scenario analysis of power industry generation and fuel consumption. The Utility Fuel Consumption Model (UFCM), developed for the project, predicts generating capacity and generation by region and fuel through 2015, based on load duration curves, generation dispatch, and expected capacity additions. Scenarios embody uncertain factors, such as electricity demand growth, fuel switching, coal-gas competition, the merit order of gas-coal dispatch, and retirement of nuclear units, that substantially affect gas consumption. Some factors, especially electricity demand have very large effects. The report includes a consistent database on NUG (non-utility generation) capacity and generation and assesses historical and prospective trends in NUG generation. The report shows that NUG capacity growth will soon decline substantially. The study assesses industry capability for price-induced fuel switching from gas to oil and coal, documenting conversions of coal units to dual coal-gas capability and determining that gas-to-oil switching remains a strong influence on fuel availability and gas prices, though regulation and taxation have increased trigger prices for switching. 61 tabs

  16. EPRI's on-site soil-structure interaction research and its application to design/analysis verification

    International Nuclear Information System (INIS)

    Stepp, J.C.; Tang, H.T.

    1988-01-01

    Soil structure, interaction (SSI) research at the Electric Power Research Institute (EPRI) is focused on validating modeling and computational procedures. A data base has been obtained with instrumented scale models of stiff structures founded both on unsaturated alluvial soils and on rock. Explosives were used to induce strong ground-motion for two experiments, one on rock and the other on alluvium. A third experiment, a one-fourth scale containment structure on saturated alluvium, relies on earthquakes as the energy source. Analysis of the explosion-induced SSI data shows a marked shift in the fundamental frequency of the soil-structure system to a lower frequency. The magnitude of the shift is a function of foundation conditions and level of excitation. Analytical simulation was found to require more sophisticated soil constitutive models and computer codes than are used in current practice. The current phase of the program concentrates on evaluating SSI models used in current design practice by comparing predicted with recorded data at points in the soil-structure system. (author)

  17. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: January 1 to June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. (orig./HP) [de

  18. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: July 1 to December 31, 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. (orig./HP) [de

  19. Qualification according to PDI's techniques UT EPRI methodology Phased Array for the inspection of vessels of PWR reactor with advanced robotic equipment; Cualificacion segun metodologia PDI de EPRI de te cnicas UT Phased Array para la inspeccion de vasijas de reactor PWR con eq uipos roboticos avanzados

    Energy Technology Data Exchange (ETDEWEB)

    Gadea, J. R.; Gonzalez, P.; Fernandez, F.

    2014-07-01

    The techniques and procedures qualified in the program EPRI PDI are directly applicable in plants whose reference code is ASME XI - specifically the Appendix VIII-, mainly USA and countries in which it is established American PWR technology. While countries with reactors in operation technology ABB (Sweden) or type VVER (Finland and Eastern countries) requires a qualification of specific technical type ENIQ, PDI qualification is a valuable reference since it allows to deal with such qualifications with guarantees. (Author)

  20. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC. Reported period: April 1 - June 30, 1987

    International Nuclear Information System (INIS)

    1987-08-01

    The list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  1. Evaluation of existing EPRI and INEL test data to determine the worm to worm gear coefficient of friction in Limitorque actuators

    Energy Technology Data Exchange (ETDEWEB)

    Garza, I.A.

    1996-12-01

    About the last sizing parameter for motor operated valves which has not been determined by utility or NRC sponsored testing is actuator efficiency. A by-product of EPRI testing for valve factors is the measurement of the actuator efficiencies. Motor sizing in this testing provides efficiency testing for motors running near synchronous speed. INEL testing, sponsored by the NRC, for stem factors and rate of loading provides complimentary data for motors loaded down to zero speed. This paper analyzes the data from these two test programs to determine the coefficient of friction for the worm to worm gear interface. This allowed the development of an algorithm for determining the efficiency of actuators which have not been tested. This paper compares the results of this algorithm to the test data to provide a measure of the accuracy of this method for calculating actuator efficiency.

  2. On-Going International Research Program on Irradiated Concrete Conducted by DOE, EPRI and Japan Research Institutions. Roadmap, Achievements and Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    Le Pape, Yann [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Rosseel, Thomas M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    The Joint Department of Energy (DOE)-Electric Power Research Institute (EPRI) Program (Light Water Reactor Sustainability (LWRS) Program–Material Pathway–Concrete and Long-Term Operation (LTO) Program) and US Nuclear Regulatory Commission (NRC) research studies aim at understanding the most prominent degradation modes and their effects on the long-term operation of concrete structures to nuclear power generation. Based on the results of the Expanded Materials Degradation Analysis (EMDA), (NUREG/CR-7153, ORNL/TM-2011/545), irradiated concrete and alkali-silica reaction (ASR)-affected concrete structures are the two prioritized topics of on-going research. This report focuses specifically on the topic of irradiated concrete and summarizes the main accomplishments obtained by this joint program, but also provides an overview of current relevant activities domestically and internationally. Possible paths forward are also suggested to help near-future orientation of this program.

  3. List of reports on reactor safety research by BMFT, USNRC, EPRI and JSTA. Period under review: 1st January until 31st March 1978

    International Nuclear Information System (INIS)

    1978-05-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Regulatory Commisssion (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig.) [de

  4. Comparison of EMI/RFI requirements to qualify the equipment for nuclear power plant. (RG 1.180, EPRI TR 102323, IEC 62003 and GB/T 11684)

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Tae Heon [Korea Testing Laboratory, Ansan (Korea, Republic of); Kim, Jong Seog [Research Institute of Korea Electric Power Corporation, Daejeon (Korea, Republic of); Seo, Jeong Ho; Cho, Kyoung Youn [Korea Electric Association, Seoul (Korea, Republic of)

    2011-05-15

    One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). In some reports for nuclear power plant (NPP), electromagnetic interference (EMI), radio frequency interference (RFI), and power surges have been identified as environmental conditions that can affect the performance of safety-related electrical equipment. There are mainly two reference guides for applying to qualify EMI/RFI requirements of the equipment used in a NPP: US NRC RG 1.180 and EPRI TR 102323. Recently, IEC published the standard for the equipment in the NPP, IEC 62003. This paper has compared the requirements of these, including comparing of the requirement of the Chinese national standard, GB/T 11684

  5. Comparison of EMI/RFI requirements to qualify the equipment for nuclear power plant. (RG 1.180, EPRI TR 102323, IEC 62003 and GB/T 11684)

    International Nuclear Information System (INIS)

    Jang, Tae Heon; Kim, Jong Seog; Seo, Jeong Ho; Cho, Kyoung Youn

    2011-01-01

    One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). In some reports for nuclear power plant (NPP), electromagnetic interference (EMI), radio frequency interference (RFI), and power surges have been identified as environmental conditions that can affect the performance of safety-related electrical equipment. There are mainly two reference guides for applying to qualify EMI/RFI requirements of the equipment used in a NPP: US NRC RG 1.180 and EPRI TR 102323. Recently, IEC published the standard for the equipment in the NPP, IEC 62003. This paper has compared the requirements of these, including comparing of the requirement of the Chinese national standard, GB/T 11684

  6. On-Going International Research Program on Irradiated Concrete Conducted by DOE, EPRI and Japan Research Institutions. Roadmap, Achievements and Path Forward

    International Nuclear Information System (INIS)

    Le Pape, Yann; Rosseel, Thomas M.

    2015-01-01

    The Joint Department of Energy (DOE)-Electric Power Research Institute (EPRI) Program (Light Water Reactor Sustainability (LWRS) Program Material Pathway Concrete and Long-Term Operation (LTO) Program) and US Nuclear Regulatory Commission (NRC) research studies aim at understanding the most prominent degradation modes and their effects on the long-term operation of concrete structures to nuclear power generation. Based on the results of the Expanded Materials Degradation Analysis (EMDA), (NUREG/CR-7153, ORNL/TM-2011/545), irradiated concrete and alkali-silica reaction (ASR)-affected concrete structures are the two prioritized topics of on-going research. This report focuses specifically on the topic of irradiated concrete and summarizes the main accomplishments obtained by this joint program, but also provides an overview of current relevant activities domestically and internationally. Possible paths forward are also suggested to help near-future orientation of this program.

  7. Evaluation of existing EPRI and INEL test data to determine the worm to worm gear coefficient of friction in Limitorque actuators

    International Nuclear Information System (INIS)

    Garza, I.A.

    1996-01-01

    About the last sizing parameter for motor operated valves which has not been determined by utility or NRC sponsored testing is actuator efficiency. A by-product of EPRI testing for valve factors is the measurement of the actuator efficiencies. Motor sizing in this testing provides efficiency testing for motors running near synchronous speed. INEL testing, sponsored by the NRC, for stem factors and rate of loading provides complimentary data for motors loaded down to zero speed. This paper analyzes the data from these two test programs to determine the coefficient of friction for the worm to worm gear interface. This allowed the development of an algorithm for determining the efficiency of actuators which have not been tested. This paper compares the results of this algorithm to the test data to provide a measure of the accuracy of this method for calculating actuator efficiency

  8. PWR Secondary Water Chemistry Control Status: A Summary of Industry Initiatives, Experience and Trends Relative to the EPRI PWR Secondary Water Chemistry Guidelines

    International Nuclear Information System (INIS)

    Fruzzetti, Keith; Choi, Samuel

    2012-09-01

    The latest revision of the EPRI Pressurized Water Reactor (PWR) Secondary Water Chemistry Guidelines was issued in February 2009. The Guidelines continue to focus on minimizing stress corrosion cracking (SCC) of steam generator tubes, as well as minimizing degradation of other major components / subsystems of the secondary system. The Guidelines provide a technically-based framework for a plant-specific and effective PWR secondary water chemistry program. With the issuance of Revision 7 of the Guidelines in 2009, many plants have implemented changes that allow greater flexibility on startup. For example, the previous Guidelines (Revision 6) contained a possible low power hold at 5% power and a possible mid power hold at approximately 30% power based on chemistry constraints. Revision 7 has established a range over which a plant-specific value can be chosen for the possible low power hold (between 5% and 15%) and mid power hold (between 30% and 50%). This has provided plants the ability to establish significant plant evolutions prior to reaching the possible power hold; such as establishing seal steam to the condenser, placing feed pumps in service, or initiating forward flow of heater drains. The application of this flexibility in the industry will be explored. This paper also highlights the major initiatives and industry trends with respect to PWR secondary chemistry; and outlines the recent work to effectively address them. These will be presented in light of recent operating experience, as derived from EPRI's PWR Chemistry Monitoring and Assessment (CMA) program (which contains more than 400 cycles of operating chemistry data). (authors)

  9. From Electrons Paired to Electric Power Delivered- A Personal Journey in Research and Applications of Superconductivity at IBM, EPRI, and Beyond

    Science.gov (United States)

    Grant, Paul

    2014-03-01

    This talk will reprise a personal journey by the speaker in industrial and applied physics, commencing with his employment by IBM at age 17 in the early 1950s, and continuing through his corporate sponsored undergraduate and graduate years at Clarkson and Harvard Universities, resulting in 1965 in a doctorate in applied physics from the latter. He was subsequently assigned by IBM to its research division in San Jose (now Almaden), where he initially carried out both pure and applied theoretical and experimental investigations encompassing a broad range of company-related product technologies...storage, display, printer and data acquisition hardware and software. In 1973, he undertook performing DFT and quantum Monte Carlo calculations in support of group research in the then emerging field of organic and polymer superconductors, a very esoteric pursuit at the time. Following upon several corporate staff assignments involving various product development and sales strategies, in 1982 he was appointed manager of the cooperative phenomena group in the Almaden Research Center, which beginning in early 1987, made significant contributions to both the basic science and applications of high temperature superconductivity (HTSC). In 1993, after a 40-year career, he retired from IBM to accept a Science Fellow position at the Electric Power Research Institute (EPRI) where he funded power application development of superconductivity. In 2004, he retired from his EPRI career to undertake ``due diligence'' consulting services in support of the venture capital community in Silicon Valley. As a ``hobby,'' he currently pursues and publishes DFT studies in hope of discovering the pairing mechanism of HTSC. In summary, the speaker's career in industrial and applied physics demonstrates one can combine publishing a record three PRLs in one month with crawling around underground in substations with utility lineman helping install superconducting cables, along the way publishing 10

  10. Proceedings: On-line monitoring of corrosion an water chemistry for the electric power utility industry: An EPRI workshop held during the 12th International Corrosion Congress

    International Nuclear Information System (INIS)

    Licina, G.

    1994-03-01

    A two-day EPRI workshop on On-line Monitoring of Corrosion and Water Chemistry for the Electric Power Utility Industry included discussions on a variety of methods for the online monitoring of corrosion and water chemistry in a power plant environment. The workshop was held September 22 and 23, 1993 in Houston, Texas, as a part of the 12th International Corrosion Congress sponsored by NACE International. Methods in various stages of development, from laboratory demonstrations to in-plant monitoring, were presented by authors from all over the world. Recent developments in corrosion monitoring and the detection of specific chemical species in power plant environments have utilized a variety of electrochemical methods (both AC and DC), electrical resistance techniques, and potential drop techniques to evaluate crack extension. Other approaches, such as Raman spectroscopy of corroding surfaces, Specific ion detectors, and X-ray fluorescence and ion chromatography to analyze corrosion products have been demonstrated in the laboratory. Techniques that were described in the twenty-three technical papers included: Electrochemical noise, Electrical resistance, Field signature method, Linear polarization resistance, Neutron activation, Corrosion potential monitoring, Electrochemical detection of biofilm activity, Analysis of corrosion products by X-ray fluorescence, Potential drop method for assessing environmentally assisted crack growth, Harmonic impedance spectroscopy, Contact electric resistance, Conductivity and hydrogen sensors, Solid state methods for tracking oxygen and pH, and Raman spectroscopy. Individual papers are indexed separately

  11. Evaluation of PWR and BWR assembly benchmark calculations. Status report of EPRI computational benchmark results, performed in the framework of the Netherlands` PINK programme (Joint project of ECN, IRI, KEMA and GKN)

    Energy Technology Data Exchange (ETDEWEB)

    Gruppelaar, H. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Klippel, H.T. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Kloosterman, J.L. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Hoogenboom, J.E. [Technische Univ. Delft (Netherlands). Interfacultair Reactor Instituut; Leege, P.F.A. de [Technische Univ. Delft (Netherlands). Interfacultair Reactor Instituut; Verhagen, F.C.M. [Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands); Bruggink, J.C. [Gemeenschappelijke Kernenergiecentrale Nederland N.V., Dodewaard (Netherlands)

    1993-11-01

    Benchmark results of the Dutch PINK working group on calculational benchmarks on single pin cell and multipin assemblies as defined by EPRI are presented and evaluated. First a short update of methods used by the various institutes involved is given as well as an update of the status with respect to previous performed pin-cell calculations. Problems detected in previous pin-cell calculations are inspected more closely. Detailed discussion of results of multipin assembly calculations is given. The assembly consists of 9 pins in a multicell square lattice in which the central pin is filled differently, i.e. a Gd pin for the BWR assembly and a control rod/guide tube for the PWR assembly. The results for pin cells showed a rather good overall agreement between the four participants although BWR pins with high void fraction turned out to be difficult to calculate. With respect to burnup calculations good overall agreement for the reactivity swing was obtained, provided that a fine time grid is used. (orig.)

  12. Evaluation of PWR and BWR assembly benchmark calculations. Status report of EPRI computational benchmark results, performed in the framework of the Netherlands' PINK programme (Joint project of ECN, IRI, KEMA and GKN)

    International Nuclear Information System (INIS)

    Gruppelaar, H.; Klippel, H.T.; Kloosterman, J.L.; Hoogenboom, J.E.; Bruggink, J.C.

    1993-11-01

    Benchmark results of the Dutch PINK working group on calculational benchmarks on single pin cell and multipin assemblies as defined by EPRI are presented and evaluated. First a short update of methods used by the various institutes involved is given as well as an update of the status with respect to previous performed pin-cell calculations. Problems detected in previous pin-cell calculations are inspected more closely. Detailed discussion of results of multipin assembly calculations is given. The assembly consists of 9 pins in a multicell square lattice in which the central pin is filled differently, i.e. a Gd pin for the BWR assembly and a control rod/guide tube for the PWR assembly. The results for pin cells showed a rather good overall agreement between the four participants although BWR pins with high void fraction turned out to be difficult to calculate. With respect to burnup calculations good overall agreement for the reactivity swing was obtained, provided that a fine time grid is used. (orig.)

  13. EPRI engineering workstation software - Discussion and demonstration

    International Nuclear Information System (INIS)

    Stewart, R.P.; Peterson, C.E.; Agee, L.J.

    1992-01-01

    Computing technology is undergoing significant changes with respect to engineering applications in the electric utility industry. These changes result mainly from the introduction of several UNIX workstations that provide mainframe calculational capability at much lower costs. The workstations are being coupled with microcomputers through local area networks to provide engineering groups with a powerful and versatile analysis capability. PEGASYS, the Professional Engineering Graphic Analysis System, is a software package for use with engineering analysis codes executing in a workstation environment. PEGASYS has a menu driven, user-friendly interface to provide pre-execution support for preparing unput and graphical packages for post-execution analysis and on-line monitoring capability for engineering codes. The initial application of this software is for use with RETRAN-02 operating on an IBM RS/6000 workstation using X-Windows/UNIX and a personal computer under DOS

  14. The EPRI Laboratory experiments at ANL

    International Nuclear Information System (INIS)

    Roche, M.F.; Settle, J.L.; Leibowitz, L.; Johnson, C.E.; Ritzman, R.L.

    1987-01-01

    The vaporization of core-concrete mixtures is being measured using a transpiration method. Mixtures of stainless steel, concrete (limestone or basaltic) and urania (doped with La 2 O 3 , SrO, BaO, and ZrO 2 ) are vaporized at 2150 - 2400 K from a zirconia crucible into flowing He - 6% H 2 gas. Up to 600 ppM H 2 O is added to the gas to fix the partial molar free energy of oxygen in the range -420 kJ to -550 kJ. The fraction of the sample that is vaporized is determined by weight change and by chemical analyses on the condensates that are collected in an Mo condenser tube. The results are being used to test the thermodynemic data base and the underlying assumptions of computer codes used for prediction of release during the severe accident. 13 refs., 2 tabs

  15. LWR safety research at EPRI: an update

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Kalra, S.P.

    1983-01-01

    The philosophy, objectives, approach, and updated status of the Electric Power Research Institute's Light-Water-Reactor Safety Research Program are presented. In light of current industry needs, the major research and development emphases are described. The program focuses on providing enhanced capability via large-scale test projects, for understanding and predicting the behavior of nuclear power plants. This leads to a realistic quantification of the safety margins and to ways of improving reliability, availability, and productivity and thus to significant economic benefits for the nuclear industry. The major accomplishments resulting from various projects in the program categories of risk assessment, code development and validation, and analysis and testing are presented with the goal of technology transfer to the nuclear industry

  16. Transient evaluation using EMTP at one phase opening with the offsite power transformer for the emergency power supply systems of nuclear power plants. This report is a follow-up of the report published two years ago. Verification related to the open-phase detection method of the transformer by United States Electric Power Research Institute (EPRI)

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2015-01-01

    open-phase when the transformer is no-load which United States Electric Power Research Institute (EPRI) developed. As the detailed analyses data from EPRI related to the detection method concerned have not been disclosed officially yet, in this paper, the quantitative and detailed verification results of the method using EMTP is reported. (author)

  17. Proceedings of the USNRC/EPRI/ANL heated crevice seminar.

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. Y.; Fruzzetti, K.; Muscara, J.; Diercks, D. R.; Energy Technology; EPRI; USNRC

    2003-08-31

    An international Heated Crevice Seminar, sponsored by the Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Argonne National Laboratory, and the Electric Power Research Institute, was held at Argonne National Laboratory on October 7-11, 2002. The objective of the seminar was to provide a working forum for the exchange of information by contributing experts on current issues related to corrosion in heated crevices, particularly as it relates to the integrity of PWR steam generator tubes. Forty-five persons from six countries attended the seminar, including representatives from government agencies, private industry and consultants, government research laboratories, nuclear vendors, and electrical utilities. The seminar opened with keynote talks on secondary-side crevice environments associated with IGA and IGSCC of mill-annealed Alloy 600 steam generator tubes and the submodes of corrosion in heat transfer crevices. This was followed by technical sessions on (1) Corrosion in Crevice Geometries, (2) Experimental Methods, (3) Results from Experimental Studies, and (4) Modeling. The seminar concluded with a panel discussion on the present understanding of corrosive processes in heated crevices and future research needs.

  18. Status report on the EPRI fuel cycle accident risk assessment

    International Nuclear Information System (INIS)

    Erdmann, R.C.; Fullwood, R.R.; Garcia, A.A.; Mendoza, Z.T.; Ritzman, R.L.; Stevens, C.A.

    1979-07-01

    This report summarizes and extends the work reported in five unpublished draft reports: the accidental radiological risk of reprocessing spent fuel, mixed oxide fuel fabrication, the transportation of materials within the fuel cycle, and the disposal of nuclear wastes, and the routine atmospheric radiological risk of mining and milling uranium-bearing ore. Results show that the total risk contribution of the fuel cycle is only about 1% of the accident risk of the power plant and hence, with little error, the accident risk of nuclear electric power is that of the power plant itself. The power plant risk, assuming a very large usage of nuclear power by the year 2005, is only about 0.5% of the radiological risk of natural background. This work aims at a realistic assessment of the process hazards, the effectiveness of confinement and mitigation systems and procedures, and the associated likelihoods and estimated errors. The primary probabilistic estimation tool is fault tree analysis with the release source terms calculated using physical--chemical processes. Doses and health effects are calculated with the CRAC code. No evacuation or mitigation is considered: source terms may be conservative through the assumption of high fuel burnup (40,000 MWd/T) and short cooling (90 to 150 d); HEPA filter efficiencies are derived from experiments

  19. EPRI continues research on photovoltaic, grid storage integration : part 1

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2010-11-15

    This article discussed a core set of potential inverter/charger capabilities that could enhance the value of grid-tied PV and storage devices, making it possible to standardize communication messages for those functions that are common across many product types. For communication-connected PV and storage devices to benefit integrated distribution management systems, communication connectedness is required to allow the utility to both monitor and manage the behaviour of distributed devices so as to optimize system performance. Different system architectures result in different communication needs at the PV/storage device. Summary descriptions were provided for the following 7 necessary common smart inverter command functions: (1) connect/disconnect from grid, (2) power output adjustment, (3) var management, (4) storage management, (5) event/history logging, (6) status reporting/reading, and (7) time adjustment. Each function assumes the command execution is spread out over time for each device to avoid system disruption. As only the inverter can decide if a particular function is supportable, some functions were created as a targets rather than commands. Instead of sending individual commands to each PV inverter in the system, inverters should be equipped to manage their own level of reactive power generation based on the inverter capability, the configuration settings provided by the utility, and the locally observed system voltage. A single broadcast command could then switch large groups of inverters between particular volt/var configurations depending on system requirements. This would effectively accommodate both the diverse range of product types and the requirements of the grid, enabling increased penetration levels. 5 figs.

  20. EPRI nuclear fuel-cycle accident risk assessment

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    The present results of the nuclear fuel-cycle accident risk assessment conducted by the Electric Power Research Institute show that the total risk contribution of the nuclear fuel cycle is only approx. 1% of the accident risk of the power plant; hence, with little error, the accident risk of nuclear electric power is essentially that of the power plant itself. The power-plant risk, assuming a very large usage of nuclear power by the year 2005 is only approx. 0.5% of the radiological risk of natural background. The smallness of the fuel-cycle risk relative to the power-plant risk may be attributed to the lack of internal energy to drive an accident and the small amount of dispersible material. This work aims at a realistic assessment of the process hazards, the effectiveness of confinement and mitigation systems and procedures, and the associated likelihood of errors and the estimated size of errors. The primary probabilistic estimation tool is fault-tree analysis, with the release source terms calculated using physicochemical processes. Doses and health effects are calculated with CRAC (Consequences of Reactor Accident Code). No evacuation or mitigation is considered; source terms may be conservative through the assumption of high fuel burnup (40,000 MWd/t) and short cooling period (90 to 150 d); high-efficiency particulate air filter efficiencies are derived from experiments

  1. The industry/EPRI advanced light water reactor program

    International Nuclear Information System (INIS)

    Stahlkopf, K.E.; Noble, D.M.; Sugnet, W.R.; Bilan, W.J.

    1986-01-01

    For the United States nuclear power industry to remain viable, it must be prepared to meet the expected need for new generating capacity in the late 1990s with an improved reactor system. The best hope of meeting this requirement is with evolutionary changes in current LWR systems through system simplification and reevaluation of safety and operational design margins. The grid characteristics and the difficulty in raising capital for large projects indicate that smaller light water reactors (400 to 600 MWe) may play an important role the next generation

  2. How EPRI [Electric Power Research Institute] helps utilities save money

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    A number of case studies are presented which illustrate how the work of the Electric Power Research Institute in the USA has enabled nuclear utilities to save money. The areas covered by the examples are: steam generator tube repair; streamlining of reliability centred maintenance; cost effective instrumentation and control maintenance; reducing the frequency of instrument calibration; optimising the engineering change process; detecting and reducing fuel failure; extending the qualified life of equipment. (U.K.)

  3. Overview of the NRC/EPRI common cause analysis framework

    International Nuclear Information System (INIS)

    Rasmuson, D.M.; Worledge, D.H.; Mosleh, A.; Fleming, K.; Parry, G.W.; Paula, H.

    1988-01-01

    This paper presents an overview of a framework for the inclusion of the impact of common cause failures in risk and reliability evaluations. Common cause failures are defined as that subset of dependent failures whose causes are not explicitly included in the logic model as basic events. The emphasis here is on providing guidelines for a practical, systematic approach that can be used to perform and clearly document the analysis. The framework comprises four major stages: (1) Logic Model Development, (2) Identification of Common Cause Component Groups, (3) Common Cause Modeling and Data Analysis, and (4) Quantification and Interpretation of Results. The framework and the methods discussed for performing the different stages of the analysis integrate insights obtained from engineering assessments of the system and the historical evidence from multiple failure events into a systematic, reproducible, and defensible analysis. 25 references

  4. Steam generator inspection activities at the EPRI NDE Center

    International Nuclear Information System (INIS)

    Krzywosz, K.

    1988-01-01

    Various types of corrosion and mechanical damage continue to affect the availability of both recirculating and once-through steam generators. Both the tube bundle and its supporting structure are affected. Intergranular attack and stress corrosion cracking (SCC) are the corrosion-assisted tube-wall damage mechanisms of most concern at this time. Fatigue cracking and fretting at antivibration bars are currently the mechanical damage forms causing most concern. Improved NDE equipment and techniques are providing better detection and characterization of adverse conditions within the steam generators and doing it at an earlier stage. This allows timely corrective action. To maintain the projected life expectancy of existing and new steam generators, remedial measures have been implemented. These measures include shot- or roto-peening, U-bend stress relief, chemical cleaning of secondary side, and sleeving of tubes. The improved NDE technology will also be instrumental in monitoring and assessing the effectiveness of the remedial measures. The revision of guidance documents for steam generator in-service inspection (ISI) is providing more relevant information to support this complex operation. A multitasked project is described that includes evaluation of steam generator tube NDE technology, transfer of this technology to utilities, and rapid response utility assistance

  5. DOE/EPRI Electricity Storage Handbook in Collaboration with NRECA.

    Energy Technology Data Exchange (ETDEWEB)

    Akhil, Abbas Ali [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Huff, Georgianne [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Currier, Aileen B. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Kaun, Benjamin C [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Rastler, Dan M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Chen, Stella Bingqing [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Cotter, Andrew L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Bradshaw, Dale T. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Gauntlett, William D. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-02-01

    The Electricity Storage Handbook (Handbook) is a how - to guide for utility and rural cooperative engineers, planners, and decision makers to plan and implement energy storage projects. The Handbook also serves as an information resource for investors and venture capitalists, providing the latest developments in technologies and tools to guide their evaluation s of energy storage opportunities. It includes a comprehensive database of the cost of current storage systems in a wide variety of electric utility and customer services, along with interconnection schematics. A list of significant past and present energy storage projects is provided for a practical perspective . This Handbook, jointly sponsored by the U.S. Department of Energy and the Electric Power Research Institute in collaboration with the National Rural Electric Cooperative Association, is published in electronic form at www.sandia.gov/ess. This Handbook is best viewed online.

  6. Overview of the EPRI CONTRACTMIX model for natural gas applications

    International Nuclear Information System (INIS)

    1993-09-01

    The Contract Mix Model (CONTRACTMIX) is designed to assist gas supply planners in analyzing the costs and risks of alternative supply strategies. By explicitly incorporating uncertainty about gas demand and market conditions into the analysis, the methodology permits the analyst to compare contracting strategies on the basis of cost and risk and to assess the value of flexible strategies and contracts. The model is applicable to purchase decisions for natural gas and other fuels. CONTRACTMIX may be used at all phases of supply decision-making, from broad strategy formulation to detailed contract design and evaluation. This document introduces the prospective user to the model's capability for analysis of gas supply contracting decisions. The document describes the types of problems CONTRACTMIX is designed to address as well as the model's structure, inputs, outputs, and unique features

  7. NDE training activities at the EPRI NDE center

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The need for an industry-wide qualification for NDE personnel is becoming more evident in both in-service inspection and technical skills training. ASME Section XI requirements for the qualification and certification of visual, ultrasonic, and eddy current examines is one of the major areas being supported by training at the Center. The other major thrust is in response to the Boiling Water Reactor Owners Group and its recognition of the importance of the UT operator's accurately detecting, discriminating, and sizing intergranular stress corrosion cracks (IGSCC) in piping, and inspecting weld overlay repairs of these cracked pipes. In addition, the pressurized water reactor (PWR) utilities have recognized the importance of improved eddy current data analysis of steam generator tubing. The overall intent of the Center's training is to meet the most critical utility needs with quality training that can be used by the trainee's employer as a part of its certification of that individual. To do this, the Center has organized and activated a carefully maintained documentation and records system built around the Continuing Education Unit (CEU). To address the problem of the small supply of entry-level NDE personnel available to the utilities, the Center has developed, through its Human Resource Development, academic and utility co-op programs to generate guidelines and NDE teaching materials for high schools, technical schools, and universities

  8. Odex III: building on the EPRI walking robot

    International Nuclear Information System (INIS)

    Guzowski, S.

    1991-01-01

    Odetics has delivered a second generation preproduction Odex TM III robot to the French Commissariat a l'Energie Atomique (CEA). The CEA version of the robot is an all electric-actuated six-legged machine that uses an alternating tripod gate as its normal walking mode, keeping three of its six feet on the walking surface at all times. The six legs are normally positioned symmetrically 60 o apart around the torso, allowing for movement in all directions. Each leg subsystem contains three servo motors and a sophisticated arrangements of gear reducers, ball screws and linkage mechanisms to produce three essential leg motions (vertical travel, radial extension and tangential or side-to-side swing). This means that the top of the transporter body can be as compact as 3.5 ft in height when the legs are fully retracted, or as tall as 6.5ft when they are fully extended. Odex III can manoeuvre through doorways or turn tight corners, and the side-to-side swing of the legs allows asymmetric leg positioning for moving in constricted spaces. Odex III's feet contain sensors to determine proper foot placement while walking. One sensor-assembly detects updown vertical loading and checks that the foot is placed on a solid surface. Another set of sensors detects both side loading on the foot and obstacles in a lateral direction. Each leg can exert a 1200lb extension force. Together they are capable of exerting 5500lb of vertical force. The CEA is currently using the system in the SHERPA project which aims to demonstrate the feasibility of a versatile, modular mobile robot system for Pressurized Water Reactor maintenance. (author)

  9. DOE/EPRI Electricity Storage Handbook in Collaboration with NRECA

    Energy Technology Data Exchange (ETDEWEB)

    Akhil, Abbas A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Energy Storage Technology and Systems; Huff, Georgianne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Energy Storage Technology and Systems; Currier, Aileen B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Energy Storage Technology and Systems; Hernandez, Jacquelynne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Energy Storage Technology and Systems; Bender, Donald Arthur [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Kaun, Benjamin C. [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Rastler, Dan M. [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Chen, Stella Bingqing [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Cotter, Andrew L. [National Rural Electric Cooperative Association, Arlington, VA (United States); Bradshaw, Dale T. [National Rural Electric Cooperative Association, Arlington, VA (United States); Gauntlett, William D. [AECOM Technical Services, Inc., Albuquerque, NM (United States); Eyer, James [Clean Energy States Alliance, Montpelier, VT (United States); Olinsky-Paul, Todd [Clean Energy States Alliance, Montpelier, VT (United States); Ellison, Michelle [E& I Consulting, Oakland, CA (United States); Schoenung, Susan [Longitude 122 West, Inc., Menlo Park, CA (United States)

    2016-09-01

    The Electricity Storage Handbook (Handbook) is a how-to guide for utility and rural cooperative engineers, planners, and decision makers to plan and implement energy storage projects. The Handbook also serves as an information resource for investors and venture capitalists, providing the latest developments in technologies and tools to guide their evaluations of energy storage opportunities. It includes a comprehensive database of the cost of current storage systems in a wide variety of electric utility and customer services, along with interconnection schematics. A list of significant past and present energy storage projects is provided for a practical perspective. This Handbook, jointly sponsored by the U.S. Department of Energy and the Electric Power Research Institute in collaboration with the National Rural Electric Cooperative Association, is published in electronic form at www.sandia.gov/ess.

  10. PWR passive plant heat removal assessment: Joint EPRI-CRIEPI advanced LWR studies

    International Nuclear Information System (INIS)

    1991-03-01

    An independent assessment of the capabilities of the PWR passive plant heat removal systems was performed, covering the Passive Residual Heat Removal (PRHR) System, the Passive Safety Injection System (PSIS) and the Passive Containment Cooling System (PCCS) used in a 600 MWe passive plant (e.g., AP600). Additional effort included a review of the test programs which support the design and analysis of the systems, an assessment of the licensability of the plant with regard to heat removal adequacy, and an evaluation of the use of the passive systems with a larger plant. The major conclusions are as follows. The PRHR can remove core decay heat, prevents the pressurizer from filling with water for a loss-of-feedwater transient, and provides safety-grade means for maintaining the reactor coolant system in a safe shutdown condition for the case where the non-safety residual heat removal system becomes unavailable. The PSIS is effective in maintaining the core covered with water for loss-of-coolant accident pipe breaks to eight inches. The PCCS has sufficient heat removal capability to maintain the containment pressure within acceptable limits. The tests performed and planned are adequate to confirm the feasibility of the passive heat removal system designs and to provide a database for verification of the analytical techniques used for the plant evaluations. Each heat removal system can perform in accordance with Regulatory requirements, with the exception that the PRHR system is unable to achieve the required cold shutdown temperature of 200 F within the required 36-hour period. The passive heat removal systems to be used for the 600 MWe plant could be scaled up to a 900 MWe passive plant in a straightforward manner and only minimal, additional confirmatory testing would be required. Sections have been indexed separately for inclusion on the data base

  11. Dry cask storage: a Vepco/DOE/EPRI cooperative demonstration program

    International Nuclear Information System (INIS)

    Smith, M.L.

    1984-01-01

    In response to a Department of Energy (DOE) Solicitation for Cooperative Agreement Proposal, Virginia Electric and Power Company (Vepco) proposed to participate in a spent fuel storage demonstration program utilizing the dry cask storage technology. This proposed program includes dry cask storage at Vepco's Surry Nuclear Power Station and research and development activities at a DOE site in support of the licensed program at Surry. Phase I of Vepco's two-phase program involves a demonstration of the licensed dry cask storage of spent fuel in an inert atmosphere at the Surry Power Station site. Phase II of Vepco's proposed program will involve the demonstration of storing unconsolidated and consolidated spent fuel in dry casks filled only with air. This phase of the program will involve DOE site testing similar to Phase I and is expected to require an additional (fourth) cask to demonstrate storage of unconsolidated spent fuel in air-filled casks

  12. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1984-10-01

    The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  13. Seismic hazard for the Savannah River Site: A comparative evaluation of the EPRI and LLNL assessments

    International Nuclear Information System (INIS)

    Wingo, H.E.

    1992-01-01

    This report was conducted to: (1) develop an understanding of causes for the vast differences between the two comprehensive studies, and (2) using a methodology consistent with the reconciled methods employed in the two studies, develop a single seismic hazard for the Savannah River Site suitable for use in seismic probabilistic risk assessments with emphasis on the K Reactor. Results are presented for a rock site which is a typical because detailed evaluations of soil characteristics at the K Reactor are still in progress that account for the effects of a soil stablizing grouting program. However when the soils analysis is completed, the effects of soils can be included with this analysis with the addition of a single factor that will decrease slightly the seismic hazard for a rock site

  14. UK contribution to CEGB-EPRI-CRIEPI program on seismic isolation

    International Nuclear Information System (INIS)

    Austin, N.M.; Hattori, S.; Rodwell, E.; Womack, G.J.

    1989-01-01

    Over the last decade the concept of seismic isolation applied to nuclear power plants has generated a great deal of interest worldwide and a number of comprehensive reviews on the topic have been published. Understandably, most of the design and research and development (R and D) effort on seismic isolation has come from countries where larger magnitude earthquakes are an ever-present problem; e.g., Japan, USA, etc. In some areas of these countries seismic isolation may in fact present the only feasible design solution for potential sites of Liquid-Metal-Cooled Reactors (LMR's). This paper summarizes the test results obtained from a small scale seismic isolation system consisting of a laminated steel/natural rubber bearing and a viscodamper. Dynamic characteristics of the system; e.g., stiffness and damping, were measured for a variety of loading conditions. The results are suitable for developing a mathematical model of the isolation system and providing data for use in the design of larger scale bearings and viscodampers

  15. EPRI 25kW high concentration photovoltaic integrated array concept and associated economics

    International Nuclear Information System (INIS)

    Gunn, J.A.; Dostalek, F.J.

    1993-01-01

    This paper describes a cost effective photovoltaic array design for the high concentration technology being developed by the Electric Power Research Institute for utility scale applications. The concept of an ''integrated array'' is to attach Fresnel lens parquets directly to the front of the tracker structure and PV panels directly to the back of the structure thereby eliminating redundant structural components. The concept also incorporates the maximum use of automated manufacturing techniques for all components thereby minimizing material waste, fabrication and assembly labor. This paper also describes the results of a first approach cost and economic study for the technology which shows the potential for levelized energy cost below $0.10/kWh for a 50 MW ac plant given a mature technology

  16. Progress report - list of reports from BMFT, CEA, EPRI, JSTA and USNRC reactor safety research

    International Nuclear Information System (INIS)

    1982-10-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  17. Classic articles and workbook: EPRI monographs on simulation of electric power production

    International Nuclear Information System (INIS)

    Stremel, J.P.

    1991-12-01

    This monograph republishes several articles including a seminal one on probabilistic production costing for electric power generation. That article is given in the original French along with a English translation. Another article, written by R. Booth, gives a popular explanation of the theory, and a workbook by B. Manhire is included that carries through a simple example step by step. The classical analysis of non-probabilistic generator dispatch by L.K. Kirchmayer is republished along with an introductory essay by J.P. Stremel that puts in perspective the monograph material. The article in French was written by H. Baleriaux, E. Jamoulle, and Fr. Linard de Guertechin and first published in Brussels in 1967. It derived a method for calculating the expected value of production costs by modifying a load duration curve through the use of probability factors that account for unplanned random generator outages. Although the paper showed how pump storage plants could be included and how linear programming could be applied, the convolution technique used in the probabilistic calculations is the part most widely applied. The tutorial paper by Booth was written in a light style, and its lucidity helped popularize the method. The workbook by Manhire also shows how the calculation can be shortened significantly using cumulants to approximate the load duration curve

  18. List of reports in reactor safety research by BMFT, EPRI, JSTA, and USNRC

    International Nuclear Information System (INIS)

    1981-05-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig./HP) [de

  19. Life extension for fossil power plants: The EPRI [Electric Power Research Institute] strategy

    International Nuclear Information System (INIS)

    Byron, J.; Dooley, B.

    1988-01-01

    Fossil fuel-fired generating plants have traditionally been built under the assumption of an economic life of 20-30 years. Due to low load growth, escalating interest rates and costs of construction, and increasing regulation, great interest is expressed in retaining these units in service for 50-60 years or longer. Life extension activities are part of an ongoing process that continues throughout the extended lives of a utility's units. The process begins with an initial evaluation of life extension as a generation alternative, resulting in a ranking of units for life extension and a prioritization of components for evaluation. As the process continues, more detailed inspection data are created by a three-level approach, as well as a means for collecting, organizing and scheduling the information. This is implemented through the Integrated Life Extension Management (ILEM) model. This model provides information needed for management decision making such as component performance on unit power rating, availability of components on unit availability, component performance on unit availability and overall costs of the life extension tasks. Risks involved in life extension include the initial unavailability of capacity credits, uncertainty as to the level of availability that can be achieved by the life-extended plant, and uncertainties in environmental compliance. 8 refs., 1 fig., 2 tabs

  20. EPRI flow-loop/in situ test program for motor-operated valves

    International Nuclear Information System (INIS)

    Hosler, J.F.; Dorfman, L.S.

    1994-01-01

    The Electric Power Research Institute is undertaking a comprehensive research program to develop and validate methods for predicting the performance of common motor-operated gate, global, and butterfly valves. To assess motor-operated valve (MOV) performance characteristics and provide a basis for methods validation, full-scale testing was conducted on 62 MOVs. Tests were performed in four flow-loop facilities and in nine nuclear units. Forty-seven gate, five globe, and 10 butterfly valves were tested under a wide range of flow and differential pressure conditions. The paper describes the test program scope, test configurations, instrumentation and data acquisition, testing approach, and data analysis methods. Key results are summarized

  1. List of reports from BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1982-02-01

    This list reviews reports from the Federal Republic of Germany, from France from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  2. Summary of EPRI projects for improving power plant maintenance and maintainability

    International Nuclear Information System (INIS)

    Shugars, H.G.; Poole, D.N.; Pack, R.W.

    1979-01-01

    The Electric Power Research Institute is sponsoring projects to improve power plant maintenance and maintainability. Areas presently being emphasized are improvements in plant design for maintainability, improvements in performing nuclear plant refuelings, and development of on-line monitoring and diagnostic systems for various plant components. The seven projects are reviewed. They are: (1) human factors review of power plant maintainability; (2) refueling outage improvement; (3) on-line monitoring and diagnostics for power plant machinery; (4) acoustic emission and vibrati1on signature analysis of fossil fuel plant components; (5) acoustic monitoring of power plant valves; (6) on-line monitoring and diagnostics for generators; and (7) detection of water induction in steam turbines. Each project contractor and the project manager are listed for reference. 8 references

  3. Perry's bio-gas experience 1995 ASME/EPRI radwaste workshop

    International Nuclear Information System (INIS)

    Schwenk, A.K.

    1995-01-01

    The Perry Power Plant has been in commercial operation for about ten years. Although we didn't know it at the time, we now believe our bio-gas problem may have started about seven years ago. Barnwell discovered we had a bio-gas problem about a year and a half ago. We found out we had a bio-gas problem a few hours later. The history associated with this process at Perry is outlined, and past as well as present efforts to monitor this process are also discussed

  4. Proceedings: Primary water stress corrosion cracking: 1989 EPRI remedial measures workshop

    International Nuclear Information System (INIS)

    Gorman, J.A.

    1990-04-01

    A meeting on ''PWSCC Remedial Measures'' was organized to give those working in this area an opportunity to share their results, ideas and plans with regard to development and application of remedial measures directed against the primary water stress corrosion cracking (PWSCC) phenomenon affecting alloy 600 steam generator tubes. Topics discussed included: utility experience and strategies; nondestructive examination (NDE) methods for PWSCC; technical topics ranging from predictive methods for occurrence of PWSCC to results of corrosion tests; and services provided by vendors that can help prevent the occurrence of PWSCC or can help address problems caused by PWSCC once it occurs

  5. Testing and development of electric vehicle batteries for EPRI Electric Transportation Program

    Science.gov (United States)

    1985-11-01

    Argonne National Laboratory conducted an electric-vehicle battery testing and development program for the Electric Power Research Institute. As part of this program, eighteen battery modules previously developed by Johnson Controls, Inc. were tested. This type of battery (EV-2300 - an improved state-of-the-art lead-acid battery) was designed specifically for improved performance, range, and life in electric vehicles. In order to obtain necessary performance data, the batteries were tested under various duty cycles typical of normal service. This program, supported by the Electric Power Research Institute, consisted of three tasks: determination of the effect of cycle life vs peak power and rest period, determination of the impact of charge method on cycle life, and evaluation of the EV-2300 battery system. Two supporting studies were also carried out: one on thermal management of electric-vehicle batteries and one on enhanced utilization of active material in lead-acid batteries.

  6. Testing program PIN on experiments reported in EPRI-NP-369

    International Nuclear Information System (INIS)

    Kunt, J.; Pazdera, F.

    1980-03-01

    The testing is described of the applicability of program PIN for the thermomechanical simulation of PWR fuel elements. Program PIN is a modified program GAPCON-THERMAL-2. Four modifications are presented mostly affecting the results, viz., the fuel restructuring model, the fuel densification model, the gaseous fission product release model, and the fuel cladding creep model. The results show that the initial data for simulating fuel element behaviour in accident situations are determined using program PIN with accuracy comparable to that using other programs. (J.P.)

  7. Protective clothing and hot particle control: EPRI workshop gives the issues an airing

    International Nuclear Information System (INIS)

    Owen, D.E.

    1990-01-01

    A recent workshop organized by the Electric Power Research Institute on Protective Clothing Topics and Hot Particle Control brought together working-level engineers, industry experts and vendors. Ideas arising from the accident recovery efforts at Three Mile Island were exchanged. Among the topics discussed were the role of fabric colour in the retention of radionuclides, modesty garments, laundering of protective clothing and worker heat stress. (author)

  8. List of reports of BMFT, CEA, EPRI, JSTA and USNRC in the field of reactor safety research

    International Nuclear Information System (INIS)

    1984-04-01

    The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  9. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1986-04-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  10. Residential applliance data, assumptions and methodology for end-use forecasting with EPRI-REEPS 2.1

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, R.J,; Johnson, F.X.; Brown, R.E.; Hanford, J.W.; Kommey, J.G.

    1994-05-01

    This report details the data, assumptions and methodology for end-use forecasting of appliance energy use in the US residential sector. Our analysis uses the modeling framework provided by the Appliance Model in the Residential End-Use Energy Planning System (REEPS), which was developed by the Electric Power Research Institute. In this modeling framework, appliances include essentially all residential end-uses other than space conditioning end-uses. We have defined a distinct appliance model for each end-use based on a common modeling framework provided in the REEPS software. This report details our development of the following appliance models: refrigerator, freezer, dryer, water heater, clothes washer, dishwasher, lighting, cooking and miscellaneous. Taken together, appliances account for approximately 70% of electricity consumption and 30% of natural gas consumption in the US residential sector. Appliances are thus important to those residential sector policies or programs aimed at improving the efficiency of electricity and natural gas consumption. This report is primarily methodological in nature, taking the reader through the entire process of developing the baseline for residential appliance end-uses. Analysis steps documented in this report include: gathering technology and market data for each appliance end-use and specific technologies within those end-uses, developing cost data for the various technologies, and specifying decision models to forecast future purchase decisions by households. Our implementation of the REEPS 2.1 modeling framework draws on the extensive technology, cost and market data assembled by LBL for the purpose of analyzing federal energy conservation standards. The resulting residential appliance forecasting model offers a flexible and accurate tool for analyzing the effect of policies at the national level.

  11. R and D and Innovation Electric Utilities Challenges: the USA EPRI perspective and the European Horizon2020 framework

    International Nuclear Information System (INIS)

    Tagle, J. A.; Garcia Martin, J.; Martin Gomez, M.

    2013-01-01

    The paper presents the real challenges for the utilities worldwide to move the scientific and technological knowledge existing in our hands out of the laboratory and put it into the market place as rapidly as possible to provide a global electrification needed for a better worldwide life. Six main issues have been identified and each one is confronted with top ten challenges: Long-term operation of future and existing assets; Renewable energies; Zero-emission technologies; Energy Efficiency; Smart grids and cities and Water resources management. The corresponding challenges for each issue are described from both sides the USA utilities perspective and the European strategy with special emphasis in the road map for future R and D and innovation efforts needed for a Nuclear Energy renaissance policy.

  12. R and D and Innovation Electric Utilities Challenges: the USA EPRI perspective and the European Horizon2020 framework

    Energy Technology Data Exchange (ETDEWEB)

    Tagle, J. A.; Garcia Martin, J.; Martin Gomez, M.

    2013-07-01

    The paper presents the real challenges for the utilities worldwide to move the scientific and technological knowledge existing in our hands out of the laboratory and put it into the market place as rapidly as possible to provide a global electrification needed for a better worldwide life. Six main issues have been identified and each one is confronted with top ten challenges: Long-term operation of future and existing assets; Renewable energies; Zero-emission technologies; Energy Efficiency; Smart grids and cities and Water resources management. The corresponding challenges for each issue are described from both sides the USA utilities perspective and the European strategy with special emphasis in the road map for future R and D and innovation efforts needed for a Nuclear Energy renaissance policy.

  13. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1986-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  14. Cost of energy from utility-owned solar electric systems. A required revenue method for ERDA/EPRI evaluations

    Energy Technology Data Exchange (ETDEWEB)

    1976-06-01

    This methodology calculates the electric energy busbar cost from a utility-owned solar electric system. This approach is applicable to both publicly- and privately-owned utilities. Busbar cost represents the minimum price per unit of energy consistent with producing system-resultant revenues equal to the sum of system-resultant costs. This equality is expressed in present value terms, where the discount rate used reflects the rate of return required on invested capital. Major input variables describe the output capabilities and capital cost of the energy system, the cash flows required for system operation and maintenance, and the financial structure and tax environment of the utility.

  15. Integrating cobenefits produced with water quality BMPs into credits markets: Conceptualization and experimental illustration for EPRI's Ohio River Basin Trading

    Science.gov (United States)

    Liu, Pengfei; Swallow, Stephen K.

    2016-05-01

    This paper develops a method that incorporates the public value for environmental cobenefits when a conservation buyer can purchase water quality credits based on nonmarket valuation results. We demonstrate this approach through an experiment with adult students in a classroom laboratory environment. Our application contributes to the study of individual preference and willingness to pay for cobenefits associated with the production of water quality credits in relation to the Ohio River Basin Trading Project. We use three different methods to elicit individuals' willingness to pay (WTP), including (1) a hypothetical referendum, (2) a real referendum lacking incentive compatibility, and (3) a real choice with incentive compatibility. Methodologically, our WTP estimates suggest individuals are more sensitive to the cost changes and reveal the lowest value in the real choice with incentive compatibility. Practically, we find individuals value certain cobenefits and credits as public goods. Incorporating public value toward cobenefits may improve the overall efficiency of a water quality trading market. Based on our specification of a planner's welfare function, results suggest a substantial welfare improvement after identifying an optimal allocation of a buyer's budget across credits derived from agricultural management practices producing different portfolios of cobenefits.

  16. EPRI [Electric Power Research Institute]/ANL investigations of MCCI [molten core-concrete interactions] phenomena and aerosol release

    International Nuclear Information System (INIS)

    Spencer, B.W.; Gunther, W.H.; Armstrong, D.R.; Thompson, D.H.; Chasanov, M.G.; Sehgal, B.R.

    1986-01-01

    A program of laboratory investigations has been undertaken at Argonne National Laboratory, under sponsorship of the Electric Power Research Institute, in which the interaction between molten core materials and concrete is studied, with particular emphasis on measurements of the magnitude and chemical species present in the aerosol releases. The experiment technique used in these investigations is direct electrical heating in which a high electric current is passed through the core debris to sustain the high-temperature melt condition for potentially long periods of time. In the scoping experiments completed to date, this technique has been successfully used for corium masses of 5 and 20 kg, generating an internal heating rate of 1 kw/kg and achieving melt temperatures of 2000C. Experiments have been performed both with a concrete base and also with a cooled base with the addition of H 2 /CO sparging gas to represent chemical processes in a stratified layer. An aerosol and gas sampling system is being used to collect aerosol samples. Test results are now becoming available including masses of aerosols, x-ray diffraction, and scanning electron microscope analyses

  17. Benchmarking of EPRI-cell epithermal methods with the point-energy discrete-ordinates code (OZMA)

    International Nuclear Information System (INIS)

    Williams, M.L.; Wright, R.Q.; Barhen, J.; Rothenstein, W.

    1982-01-01

    The purpose of the present study is to benchmark E-C resonance-shielding and cell-averaging methods against a rigorous deterministic solution on a fine-group level (approx. 30 groups between 1 eV and 5.5 keV). The benchmark code used is OZMA, which solves the space-dependent slowing-down equations using continuous-energy discrete ordinates or integral transport theory to produce fine-group cross sections. Results are given for three water-moderated lattices - a mixed oxide, a uranium method, and a tight-pitch high-conversion uranium oxide configuration. The latter two lattices were chosen because of the strong self shielding of the 238 U resonances

  18. Fission product data for thermal reactors. Final report. Part I. A data set for EPRI-CINDER using ENDF/B-IV

    International Nuclear Information System (INIS)

    England, T.R.; Wilson, W.B.; Stamatelatos, M.G.

    1976-12-01

    A four-group fission-product neutron absorption library, appropriate for use in thermal reactors, is described. All decay parameters are taken from ENDF/B-IV. The absorption cross sections are also processed from ENDF/B-IV files, first into a 154-group set and subsequently collapsed into the 4-group set described in this report. The decay and cross section data were used to form 84 linear chains in the CINDER code format. These chains contain all significant fission products having half-lives exceeding 4 hours--a total of 186 nuclides. A 12-chain set containing one pseudo-chain for use in spatial depletion calculations is described. This set accurately reproduces the aggregate absorption buildup of the 84 chains. This report describes the chains and processed data, results of comparison calculations for various fuels, and a comparison of calculated temporal fission-product absorption buildup with corresponding results from a long-term fuel irradiation and cooling integral experiment

  19. DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program – Joint Research and Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Don Williams

    2012-04-01

    Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's electrical generation capability.

  20. Notes on the inherently safe core design meeting with the DOE-RRT, AI, GE, W-ARD, EPRI, and ETEC (at AI, Canoga Park, California, November 7-8, 1978)

    International Nuclear Information System (INIS)

    Jackola, A.S.; Paschall, R.K.

    1978-01-01

    The primary purpose of the meeting was to familiarize large LMFBR design managers with the capabilities of the Inherent Secondary Shutdown Systems (articulated rod and absorber balls) and to obtain inputs from them. The other purpose of the meeting was for the ISSS designers (AI, GE, and WARD) to present current work status, future plans, and schedules for their respective ISSS tasks

  1. Fast Gated EPR Imaging of the Beating Heart: Spatiotemporally-Resolved 3D Imaging of Free Radical Distribution during the Cardiac Cycle

    Science.gov (United States)

    Chen, Zhiyu; Reyes, Levy A.; Johnson, David H.; Velayutham, Murugesan; Yang, Changjun; Samouilov, Alexandre; Zweier, Jay L.

    2012-01-01

    In vivo or ex vivo electron paramagnetic resonance imaging (EPRI) is a powerful technique for determining the spatial distribution of free radicals and other paramagnetic species in living organs and tissues. However, applications of EPRI have been limited by long projection acquisition times and the consequent fact that rapid gated EPRI was not possible. Hence in vivo EPRI typically provided only time-averaged information. In order to achieve direct gated EPRI, a fast EPR acquisition scheme was developed to decrease EPR projection acquisition time down to 10 – 20 ms, along with corresponding software and instrumentation to achieve fast gated EPRI of the isolated beating heart with submillimeter spatial resolution in as little as 2 to 3 minutes. Reconstructed images display temporal and spatial variations of the free radical distribution, anatomical structure, and contractile function within the rat heart during the cardiac cycle. PMID:22473660

  2. Comparative study of Butterfly valves

    International Nuclear Information System (INIS)

    Galmes Belmonte, F.B.

    1998-01-01

    This work tries to justify the hydrodynamic butterfly valves performance, using the EPRI tests, results carried out in laboratory and in situ. This justification will be possible if: - The valves to study are similar - Their performance is calculated using EPRI's methodology Looking for this objective, the elements of the present work are: 1. Brief EPRI butterfly valve description it wild provide the factors which are necessary to define the butterfly valves similarity. 2. EPRI tests description and range of validation against test data definition. 3. Description of the spanish butterfly analyzed valves, and comparison with the EPRI performance results, to prove that this valves are similar to the EPRI test valves. In this way, it will not be necessary to carry out particular dynamic tests on the spanish valves to describe their hydrodynamic performance. (Author)

  3. REALM: an expert system for classifying emergencies

    International Nuclear Information System (INIS)

    Touchton, R.A.; Gunter, A.D.; Cain, D.G.

    1987-01-01

    In late 1983, EPRI began a program to encourage and stimulate the development of Artificial Intelligence Applications for the nuclear industry. As a part of that effort, EPRI has contracted Technology Applications, Inc., (TAI) to develop an artificially intelligent Emergency Classification system Prototype. This paper presents a description of and a status report on the recently completed prototype

  4. Development of on-site spent fuel transfer system designs

    International Nuclear Information System (INIS)

    Lambert, R.W.; Pennington, C.W.; Guerra, G.V.

    1993-01-01

    The Electric Power Research Institute (EPRI) of the United States has sponsored development of conceptual designs for accomplishing spent fuel transfer from spent fuel pools to casks and from one cask to another. Under an EPRI research contract, transnuclear has developed several concepts for spent fuel transfer systems. (J.P.N.)

  5. Minac - a small linear accelerator with large capabilities

    International Nuclear Information System (INIS)

    Lapides, M.

    1985-01-01

    Minac is a portable, high energy radiographic inspection device developed under Epri sponsorship by the Schonberg Radiation Corporation in California. It first entered field service in 1981. Since then an Epri-sponsored programme has continued to expand the capabilities of the system. (author)

  6. Recent experience with the CQE{trademark}

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, C.D.; Kehoe, D.B.; O`Connor, D.C.; Stallard, G.S.

    1997-12-31

    CQE (the Coal Quality Expert) is a software tool that brings a new level of sophistication to fuel decisions by seamlessly integrating the system-wide effects of fuel purchase decisions on power plant performance, emissions, and power generation costs. The CQE technology, which addresses fuel quality from the coal mine to the busbar and the stack, is an integration and improvement of predecessor software tools including: EPRI`s Coal Quality Information System, EPRI`s Coal Cleaning Cost Model, EPRI`s Coal Quality Impact Model, and EPRI and DOE models to predict slagging and fouling. CQE can be used as a stand-alone workstation or as a network application for utilities, coal producers, and equipment manufacturers to perform detailed analyses of the impacts of coal quality, capital improvements, operational changes, and/or environmental compliance alternatives on power plant emissions, performance and production costs. It can be used as a comprehensive, precise and organized methodology for systematically evaluating all such impacts or it may be used in pieces with some default data to perform more strategic or comparative studies.

  7. BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel

    International Nuclear Information System (INIS)

    Gilman, J.

    2005-01-01

    To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials

  8. 78 FR 13097 - Electric Power Research Institute; Seismic Evaluation Guidance

    Science.gov (United States)

    2013-02-26

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

  9. The need for standards to support V and V in the utility industry

    International Nuclear Information System (INIS)

    Breen, R.J.

    1992-01-01

    Software products continue to increase in importance as a vehicle for transferring the results of EPRI R and D to its utility sponsors. This increased emphasis has led to the development of procedures and guides to assure that software developed by EPRI is of high quality. The EPRI validation and verification guide is based on ANSI/ANS-10.4 - 87 and ANSI/IEE Std. 1012 - 1986. One approach used effectively at EPRI to bring some of its nuclear codes under an approved Quality Assurance program consistent with NRC requirements is a posterior V and V using a design review process. The steps taken to implement this process with RETRAN are described

  10. Instrumentation, controls and automation in the power industry

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    The year 1991 will be remembered as the year EPRI joined with the ISA Power Division to present an outstanding group to technical papers at the First Annual ISA/EPRI Joint Controls and Automation Conference. All papers met the theme for the conference namely Innovative Instrumentation, Controls, and Automation Techniques for the Power Generation Industry and cover a myriad of application ranging from nuclear to conventional fossil to co-generation plants involving nuclear, conventional BTG, and combined cycle equipment applications

  11. An Expert System Solution for the Quantitative Condition Assessment of Electrical Distribution Systems in the United States Air Force

    Science.gov (United States)

    1991-09-01

    Distribution system ... ......... 4 2. Architechture of an Expert system .. .............. 66 vi List of Tables Table Page 1. Prototype Component Model...expert system to properly process work requests Ln civil engineering (8:23). Electric Power Research Institute (EPRI). EPRI is a private organization ...used (51) Training Level. The level of training shop technicians receive, and the resulting proficiency, are important in all organizations . Experts 1

  12. Industry activities to resolve utility procurement issues

    International Nuclear Information System (INIS)

    Rosch, F.

    1993-01-01

    There are several industry organizations which are active in assisting the utilities in their equipment procurement enhancement. They include the Nuclear Management Resources Council (NUMARC), the Electric Power Research Institute (EPRI), and the Nuclear Procurement Issues Committee (NUPIC). The products include the NUMARC Procurement Initiatives, EPRI procurement related guidelines and databases, and NUPIC joint audits and commercial grade surveys. The industry procurement activities and products are reviewed, and their use by utilities to enhance their procurement process is related. 1 fig

  13. Development of transient initiating event frequencies for use in probabilistic risk assessments

    International Nuclear Information System (INIS)

    Mackowiak, D.P.; Gentillon, C.D.; Smith, K.L.

    1985-05-01

    Transient initiating event frequencies are an essential input to the analysis process of a nuclear power plant probabilistic risk assessment. These frequencies describe events causing or requiring scrams. This report documents an effort to validate and update from other sources a computer-based data file developed by the Electric Power Research Institute (EPRI) describing such events at 52 United States commercial nuclear power plants. Operating information from the United States Nuclear Regulatory Commission on 24 additional plants from their date of commercial operation has been combined with the EPRI data, and the entire data base has been updated to add 1980 through 1983 events for all 76 plants. The validity of the EPRI data and data analysis methodology and the adequacy of the EPRI transient categories are examined. New transient initiating event frequencies are derived from the expanded data base using the EPRI transient categories and data display methods. Upper bounds for these frequencies are also provided. Additional analyses explore changes in the dominant transients, changes in transient outage times and their impact on plant operation, and the effects of power level and scheduled scrams on transient event frequencies. A more rigorous data analysis methodology is developed to encourage further refinement of the transient initiating event frequencies derived herein. Updating the transient event data base resulted in approx.2400 events being added to EPRI's approx.3000-event data file. The resulting frequency estimates were in most cases lower than those reported by EPRI, but no significant order-of-magnitude changes were noted. The average number of transients per year for the combined data base is 8.5 for pressurized water reactors and 7.4 for boiling water reactors

  14. Development of transient initiating event frequencies for use in probabilistic risk assessments

    Energy Technology Data Exchange (ETDEWEB)

    Mackowiak, D.P.; Gentillon, C.D.; Smith, K.L.

    1985-05-01

    Transient initiating event frequencies are an essential input to the analysis process of a nuclear power plant probabilistic risk assessment. These frequencies describe events causing or requiring scrams. This report documents an effort to validate and update from other sources a computer-based data file developed by the Electric Power Research Institute (EPRI) describing such events at 52 United States commercial nuclear power plants. Operating information from the United States Nuclear Regulatory Commission on 24 additional plants from their date of commercial operation has been combined with the EPRI data, and the entire data base has been updated to add 1980 through 1983 events for all 76 plants. The validity of the EPRI data and data analysis methodology and the adequacy of the EPRI transient categories are examined. New transient initiating event frequencies are derived from the expanded data base using the EPRI transient categories and data display methods. Upper bounds for these frequencies are also provided. Additional analyses explore changes in the dominant transients, changes in transient outage times and their impact on plant operation, and the effects of power level and scheduled scrams on transient event frequencies. A more rigorous data analysis methodology is developed to encourage further refinement of the transient initiating event frequencies derived herein. Updating the transient event data base resulted in approx.2400 events being added to EPRI's approx.3000-event data file. The resulting frequency estimates were in most cases lower than those reported by EPRI, but no significant order-of-magnitude changes were noted. The average number of transients per year for the combined data base is 8.5 for pressurized water reactors and 7.4 for boiling water reactors.

  15. Electric G-Van demonstration and commercial assessment project

    Energy Technology Data Exchange (ETDEWEB)

    Braga, B.D. (Electric Power Research Inst., Palo Alto, CA (United States))

    1992-12-01

    The Electric Power Research Institute was awarded this grant to continue the joint effort initiated by EPRI, and VE International to proceed beyond the prototype phase of the electric G-Van development. The goal of EPRI and VEHMA was to develop a market for the electric G-Van, and to distribute them to commercial fleet operators. The objective of this project was to produce G-Vans in a production facility that would be comparable to the GMC Truck internal combustion engine Vandura Van produced by General Motors in quality, reliability, durability and safety. An initial market assessment/demonstration phase of sixty (60) vehicles was to be undertaken, with the ability to expand production volume quickly to meet market demands. Brief description of each task of this grant is given and the actions taken by EPRI to complete them.

  16. An expert system technology for work authorization information systems

    International Nuclear Information System (INIS)

    Munchausen, J.H.; Glazer, K.A.

    1988-01-01

    This paper describes the effort by Southern California Edison Company (SCE) and the Electric Power Research Institute (EPRI) to develop an expert systems work station designed to support the San Onofre Nuclear Generating Station (SONGS). The expert systems work station utilizes IntelliCorp KEE (Knowledge Engineering Environment) and EPRI-IntelliCorp PLEXSYS (PLant EXpert SYStem) technology, and SCE Piping and Instrumentation Diagrams (P and ID's) and host-based computer applications to assist plant operations and maintenance personnel in the development of safety tagout boundaries. Of significance in this venture is the merging of conventional computer applications technology with expert systems technology. The EPRI PLEXSYS work station will act as a front-end for the SONGS Tagout Administration and Generation System (TAGS), a conventional CICS/COBOL mainframe computer application

  17. Study on calculation of influence function with fracture mechanics analysis method for circumferential through-crack pipe

    International Nuclear Information System (INIS)

    Zheng Bin; Lu Yuechuan; Zang Fenggang; Sun Yingxue

    2009-01-01

    In order to widen the application of the engineering method of EPRI, with a series of analysis on the 3D elastic and elastic-plastic fracture mechanics finite element, the crack open displacements (COD) of cracked pipe were calculated and a key influence function h 2 in EPRI engineering method was studied against the COD results of FEM. A calculation method of h2 under the condition of tension and bending combined load was introduced in detail. In order to validate this method, the calculated h 2 results were compared with that of EPRI, and the calculated COD results based on the h 2 results were compared with that of PICEP. The compared results indicated that the calculated h 2 results as well as the COD results and the corresponding reference values were respectively accordant, and the calculation method in this paper was validated accordingly. (authors)

  18. High-temperature performance of a new nickel-based filler metal for power generation application

    Energy Technology Data Exchange (ETDEWEB)

    Shingledecker, J.; Coleman, K. [Electric Power Research Institute, Charlotte, NC (United States); Siefert, J.; Tanzosh, J. [Babcok and Wilcox Research Center, Barberton, OH (United States); Newell, W. [Euroweld, Mooresville, NC (United States)

    2010-07-01

    A new nickel-based weld filler metal, EPRI P87, has been developed as a superior alternative to ERNiCr-3 for use in dissimilar metal welds (DMW) between ferritic and austenitic materials. EPRI P87 has a low coefficient of thermal expansion more closely matching alloys such as Grade 91 and 92 than other available filler metals. Additionally, the size of the carbon denuded region adjacent to the weld in the heat-affected-zone is minimized/eliminated by proper control of weld metal composition. In this work the high-temperature mechanical behavior of DMWs utilizing EPRI P87 (GTAW and GMAW processes) was characterized through tensile and long-term creep-rupture testing. Microstructure analysis was also conducted on tested specimens to evaluate the HAZ regions and failure modes. Performance of the weld metal and welded joints is discussed and compared with ERNiCr-3 and typical 9%Cr-MoV filler metals. (orig.)

  19. Strategies for achieving a sustainable, clean and cost-effective biomass resource

    International Nuclear Information System (INIS)

    Turnbull, J.

    1993-01-01

    Biomass produced in an economically and environmentally sustainable manner, could realistically be used to supply 50,000 MW (5 Quads) of electric capacity by the year 2010 and probably twice that amount by the year 2030. During the past year, the Electric Power Research Institute (EPRI) and the U.S. Department of Energy (DOE) have each been independently evaluating the potential for biomass to become a major renewable energy resource over the next four decades, able to offset some of the U.S. dependency on imported fossil fuels while also offering important environmental and economic benefits. This paper presents EPRI's conclusions, which are more conservative than those of DOE, and outlines possible strategies by which EPRI can advance acceptance of biomass as a preferred renewable resource

  20. U.S. program to develop superconducting magnetic energy storage

    International Nuclear Information System (INIS)

    Schoenung, S.M.; Hassenzahl, W.V.; Filios, P.G.

    1988-01-01

    The United States Government, along with the Electric Power Research Institute (EPRI), has initiated a program to develop Superconducting Magnetic Energy Storage (SMES). This program is designed to answer questions of technical and economic viability by the mid-1990s, thereby paving the way to commercialization. EPRI has supported this technology since 1981 and is interested in its potential use in diurnal electric load-leveling. The U.S. Government has an additional interest in the potential of SMES to power ground-based lasers for Strategic Defense purposes. This paper presents a brief description of SMES technology, a review of the programmatic aspects of the ongoing program, including EPRI and DoD objectives, critical issues, and program milestones. The potential impact of high temperature superconductors on SMES is also discussed

  1. Use of advanced inspection technology during the ISI of a US-RPV

    Energy Technology Data Exchange (ETDEWEB)

    Buxbaum, S R; Pond, R B [Baltimore Gas and Electric Co., MD (United States); Stone, R M

    1988-12-31

    The Reactor Pressure Vessel (RPV) maintains a unique place among nuclear steam supply system components because its failure is unacceptable. The assumption of incredibility of vessel failure is a US Nuclear Regulatory Commission (USNRC) requirement of plant design and operation. Therefore, accurate detection and characterization of vessel flaws are essential. In order to meet the needs for improved pressure vessel inspection, EPRI assisted in the development of the Ultrasonic Data Recording and Processing System (UDRPS). The EPRI NDE Center has supported the transfer to industry through demonstration and documentation of the original system capability and by assisting utilities in their initial applications. Baltimore Gas and Electric (BG and E) purchased a second generation UDRPS and has used the system during the 10 year ISI at the Calvert Cliffs Nuclear Plant, Units 1 and 2. This presentation deals with the BG and E applications and the EPRI NDE Center support provided before and during the Calvert Cliffs ISI applications. (author).

  2. In search of cost-effective, reliable software

    International Nuclear Information System (INIS)

    Naser, J.A.; Bhatt, S.C.

    1992-01-01

    Considerable effort is ongoing to utilize the strengths of digital technology to upgrade and add functionality to existing systems and to develop solutions to problems in the nuclear industry. Acceptance of digital solutions requires verification and validation activities to ensure the reliability and acceptance of these solutions. EPRI has an ongoing effort to develop a methodology for verification and validation of digital control systems. Also, a joint project between the NRC and EPRI is developing a methodology for expert system verification and validation. To obtain a wider acceptance of digital system solutions and hence the utilization of verification and validation techniques, cost effective methods for design, development and verification and validation are needed. EPRI is leading an effort to develop methods for cost effective verification and validation for all types of software

  3. Maintainability effectiveness evaluations and enhancement

    International Nuclear Information System (INIS)

    Seminara, J.L.

    1985-01-01

    In the mid-seventies EPRI initiated a research project to review the human factors aspects of nuclear power plant control rooms. In the course of investigating operator-control room interfaces in five operational control rooms, it became evident that many plant outages had either been caused or prolonged by human factors problems associated with maintenance activities. Consequently, as one of several follow-on projects, EPRI sponsored a review of nine power plants (five nuclear and four fossil) to examine the human factors aspects of plant maintainability. This survey revealed a wide variety of generic human factors problems that could negatively impact the effectiveness of plant maintenance personnel. It was clear that plant maintainability features deserved no less attention to human factors concerns than the operational features of the control room. This paper describes subsequent EPRI-initiated efforts to assist the utilities in conducting self-reviews of maintainability effectiveness and effect needed enhancements

  4. Effects of respirator use on worker performance

    Energy Technology Data Exchange (ETDEWEB)

    Cardarelli, R. [Yankee Atomic Electric Co., Bolton, MA (United States)

    1995-03-01

    In 1993, EPRI funded Yankee Atomic Electric Company to examine the effects of respirator use on worker efficiency. Phase I of Yankee`s effort was to develop a study design to determine respirator effects. Given success in Phase I, a larger population will be tested to determine if a stasitically significant respirator effect on performance can be measured. This paper summarizes the 1993 EPRI/Yankee Respirator Effects of Pilot Study, and describes the study design for the 1994 EPRI/Yankee Respirator Study to be conducted at the Oyster Creek Nuclear Power Plant. Also described is a summary of respirator effect studies that have been conducted during the last ten (10) years.

  5. Evaluation of J-integral estimation scheme for flawed throughwall pipes

    Energy Technology Data Exchange (ETDEWEB)

    Zahoor, A.

    1987-02-01

    The accuracy of the EPRI J-integral estimation scheme for pipes with throughwall cracks and subjected to pure bending was assessed using available experimental data on circumferentially flawed throughwall pipes. The evaluations were performed using elastic plastic J-integral (J) and tearing modulus (T) analysis methods. The results indicated that the EPRI J estimation scheme solutions are unnecessarily conservative compared to results from pipe experiments. As a result of these evaluations an improved J estimation scheme is developed, which is shown to have improved accuracy compared to the original EPRI J estimation scheme. These results imply that the flaw evaluation procedures in the ASME Code on austenitic piping welds are conservative. These results also have applications to the leak before break fracture mechanics analyses.

  6. Evaluation of J-integral estimation scheme for flawed throughwall pipes

    International Nuclear Information System (INIS)

    Zahoor, A.

    1987-01-01

    The accuracy of the EPRI J-integral estimation scheme for pipes with throughwall cracks and subjected to pure bending was assessed using available experimental data on circumferentially flawed throughwall pipes. The evaluations were performed using elastic plastic J-integral (J) and tearing modulus (T) analysis methods. The results indicated that the EPRI J estimation scheme solutions are unnecessarily conservative compared to results from pipe experiments. As a result of these evaluations an improved J estimation scheme is developed, which is shown to have improved accuracy compared to the original EPRI J estimation scheme. These results imply that the flaw evaluation procedures in the ASME Code on austenitic piping welds are conservative. These results also have applications to the leak before break fracture mechanics analyses. (orig.)

  7. Digest of current research in the electric-utility industry. Volume 1. Categories 1-5

    International Nuclear Information System (INIS)

    Andrews, K.; Bates, P.; Berkey, R.; Gray, K.; Kindt, C.; O'Gara, M.; Pakulski, R.

    1980-01-01

    The major objective of the Electric Power Research Institute (EPRI) is to be a prime source of information of R and D activities in the field of electric energy. Therefore, EPRI developed the Research and Development Information System (RDIS) which is a computerized data base of research projects sponsored by EPRI and by individual electric utilities throughout the US. The heart of RDIS is a computerized on-line data base containing approximately 7200 records of R and D projects. The data base is organized into 13 major categories: General R and D support, hydroelectric power, nuclear power, fossil fuels, advanced power systems, transmission, distribution, stations and substations, consumer utilization, economics, personnel, area development, and environmental assessment. This issue of the Digest of Current Research, issued annually and published in two volumes, represents the data base as of August 1980. This volume covers categories 1 through 5. Subject and corporate indexes are included

  8. Digest of current research in the electric-utility industry. Volume 2. Categories 6-13

    International Nuclear Information System (INIS)

    Andrews, K.; Bates, P.; Berkey, R.; Gray, K.; Kindt, C.; O'Gara, M.; Pakulski, R.

    1980-01-01

    The major objective of the Electric Power Research Institute (EPRI) is to be a prime source of information of R and D activities in the field of electric energy. Therefore, EPRI developed the Research and Development Information System (RDIS) which is a computerized data base of research projects sponsored by EPRI and by individual electric utilities throughout the US. The heart of RDIS is a computerized on-line data base containing approximately 7200 records of R and D projects. The data base is organized into 13 major categories: General R and D Support, hydroelectric power, nuclear power, fossil fuels, advanced power systems, transmission, distribution, stations and substations, consumer utilization, economics, personnel, area development, and environmental assessment. This issue of the Digest of Current Research, issued annually and published in two volumes represents the data base as of August 1980. This volume covers categories 6 through 13. Subject and corporate indexes are included

  9. Experimental determination of the radial dose distribution in high gradient regions around 192Ir wires: Comparison of electron paramagnetic resonance imaging, films, and Monte Carlo simulations

    International Nuclear Information System (INIS)

    Kolbun, N.; Leveque, Ph.; Abboud, F.; Bol, A.; Vynckier, S.; Gallez, B.

    2010-01-01

    Purpose: The experimental determination of doses at proximal distances from radioactive sources is difficult because of the steepness of the dose gradient. The goal of this study was to determine the relative radial dose distribution for a low dose rate 192 Ir wire source using electron paramagnetic resonance imaging (EPRI) and to compare the results to those obtained using Gafchromic EBT film dosimetry and Monte Carlo (MC) simulations. Methods: Lithium formate and ammonium formate were chosen as the EPR dosimetric materials and were used to form cylindrical phantoms. The dose distribution of the stable radiation-induced free radicals in the lithium formate and ammonium formate phantoms was assessed by EPRI. EBT films were also inserted inside in ammonium formate phantoms for comparison. MC simulation was performed using the MCNP4C2 software code. Results: The radical signal in irradiated ammonium formate is contained in a single narrow EPR line, with an EPR peak-to-peak linewidth narrower than that of lithium formate (∼0.64 and 1.4 mT, respectively). The spatial resolution of EPR images was enhanced by a factor of 2.3 using ammonium formate compared to lithium formate because its linewidth is about 0.75 mT narrower than that of lithium formate. The EPRI results were consistent to within 1% with those of Gafchromic EBT films and MC simulations at distances from 1.0 to 2.9 mm. The radial dose values obtained by EPRI were about 4% lower at distances from 2.9 to 4.0 mm than those determined by MC simulation and EBT film dosimetry. Conclusions: Ammonium formate is a suitable material under certain conditions for use in brachytherapy dosimetry using EPRI. In this study, the authors demonstrated that the EPRI technique allows the estimation of the relative radial dose distribution at short distances for a 192 Ir wire source.

  10. Corrosion control in electric power plants

    International Nuclear Information System (INIS)

    Syrett, B.C.

    1992-01-01

    This paper reports that corrosion of components in power plants costs the US electric power utility industry billions of dollars each year. Through the Electric Power Research Institute's (EPRI) research and development, several approaches have been developed to reduce these huge costs. They include improved materials selection procedures, coatings, cathodic protection, inhibitors, removal of aggressive species from the environment, and on-line corrosion monitoring. In addition, as part of an on-going technology transfer effort, EPRI is developing databases and expert systems that will help utilities obtain corrosion information and guide them in materials selection and failure analysis

  11. New advances in human reliability using the EPRIHRA calculator

    International Nuclear Information System (INIS)

    Julius, J. A.; Grobbelaar, J. F.

    2006-01-01

    This paper describes new advances in human reliability associated with the integration of HRA methods, lessons learned during the first few years of operation of the EPRI HRA / PRA Tools Users Group, and application of human reliability techniques in areas beyond the more traditional Level 1 internal events PRA. This paper is organized as follows. 1. EPRI HRA Users Group Overview (mission, membership, activities, approach) 2. HRA Methods Currently Used (selection, integration, and addressing dependencies) 3. New Advances in HRA Methods 4. Conclusions. (authors)

  12. The impact of seismically-induced relay chatter on nuclear plant risk

    International Nuclear Information System (INIS)

    Bley, D.C.; McIntyre, T.J.; Smith, B.; Kassawara, R.P.

    1987-01-01

    This paper describes a systematic scheme for analyzing the impact of relay chatter that is amenable to both PRA analysis and seismic margins analysis. It uses knowledge of the systems engineering of the plant to bound the scope of the problem to a tractable size and has been applied to both the Diablo Canyon PRA and the EPRI seismic margines program trial evaluation at the Catawba Nuclear Power Plant. It has also been coordinated with similar EPRI-sponsored work on relay functionality for the Seismic Qualification Utility Group. (orig./HP)

  13. Handy help for maintenance workers

    International Nuclear Information System (INIS)

    Moore, T.

    1994-01-01

    Lightweight, low-cost, color-coded job cards packed with technical reference information and geared to specific types of maintenance and troubleshooting efficiency in nuclear as well as other types of power plants. Developed in conjunction with EPRI's counterpart in Japan, job card sets have been pilot-tested at two operating U.S. nuclear plants and are also being evaluated by Japanese utilities. In addition to their potential for utility customization, job cards could become a new line of EPRI information product that is used directly by the people who inspect and repair equipment in utility power plants

  14. Evaluation of PWR and BWR pin cell benchmark results

    International Nuclear Information System (INIS)

    Pijlgroms, B.J.; Gruppelaar, H.; Janssen, A.J.; Hoogenboom, J.E.; Leege, P.F.A. de; Voet, J. van der; Verhagen, F.C.M.

    1991-12-01

    Benchmark results of the Dutch PINK working group on PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs., 9 figs., 30 tabs

  15. Evaluation of PWR and BWR pin cell benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Pijlgroms, B.J.; Gruppelaar, H.; Janssen, A.J. (Netherlands Energy Research Foundation (ECN), Petten (Netherlands)); Hoogenboom, J.E.; Leege, P.F.A. de (Interuniversitair Reactor Inst., Delft (Netherlands)); Voet, J. van der (Gemeenschappelijke Kernenergiecentrale Nederland NV, Dodewaard (Netherlands)); Verhagen, F.C.M. (Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands))

    1991-12-01

    Benchmark results of the Dutch PINK working group on PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs., 9 figs., 30 tabs.

  16. Workshop on sulfur chemistry in flue gas desulfurization

    Energy Technology Data Exchange (ETDEWEB)

    Wallace, W.E. Jr.

    1980-05-01

    The Flue Gas Desulfurization Workshop was held at Morgantown, West Virginia, June 7-8, 1979. The presentations dealt with the chemistry of sulfur and calcium compounds in scrubbers. DOE and EPRI programs in this area are described. Ten papers have been entered individually into EDB and ERA. (LTN)

  17. Recommendations of the MRP-139: Inspection of Welds dissimilar in Nozzles PWR reactor vessel in Spain

    International Nuclear Information System (INIS)

    Gadea, J. R.; Willke, A.; Regidor, J. J.; Tecnatom, S. A.

    2010-01-01

    The guide EPRI MRP-139, which provides the way forward for the inspection and evaluation of dissimilar butt welds, the primary system of PWR reactors, indicating the type of nondestructive testing to be done in these areas, based on discovered several cases of default in lnconel alloys 600 and 182 in American and European plants. The phenomenon of cracking.

  18. Dancing with the Electrons: Time-Domain and CW In Vivo EPR Imaging

    Directory of Open Access Journals (Sweden)

    Murali C. Krishna

    2008-01-01

    Full Text Available The progress in the development of imaging the distribution of unpaired electrons in living systems and the functional and the potential diagnostic dimensions of such an imaging process, using Electron Paramagnetic Resonance Imaging (EPRI, is traced from its origins with emphasis on our own work. The importance of EPR imaging stems from the fact that many paramagnetic probes show oxygen dependent spectral broadening. Assessment of in vivo oxygen concentration is an important factor in radiation oncology in treatment-planning and monitoring treatment-outcome. The emergence of narrow-line trairylmethyl based, bio-compatible spin probes has enabled the development of radiofrequency time-domain EPRI. Spectral information in time-domain EPRI can be achieved by generating a time sequence of T2* or T2 weighted images. Progress in CW imaging has led to the use of rotating gradients, more recently rapid scan with direct detection, and a combination of all the three. Very low field MRI employing Dynamic Nuclear polarization (Overhauser effect is also employed for monitoring tumor hypoxia, and re-oxygenation in vivo. We have also been working on the co-registration of MRI and time domain EPRI on mouse tumor models at 300 MHz using a specially designed resonator assembly. The mapping of the unpaired electron distribution and unraveling the spectral characteristics by using magnetic resonance in presence of stationary and rotating gradients in indeed ‘dancing with the (unpaired electrons’, metaphorically speaking.

  19. Characterization of Melanin Radicals in Paraffin-embedded Malignant Melanoma and Nevus Pigmentosus Using X-band EPR and EPR Imaging.

    Science.gov (United States)

    Nakagawa, Kouichi; Minakawa, Satoko; Sawamura, Daisuke; Hara, Hideyuki

    2017-01-01

    Continuous wave electron paramagnetic resonance (CW EPR) and X-band (9 GHz) EPR imaging (EPRI) were used to nondestructively investigate the possible differentiation between malignant melanoma (MM) and nevus pigmentosus (NP) melanin radicals in paraffin-embedded specimens. The EPR spectra of both samples were analyzed using linewidth, spectral pattern, and X-band EPRI. The CW-EPR spectra of the MM showed an additional signal overlap. Eumelanin- and pheomelanin-related radicals were observed in the MM specimens. The EPR results revealed that the peak-to-peak linewidths (ΔH pp ) of paraffin-embedded MM and NP samples were 0.65 ± 0.01 and 0.69 ± 0.01 mT, respectively. The g-value was 2.005 for both samples. Moreover, the two-dimensional (2D) EPRI of the MM showed different signal intensities at the different tumor stages, unlike the NP, which displayed fewer variations in signal intensity. Thus, the present results suggest that EPR and 2D EPRI can be useful for characterization of the two melanin radicals in the MM and for determination of their size and concentration.

  20. 78 FR 18817 - Revisions to Reliability Standard for Transmission Vegetation Management

    Science.gov (United States)

    2013-03-28

    ... used in the technical reference paper [Exh. A of NERC's petition].'' \\25\\ \\24\\ NERC Petition, Ex. I... set by Institute of Electric and Electronics Engineers (IEEE) Standard 516 that, as indicated in Order... Power Research Institute (EPRI) is planning to undertake field tests of energized high voltage conductor...

  1. Joint utility task group CGI data-base procurement history module

    International Nuclear Information System (INIS)

    Rosch, F.

    1993-01-01

    The purpose of the procurement history record module of the Joint Utility Task Group's (JUTG's) commercial-grade item (CGI) data base is to assist utilities to cost effectively implement the dedication methodology provided in the Electric Power Research Institute's (EPRI's) report NP-5652, open-quotes Guidelines for the Utilization of Commercial Grade Items in Nuclear Safety-Related Applications.close quotes

  2. Status of the TMI SOFC system

    Energy Technology Data Exchange (ETDEWEB)

    Ruhl, R.C.; Petrik, M.A.; Cable, T.L. [Technology Management, Inc., Cleveland, OH (United States)

    1996-12-31

    TMI has completed preliminary engineering designs for complete 20kW SOFC systems modules for stationary distributed generation applications using pipeline natural gas [sponsored by Rochester Gas and Electric (Rochester, New York) and EPRI (Palo Alto, California)]. Subsystem concepts are currently being tested.

  3. ATWS: a reappraisal. Part 3. Frequency of anticipated transients

    International Nuclear Information System (INIS)

    McClymont, A.S.; Poehlman, B.W.

    1982-01-01

    This document is the first revision of Part 3 of the EPRI study of the anticipated transients without scram question. This revision includes an update of events at nuclear power plants which had led to fast reactor shutdowns (scrams). The purpose of this document is to present the nuclear power plant operating experience, reflecting the frequency of these events identified by their principal characteristics

  4. 77 FR 9273 - WORKSHOP Sponsored by the Nuclear Regulatory Commission and the Electric Power Research Institute...

    Science.gov (United States)

    2012-02-16

    ... Commission and the Electric Power Research Institute on the Treatment of Probabilistic Risk Assessment.... SUMMARY: The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research (RES), in cooperation with the Electric Power Research Institute (EPRI), will hold a joint workshop on the Treatment of...

  5. Radiolytic model of CN Cofrentes using BWRVIA: analysis of the effectiveness of mitigation in locations of the vessel with application of noble metal son-line; Modelo radiolitico de C. N: Cofrentes utilizando el BWRVIA: analisis de la efectividad de mitigacion en localizaciones de la vasija con aplicacion de metales nobles on-line

    Energy Technology Data Exchange (ETDEWEB)

    Martin-Serrano Ledesma, C.; Sanchez Zapata, J. D.

    2012-07-01

    The effectiveness of mitigation is found from two chemical parameters: electrochemical potential (pm-a hydrogen injection) and Molar Ratio (for the application of noble metals). EPRI code exists, the BWRVIA (BWR Vessel Internals Application,) which enables setting model the impact radiolysis of water, the balance of liquid-vapor phase and recirculation have on the chemical variation of these parameters.

  6. Proceedings: 2001 Nuclear Asset Management Workshop

    International Nuclear Information System (INIS)

    2002-01-01

    The fourth annual EPRI Nuclear Asset Management Workshop helped decision makers at all levels of nuclear enterprises to keep informed about developing nuclear asset management (NAM) processes, methods, and tools. The goal is to operate nuclear plants with enhanced profitability, while maintaining safety

  7. Dancing with the Electrons: Time-Domain and CW EPR Imaging

    Directory of Open Access Journals (Sweden)

    Sankaran Subramanian

    2008-01-01

    Full Text Available The progress in the development of imaging the distribution of unpaired electrons in living systems and the functional and the potential diagnostic dimensions of such an imaging process, using Electron Paramagnetic Resonance Imaging (EPRI, is traced from its origins with emphasis on our own work. The importance of EPR imaging stems from the fact that many paramagnetic probes show oxygen dependent spectral broadening. Assessment of in vivo oxygen concentration is an important factor in radiation oncology in treatment-planning and monitoring treatment-outcome. The emergence of narrow-line trairylmethyl based, bio-compatible spin probes has enabled the development of radiofrequency time-domain EPRI. Spectral information in time-domain EPRI can be achieved by generating a time sequence of T 2 * or T 2 weighted images. Progress in CW imaging has led to the use of rotating gradients, more recently rapid scan with direct detection, and a combination of all the three. Very low field MRI employing Dynamic Nuclear polarization (Overhauser effect is also employed for monitoring tumor hypoxia, and re-oxygenation in vivo . We have also been working on the co-registration of MRI and time domain EPRI on mouse tumor models at 300 MHz using a specially designed resonator assembly. The mapping of the unpaired electron distribution and unraveling the spectral characteristics by using magnetic resonance in presence of stationary and rotating gradients in indeed ‘dancing with the ( unpaired electrons’, metaphorically speaking.

  8. Rule-based emergency action level monitor prototype

    International Nuclear Information System (INIS)

    Touchton, R.A.; Gunter, A.D.; Cain, D.

    1985-01-01

    In late 1983, the Electric Power Research Institute (EPRI) began a program to encourage and stimulate the development of artificial intelligence (AI) applications for the nuclear industry. Development of a rule-based emergency action level classification system prototype is discussed. The paper describes both the full prototype currently under development and the completed, simplified prototype

  9. Reactor systems modeling for ICF hybrids

    International Nuclear Information System (INIS)

    Berwald, D.H.; Meier, W.R.

    1980-10-01

    The computational models of ICF reactor subsystems developed by LLNL and TRW are described and a computer program was incorporated for use in the EPRI-sponsored Feasibility Assessment of Fusion-Fission Hybrids. Representative parametric variations have been examined. Many of the ICF subsystem models are very preliminary and more quantitative models need to be developed and included in the code

  10. Trial application of guidelines for nuclear plant response to an earthquake

    International Nuclear Information System (INIS)

    Schmidt, W.; Oliver, R.; O'Connor, W.

    1993-09-01

    Guidelines have been developed to assist nuclear plant personnel in the preparation of earthquake response procedures for nuclear power plants. These guidelines are published in EPRI report NP-6695, ''Guidelines for Nuclear Plant Response to an Earthquake,'' dated December 1989. This report includes two sets of nuclear plant procedures which were prepared to implement the guidelines of EPRI report NP-6695. The first set were developed by the Toledo Edison Company Davis-Besse plant. Davis-Besse is a pressurized water reactor (PWR) and contains relatively standard seismic monitoring instrumentation typical of many domestic nuclear plants. The second set of procedures were prepared by Yankee Atomic Electric Company for the Vermont Yankee facility. This plant is a boiling water reactor (BWR) with state-of-the-art seismic monitoring and PC-based data processing equipment, software developed specifically to implement the OBE Exceedance Criterion presented in EPRI report NP-5930, ''A Criterion for Determining Exceedance of the operating Basis Earthquake.'' The two sets of procedures are intended to demonstrate how two different nuclear utilities have interpreted and applied the EPRI guidance given in report NP-6695

  11. UC-B reflood experimental plan

    International Nuclear Information System (INIS)

    Yu, K.P.; Abdollahian, D.; Peake, W.T.; Elias, E.; Yadigaroglu, G.; Greif, R.

    1977-04-01

    The EPRI sponsored single tube reflooding heat transfer facility is described. The facility is located at the University of California, Berkeley. The physical systems which constitute the facility as well as the objectives and background of the program are described. The steam-water separator is described in detail Finally, the operating procedure and the test apparatus performance are discussed

  12. Proceedings: Radiation Protection Technology Conference: Providence, RI, November 2001

    International Nuclear Information System (INIS)

    2002-01-01

    Health physics (HP) professionals within the nuclear industry are continually upgrading their respective programs with new methods and technologies. The move to shorter outages combined with a diminishing group of contract HP technicians and demanding emergent work makes such changes even more important. The EPRI Radiation Protection Technology Conference focused on a number of key health physics issues and developments

  13. Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report

    International Nuclear Information System (INIS)

    Johansen, R.

    2011-01-01

    Summary report for Fiscal Year 2011 activities associated with the Constellation Pilot Project. The project is a joint effor between Constellation Nuclear Energy Group (CENG), EPRI, and the DOE Light Water Reactor Sustainability Program. The project utilizes two CENG reactor stations: R.E. Ginna and Nine Point Unit 1. Included in the report are activities associate with reactor internals and concrete containments.

  14. "Fish Friendly" Hydropower Turbine Development and Deployment. Alden Turbine Preliminary Engineering and Model Testing

    Energy Technology Data Exchange (ETDEWEB)

    Dixon, D. [Electric Power Research Institute, Palo Alto, CA (United States)

    2011-10-01

    This report presents the results of a collaborative research project funded by the Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and hydropower industry partners with the objective of completing the remaining developmental engineering required for a “fish-friendly” hydropower turbine called the Alden turbine.

  15. IMAGE information monitoring and applied graphics software environment. Volume 2. Software description

    International Nuclear Information System (INIS)

    Hallam, J.W.; Ng, K.B.; Upham, G.L.

    1986-09-01

    The EPRI Information Monitoring and Applied Graphics Environment (IMAGE) system is designed for 'fast proto-typing' of advanced concepts for computer-aided plant operations tools. It is a flexible software system which can be used for rapidly creating, dynamically driving and evaluating advanced operator aid displays. The software is written to be both host computer and graphic device independent

  16. Energy Systems Integration: Demonstrating Distributed Resource Communications

    Energy Technology Data Exchange (ETDEWEB)

    2017-01-01

    Overview fact sheet about the Electric Power Research Institute (EPRI) and Schneider Electric Integrated Network Testbed for Energy Grid Research and Technology Experimentation (INTEGRATE) project at the Energy Systems Integration Facility. INTEGRATE is part of the U.S. Department of Energy's Grid Modernization Initiative.

  17. Magnetic energy transfer and storage

    International Nuclear Information System (INIS)

    Blevins, D.J.; Haarman, R.A.; Hoffman, C.G.

    1976-01-01

    Brief discussions are given for the following research topics: (1) HVDC interrupter tests, (2) 300-kJ test facilities, (3) superconducting wire development, (4) coil development program, (5) SFTR prototype METS system, (6) SFTR conceptual design study, (7) dielectric strength and voltage tracking studies, and (8) EPRI homopolar study contract

  18. Data needs for common cause failure analysis

    International Nuclear Information System (INIS)

    Parry, G.W.; Paula, H.M.; Rasmuson, D.; Whitehead, D.

    1990-01-01

    The procedures guide for common cause failure analysis published jointly by USNRC and EPRI requires a detailed historical event analysis. Recent work on the further development of the cause-defense picture of common cause failures introduced in that guide identified the information that is necessary to perform the detailed analysis in an objective manner. This paper summarizes these information needs

  19. Tube problems: worldwide statistics reviewed

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    EPRI's Steam Generator Strategic Management Project issues an annual report on the progress being made in tackling steam generator problems worldwide, containing a wealth of detailed statistics on the status of operating units and degradation mechanisms encountered. A few highlights are presented from the latest report, issued in October 1993, which covers the period to 31 December 1992. (Author)

  20. Tension tests of concrete containment wall elements

    International Nuclear Information System (INIS)

    Schultz, D.M.; Julien, J.T.; Russel, H.G.

    1984-01-01

    Tension tests of concrete containment wall elements were conducted as part of a three-phase research program sponsored by the Electric Power Research Institute (EPRI). The objective of the EPRI experimental/analytical program is twofold. The first objective is to provide the utility industry with a test-verified analytical method for making realistic estimates of actual capacities of reinforced and prestressed concrete containments under internal over-pressurization from postulated degraded core accidents. The second objective is to determine qualitative and quantitative leak rate characteristics of typical containment cross-sections with and without penetrations. This paper covers the experimental portion to the EPRI program. The testing program for Phase 1 included eight large-scale specimens representing elements from the wall of a containment. Each specimen was 60-in (1525-mm) square, 24-in (610-mm) thick, and had full-size reinforcing bars. Six specimens were representative of prototypical reinforced concrete containment designs. The remaining two specimens represented prototypical prestressed containment designs. Various reinforcement configurations and loading arrangements resulted in data that permit comparisons of the effects of controlled variables on cracking and subsequent concrete/reinforcement/liner interaction in containment elements. Subtle differences, due to variations in reinforcement patterns and load applications among the eight specimens, are being used to benchmark the codes being developed in the analytical portion of the EPRI program. Phases 2 and 3 of the test program will examine leak rate characteristics and failure mechanisms at penetrations and structural discontinuities. (orig.)

  1. Why and how of fusion

    International Nuclear Information System (INIS)

    Miley, G.H.

    1977-01-01

    The potential advantages of fusion power are listed. The approaches to plasma containment are mentioned and the status of the fusion program is described. The ERDA and EPRI programs are discussed. The Fusion Energy Foundation's activities are mentioned. Fusion research at the U. of Ill. is described briefly

  2. Fire PRA requantification studies. Final report

    International Nuclear Information System (INIS)

    Parkinson, W.

    1993-03-01

    This report describes the requantification of two existing fire probabilistic risk assessments (PRAs) using a fire PRA method and data that are being developed by the Electric Power Research Institute (EPRI). The two existing studies are the Seabrook Station Probabilistic Safety Assessment that was made in 1983 and the 1989 NUREG-1150 analysis of the Peach Bottom Plant. Except for the fire methods and data, the original assumptions were used. The results from the requantification show that there were excessive conservatisms in the original studies. The principal reason for a hundredfold reduction in the Peach Bottom core- damage frequency is the determination that no electrical cabinet fire in a switchgear room would damage both offsite power feeds. Past studies often overestimated the heat release from electrical cabinet fires. EPRI's electrical cabinet heat release rates are based on tests that were conducted for Sandia's fire research program. The rates are supported by the experience in the EPRI Fire Events Database for U.S. nuclear plants. Test data and fire event experience also removed excessive conservatisms in the Peach Bottom control and cable spreading rooms, and the Seabrook primary component cooling pump, turbine building relay and cable spreading rooms. The EPRI fire PRA method and data will show that there are excessive conservatisms in studies that were made for many plants and can benefit them accordingly

  3. Monitored Natural Attenuation as a Remediation Strategy for Nuclear Power Plant Applications

    Science.gov (United States)

    Kim, K.; Bushart, S.

    2009-12-01

    A NRC Information Notice (IN 2006-13) was produced to inform holders of nuclear operating licenses “of the occurrence of radioactive contamination of ground water at multiple facilities due to undetected leakage from facility structures, systems, or components (SSCs) that contain or transport radioactive fluids” so that they could consider actions, as appropriate, to avoid similar problems. To reinforce their commitment to environmental stewardship the nuclear energy industry has committed to improving management of situations that have the potential to lead to the inadvertent release of radioactive fluids. This Industry Groundwater Protection Initiative, finalized in June 2007 as [NEI 07-07], calls for implementation and improvement of on-site groundwater monitoring programs and enhanced communications with stakeholders and regulators about situations related to inadvertent releases. EPRI developed its Groundwater Protection Program to provide the nuclear energy industry with the technical support needed to implement the Industry Groundwater Initiative. An objective of the EPRI Groundwater Protection Program is to provide the nuclear industry with technically sound guidance for implementing and enhancing on-site groundwater monitoring programs. EPRI, in collaboration with the EPRI Groundwater Protection Committee of utility members, developed the EPRI Groundwater Protection Guidelines for Nuclear Power Plants (EPRI Report 1015118, November 2007), which provides site-specific guidance for implementing a technically sound groundwater monitoring program. The guidance applies a graded approach for nuclear plants to tailor a technically effective and cost efficient groundwater monitoring program to the site’s hydrogeology and risk for groundwater contamination. As part of the Groundwater Protection Program, EPRI is also investigating innovative remediation technologies for addressing low-level radioactive contamination in soils and groundwater at nuclear power

  4. Estimation of core-damage frequency to evolutionary ALWR [advanced light water reactor] due to seismic initiating events: Task 4.3.3

    International Nuclear Information System (INIS)

    Brooks, R.D.; Harrison, D.G.; Summitt, R.L.

    1990-04-01

    The Electric Power Research Institute (EPRI) is presently developing a requirements document for the design of advanced light water reactors (ALWRs). One of the basic goals of the EPRI ALWR Requirements Document is that the core-damage frequency for an ALWR shall be less than 1.0E-5. To aid in this effort, the Department of Energy's Advanced Reactor Severe Accident Program (ARSAP) initiated a functional probabilistic risk assessment (PRA) to determine how effectively the evolutionary plant requirements contained in the existing EPRI Requirements Document assure that this safety goal will be met. This report develops an approximation of the core-damage frequency due to seismic events for both evolutionary plant designs (pressurized-water reactor (PWR) and boiling-water reactor(BWR)) as modeled in the corresponding functional PRAs. Component fragility values were taken directly form information which has been submitted for inclusion in Appendix A to Volume 1 of the EPRI Requirements Document. The results show a seismic core-damage frequency of 5.2E-6 for PWRS and 5.0E-6 for BWRs. Combined with the internal initiators from the functional PRAs, the overall core-damage frequencies are 6.0E-6 for the pwr and BWR, both of which satisfy the 1.0E-5 EPRI goal. In addition, site-specific considerations, such as more rigid components and less conservative fragility data and seismic hazard curves, may further reduce these frequencies. The effect of seismic events on structures are not addressed in this generic evaluation and should be addressed separately on a design-specific basis. 7 refs., 6 figs., 3 tabs

  5. UFD Storage and Transportation - Transportation Working Group Report

    International Nuclear Information System (INIS)

    Maheras, Steven J.; Ross, Steven B.

    2011-01-01

    The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during extended storage. The list of SSCs and the associated degradation mechanisms (known as features, events, and processes (FEPs)) were based on the list of used nuclear fuel (UNF) storage system SSCs and degradation mechanisms developed by the UFD Storage Task (Hanson et al. 2011). Other sources of information surveyed to develop the list of SSCs and their degradation mechanisms included references such as Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel (NWTRB 2010), Transportation, Aging and Disposal Canister System Performance Specification, Revision 1 (OCRWM 2008), Data Needs for Long-Term Storage of LWR Fuel (EPRI 1998), Technical Bases for Extended Dry Storage of Spent Nuclear Fuel (EPRI 2002), Used Fuel and High-Level Radioactive Waste Extended Storage Collaboration Program (EPRI 2010a), Industry Spent Fuel Storage Handbook (EPRI 2010b), and Transportation of Commercial Spent Nuclear Fuel, Issues Resolution (EPRI 2010c). SSCs include items such as the fuel, cladding, fuel baskets, neutron poisons, metal canisters, etc. Potential degradation mechanisms (FEPs) included mechanical, thermal, radiation and chemical stressors, such as fuel fragmentation, embrittlement of cladding by hydrogen, oxidation of cladding, metal fatigue, corrosion, etc. These degradation mechanisms are discussed in Section 2 of this report. The degradation mechanisms have been evaluated to determine if they would be influenced by extended storage or high burnup, the need for additional data, and their importance to transportation. These categories were used to identify the most significant transportation degradation mechanisms. As expected, for the most part, the

  6. Insights from Guideline for Performance of Internal Flooding Probabilistic Risk Assessment (IFPRA)

    International Nuclear Information System (INIS)

    Choi, Sun Yeong; Yang, Joo Eon

    2009-01-01

    An internal flooding (IF) risk assessment refers to the quantitative probabilistic safety assessment (PSA) treatment of flooding as a result of pipe and tank breaks inside the plants, as well as from other recognized flood sources. The industry consensus standard for Internal Events Probabilistic Risk Assessment (ASME-RA-Sb-2005) includes high-level and supporting technical requirements for developing internal flooding probabilistic risk assessment (IFPRA). This industry standard is endorsed in Regulatory Guide 1.200, Revision 1 as an acceptable approach for addressing the risk contribution from IF events for risk informed applications that require U.S. Nuclear Regulatory commission (NRC) approval. In 2006, EPRI published a draft report for IFPRA that addresses the requirements of the ASME PRA consensus standard and have made efforts to refine and update the final EPRI IFPRA guideline. Westinghouse has performed an IFPRA analysis for several nuclear power plants (NPPs), such as Watts Bar and Fort Calhoun, using the draft EPRI guidelines for development of an IFPRA. Proprietary methodologies have been developed to apply the EPRI guidelines. The objectives of the draft report for IFPRA guideline are to: · Provide guidance for PSA practitioners in the performance of the elements of a PRA associated with internal flooding events consistent with the current state of the art for internal flooding PRA · Provide guidance regarding acceptable approaches that is sufficient to meeting the requirements of the ASME PRA Standard associated with internal flooding · Incorporate lessons learned in the performance of internal flooding PRAs including those identified as pilot applications of earlier drafts of this procedures guide The purpose of this paper is to present a vision for domestic nuclear power plants' IFPRA by comparing the method of the draft EPRI guidelines with the existing IFPRA method for domestic NPPs

  7. Insights from Guideline for Performance of Internal Flooding Probabilistic Risk Assessment (IFPRA)

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Sun Yeong; Yang, Joo Eon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2009-10-15

    An internal flooding (IF) risk assessment refers to the quantitative probabilistic safety assessment (PSA) treatment of flooding as a result of pipe and tank breaks inside the plants, as well as from other recognized flood sources. The industry consensus standard for Internal Events Probabilistic Risk Assessment (ASME-RA-Sb-2005) includes high-level and supporting technical requirements for developing internal flooding probabilistic risk assessment (IFPRA). This industry standard is endorsed in Regulatory Guide 1.200, Revision 1 as an acceptable approach for addressing the risk contribution from IF events for risk informed applications that require U.S. Nuclear Regulatory commission (NRC) approval. In 2006, EPRI published a draft report for IFPRA that addresses the requirements of the ASME PRA consensus standard and have made efforts to refine and update the final EPRI IFPRA guideline. Westinghouse has performed an IFPRA analysis for several nuclear power plants (NPPs), such as Watts Bar and Fort Calhoun, using the draft EPRI guidelines for development of an IFPRA. Proprietary methodologies have been developed to apply the EPRI guidelines. The objectives of the draft report for IFPRA guideline are to: {center_dot} Provide guidance for PSA practitioners in the performance of the elements of a PRA associated with internal flooding events consistent with the current state of the art for internal flooding PRA {center_dot} Provide guidance regarding acceptable approaches that is sufficient to meeting the requirements of the ASME PRA Standard associated with internal flooding {center_dot} Incorporate lessons learned in the performance of internal flooding PRAs including those identified as pilot applications of earlier drafts of this procedures guide The purpose of this paper is to present a vision for domestic nuclear power plants' IFPRA by comparing the method of the draft EPRI guidelines with the existing IFPRA method for domestic NPPs.

  8. Application of online chemistry monitoring programs and technology

    International Nuclear Information System (INIS)

    Perkins, D.; Choi, S.; Haas, C.

    2010-01-01

    To fully understand the impact of chemistry changes, several plant parameters must be considered and reviewed with actual chemistry analyses and compared to plant operating parameters. In some cases, this requires the ability to rapidly correlate plant operational data with laboratory and chemistry data. An effective online monitoring system should be able to: Integrate and extract online data from the plant laboratory and operating information from various plant data sources continuously; Interrogate and extract laboratory data from manually entered data on predefined frequencies; Interact with multiple laboratories in multiple locations; Evaluate data against plant limits (calculated or static) and provide personnel with action level or notification of plant exceeding limits; and, Provide the ability to evaluate against a standard and site specific set of calculations. The nuclear power industry continues to refine and apply new technologies in an effort to notify operators of changes in chemical conditions, calculate complex high temperature results, and monitor system performance. EPRI developed software specifically focused on plant chemistry program optimization using power operation and shutdown data applied with plant equipment. This software evolved into the family of software referred to as EPRI ChemWorks™ applications. As technology changed and improved, the application of online monitoring was essential for plant personnel working offsite. These changes in technology prompted EPRI to the development of SMART ChemWorks™ using the EPRI ChemWorks™ plant chemistry simulator and MULTEQ applications as the backbone for these simulations and calculations. SMART ChemWorks™ is an online monitoring system that queries plant databases and continuously monitors plant and chemistry parameters. The system uses a real-time intelligence engine to perform virtual sensing, identify normal and off-normal conditions and compare in-line instrument output to grab

  9. Calculation of forces on reactor containment fan cooler piping

    International Nuclear Information System (INIS)

    Miller, J.S.; Ramsden, K.

    2004-01-01

    The purpose of this paper is to present the results of the Reactor Containment Fan Cooler (RCFC) system piping load calculations. These calculations are based on piping loads calculated using the EPRI methodology and RELAP5 to simulate the hydraulic behavior of the system. The RELAP5 generated loads were compared to loads calculated using the EPRI GL-96-06 methodology. This evaluation was based on a pressurized water reactor's RCFC coils thermal hydraulic behavior during a Loss of Offsite Power (LOOP) and a loss of coolant accident (LOCA). The RCFC consist of two banks of service water and chill water coils. There are 5 SX and 5 chill water coils per bank. Therefore, there are 4 RCFC units in the containment with 2 banks of coils per RCFC. Two Service water pumps provide coolant for the 4 RCFC units (8 banks total, 2 banks per RCFC unit and 2 RCFC units per pump). Following a LOOP/LOCA condition, the RCFC fans would coast down and upon being re-energized, would shift to low-speed operation. The fan coast down is anticipated to occur very rapidly due to the closure of the exhaust damper as a result of LOCA pressurization effects. The service water flow would also coast down and be restarted in approximately 43 seconds after the initiation of the event. The service water would drain from the RCFC coils during the pump shutdown and once the pumps restart, water is quickly forced into the RCFC coils causing hydraulic loading on the piping. Because of this scenario and the potential for over stressing the piping, an evaluation was performed by the utility using RELAP5 to assess the piping loads. Subsequent to the hydraulic loads being analyzed using RELAP5, EPRI through GL-96-06 provided another methodology to assess loads on the RCFC piping system. This paper presents the results of using the EPRI methodology and RELAP5 to perform thermal hydraulic load calculations. It is shown that both EPRI methodology and RELAP5 calculations can be used to generate hydraulic loads

  10. Benefits of Digital Equipment Generic Qualification Activities

    International Nuclear Information System (INIS)

    Thomas, James E.; Steiman, Samuel C.

    2002-01-01

    As a result of nuclear power plant instrumentation and control obsolescence issues, there have been numerous activities during recent years relating to the qualification of digital equipment. Some of these activities have been 'generic' in nature in that the qualification was not limited to plant specific applications, but was intended to cover a broad base of potential applications of the digital equipment. These generic qualifications have been funded by equipment manufacturers and by utility groups and organizations. The generic activities sponsored by the Electric Power Research Institute (EPRI) have been pilot projects for an overall generic qualification approach. The primary benefit resulting from the generic qualification work to date is that a number of digital platforms and digital devices are now available for use in various nuclear safety-related applications. Many of the tests and evaluations necessary to support plant specific applications have been completed. The amount of data and documentation that each utility must develop on a case by case basis has been significantly reduced. There are also a number of additional benefits resulting from these industry efforts. The challenges and difficulties in qualifying digital equipment for safety-related applications are now more clearly understood. EPRI has published a lessons learned document (EPRI Report 1001452, Generic Qualification of Commercial Grade Digital Devices: Lessons Learned from Initial Pilots, which covers several different qualification areas, including device selection, project planning, vendor surveys and design reviews, and electromagnetic compatibility (EMC) qualification. Application of the experience and lessons learned from the EPRI pilot activities should help reduce the effort and cost required for future qualification work. Most generic qualification activities for commercial equipment have been conducted using the approach of EPRI TR-106439, Guideline on Evaluation and Acceptance

  11. Tapping global expertise in coal technology

    Energy Technology Data Exchange (ETDEWEB)

    Shepard, M

    1986-01-01

    The basic technology of fossil-fuel-fired electricity generation has remained virtually the same for 30 years. To encourage the development of new coal technology for US utilities, EPRI has signed contracts with power equipment manufacturers from Europe, Japan and the USA. These firms will work cooperatively to demonstrate improved designs, materials and procedures in existing commercial plants and large-scale laboratory facilities. The manufacturers will focus on boilers, turbines, balance-of-plant components and retrofit applications, and will validate individual components in separate installations and develop equipment specifications. EPRI and its contractors will spend approximately 25 million dollars over the next 5 years on developing improved coal-fired plant. (6 refs.)

  12. Decision aid by fuzzy inference: a case study related to the problem of radioactive waste management

    International Nuclear Information System (INIS)

    Krunsch, P.; Fiordalisa, A.; Fortemps, Ph.

    1999-01-01

    This paper illustrates a fuzzy inference system (FIS) developed to assist the economic calculus in radioactive waste management (RWM). The extended time horizons and, in addition, the first-of-a-kind nature of many RWM systems induce large cost uncertainties in project funding. The traditional approach in economic calculus is to include contingency factors in basic cost estimates. A distinction is made between T-factors, used for technological uncertainties, and P-factors, used for project contingencies. In the particular case of nuclear projects, the Electric Power Research Institute (EPRI) has developed specific recommendations for defining both contingency factors. As a generalisation of the EPRI results, a new methodology using fuzzy inference rules is proposed. The inputs to the FIS are derived from the answers of experts regarding both the degrees of technological maturity and project advancement. Inferred T- and P-factors proposed by the FIS are given either as single estimates as possibility intervals. (authors)

  13. Study finds declining construction leadtimes for nukes being built

    International Nuclear Information System (INIS)

    Smock, R.

    1983-01-01

    A new Electric Power Research Institute (EPRI) study of 26 nuclear projects shows a decrease in the leadtime for nuclear plants under construction in contrast to the findings of other studies. The EPRI study plots construction leadtime against the year of construction permit issuance rather than the year of completion, and it eliminates management delays, physical plant differences, and management differences. The result is a two-part trendline reflecting the discontinuity of regulatory ratchet effects, which cause 50% of construction leadtime delay while labor material delivery problems account for 20% and deliberate delays 22% of leadtime delay. When allowance is made for deliberate delays, there is no growth in construction leadtime. There was no correlation of utility finances, the accuracy of load growth forecasts, or the state regulatory environment to the length of construction. 3 figures,

  14. Application of new technology to SMART instrumentation and control systems

    Energy Technology Data Exchange (ETDEWEB)

    Park, Heui Youn; Lee, C. K.; Kim, D. H.; Suh, Y. S.; Hur, S.; Seong, S. H.; Jang, G. S.; Koo, I. S.; Chang, M. H

    1998-03-01

    It is very important to examine the conformance with licensing requirements and standards when new digital technology and equipment apply to nuclear plants. Key requirements of licensing on digitalisation using new technologies are software and hardware V and V, reliability of communication network, and diversity and defence-in-depth concept against common mode failures of hardware and software. And it should be also evaluated whether the selection and application of new technology comply with the design concept and requirements of SMART MMIS or not. In this report, we reviewed digitalisation materials such as EPRI`s ALWR utility requirements document, I and C upgrade plan, guideline on licensing digital upgrades, and IAEA`s issues and approaches to plant modernization to explore application method on new I and C technologies, and evaluated the state of applicable new technologies for SMART MMIS which are selected from the technologies, methods, and manuals of the industrial area. (author). 36 refs., 15 tabs.

  15. On the importance of uncertain factors in seismic fragility assessment

    International Nuclear Information System (INIS)

    Borgonovo, E.; Zentner, I.; Pellegri, A.; Tarantola, S.; Rocquigny, E. de

    2013-01-01

    This paper addresses the definition of importance measures for helping the modeller to detect the factors on which to focus modelling activity and data collection in seismic fragility analysis. We study sensitivity measures consistent with the decision-support criteria of interest, namely, the (mean) fragility curve and the “High Confidence of Low Probability of Failure” (HCLPF) value. The importance measures are obtained analytically for the EPRI safety factor method, which is nowadays used worldwide for seismic risk assessment of nuclear plants. We illustrate and discuss the use of both variance-based and CDF-based importance measures in the application to two case studies, the first analytical and based on the EPRI method, the second numerical.

  16. Simulator data on human error probabilities

    International Nuclear Information System (INIS)

    Kozinsky, E.J.; Guttmann, H.E.

    1982-01-01

    Analysis of operator errors on NPP simulators is being used to determine Human Error Probabilities (HEP) for task elements defined in NUREG/CR 1278. Simulator data tapes from research conducted by EPRI and ORNL are being analyzed for operator error rates. The tapes collected, using Performance Measurement System software developed for EPRI, contain a history of all operator manipulations during simulated casualties. Analysis yields a time history or Operational Sequence Diagram and a manipulation summary, both stored in computer data files. Data searches yield information on operator errors of omission and commission. This work experimentally determines HEPs for Probabilistic Risk Assessment calculations. It is the only practical experimental source of this data to date

  17. A decision analysis framework to support long-term planning for nuclear fuel cycle technology research, development, demonstration and deployment

    International Nuclear Information System (INIS)

    Sowder, A.G.; Machiels, A.J.; Dykes, A.A.; Johnson, D.H.

    2013-01-01

    To address challenges and gaps in nuclear fuel cycle option assessment and to support research, develop and demonstration programs oriented toward commercial deployment, EPRI (Electric Power Research Institute) is seeking to develop and maintain an independent analysis and assessment capability by building a suite of assessment tools based on a platform of software, simplified relationships, and explicit decision-making and evaluation guidelines. As a demonstration of the decision-support framework, EPRI examines a relatively near-term fuel cycle option, i.e., use of reactor-grade mixed-oxide fuel (MOX) in U.S. light water reactors. The results appear as a list of significant concerns (like cooling of spent fuels, criticality risk...) that have to be taken into account for the final decision

  18. Expert system applications to nuclear power for enhancement of productivity and performance

    International Nuclear Information System (INIS)

    Naser, J.A.; Cain, D.G.; Sun, B.K.H.; Colley, R.W.; Hirota, N.S.; Gelhaus, F.E.

    1989-01-01

    Expert system technology has matured enough to offer a great deal of promise for a number of application areas in the electric utility industry. These applications can enhance productivity and aid in decision-making. Two parallel efforts are being performed at the Electric Power Research Institute (EPRI) to help the electric utility industry take advantage of expert system technology. The first effort is the development of expert system building tools which are tailored to electric utility industry applications. The second effort is the development of expert system applications. These two efforts complement each other. The application development tests the tools and identifies additional tool capabilities which are required. The tool development helps define the applications which can be successfully developed. The purpose of this paper is to describe some of the tool and application development work which is being performed at EPRI for the electric utility industry. (orig.)

  19. Large-scale demonstration of reliability centered maintenance at two nuclear generating stations

    International Nuclear Information System (INIS)

    Gaertner, J.P.; Edgar, C.; Rodin, M.E.

    1989-01-01

    This paper reports that after successful single-system pilot applications of Reliability Centered Maintenance (RCM) at various utilities, EPRI with Rochester Gas and Electric and Southern California Edison is undertaking multiple-system applications of RCM at their respective nuclear plants. The objective is to demonstrate the feasibility and cost-effectiveness of large-scale RCM application. In addition, each utility has plant-specific objectives to improve maintenance and plant availability. Each project has selected a prioritized list of some 15-20 systems on which to perform RCM. Each project is employing somewhat different RCM analysis methods, both of which conform to a global RCM definition applicable to all EPRI RCM work to date. Each project has developed important insights for improving cost and value of future analyses. Both projects will have applied the RCM process, including implementation, on several plant systems by April 1989

  20. Windows on the future using scenarios to envision the impact of future uncertainties on utility markets

    International Nuclear Information System (INIS)

    1993-09-01

    This executive report introduces a creative approach to strategy development that begins with scenarios and ends with responsive customer business strategies. Created by EPRI and its research partners, this guided approach uses examples from a workshop in ''Scenario Planning.'' The workshop was sponsored by the Customer Systems Division (CSD) as part of its forward-looking plan to provide programs and services capable of meeting customer needs, shareholder expectations, and societal concerns in a changing world. To illustrate the approach, scenarios from EPRI's Customer 20/20 project are examined using contrasting views of the future structure of the industry -- ''incremental change'' and ''retail competition.'' The three scenarios-entitled Retreating Forward, American Renaissance, and Industrial Ecology -- are driven by plausible outcomes of economic, technological, environmental, and regulatory uncertainties. The benefits of creating scenarios and developing strategic responses are depicted in drawings that portray this innovative approach

  1. Instrumentation and control program to support modernization of safety and control in NPPs

    International Nuclear Information System (INIS)

    Wilkinson, D.; James, R.; Naser, J.; Torok, R.

    1997-01-01

    The original analog IandC equipment of most operating nuclear power plants requires increasing maintenance efforts to sustain system performance. Decreasing availability of replacement parts and support organizations for analog technology accentuate obsolescence problems and resultant OandM cost increases. Modern technology, especially digital systems, offers improved functionality, performance and reliability; solutions to obsolescence of equipment; reduction in OandM costs; and the potential to enhance safety. Digital systems with their inherent advantages will be implemented only if reliable and cost-effective implementation is achieved and if the upgraded system supports reduced power production costs. EPRI and its member utilities are working together under the Integrated IandC Upgrade Initiative to address IandC issues. The present paper describes and gives the status of EPRI's Integrated IandC Upgrade Initiative. (author)

  2. Application of quality assurance program to safety related aging equipment or components

    International Nuclear Information System (INIS)

    Papaiya, N.C.

    1990-01-01

    This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements

  3. Validation of a methodology for the study of generation cost of electric power for nuclear power plants; Validacion de una metodologia para el estudio de costos de generacion de electricidad de plantas nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ortega C, R.F.; Martin del Campo M, C. [Facultad de Ingenieria, UNAM, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550, Jiutepec, Morelos (Mexico)]. E-mail: rfortega@mexis.com

    2004-07-01

    It was developed a model for the calculation of costs of electric generation of nuclear plants. The developed pattern was validated with the one used by the United States Council for Energy Awareness (USCEA) and the Electric Power Research Institute (EPRI), in studies of comparison of alternatives for electric generation of nuclear plants and fossil plants with base of gas and of coal in the United States described in the guides calls Technical Assessment Guides of EPRI. They are mentioned in qualitative form some changes in the technology of nucleo electric generation that could be included in the annual publication of Costs and Parameters of Reference for the Formulation of Projects of Investment in the Electric Sector of the Federal Commission of Electricity. These changes are in relation to the advances in the technology, in the licensing, in the construction and in the operation of the reactors called advanced as the A BWR built recently in Japan. (Author)

  4. Photovoltaic rural electrification and the electric power utility. Workshop. [Selected Papers

    Energy Technology Data Exchange (ETDEWEB)

    Huacuz, J. M.; Villasenor, F.; Urrutia, M. [eds.] [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1995-12-31

    This document contains the national and international programs about photovoltaic systems for rural electrification and the electric power utility experiences about PV programs. The IERE Workshop was hold from May 8 to 12, 1995 in Cocoyoc, Mexico. It was organized by the Electrical Research Institute of Mexico (Instituto de Investigaciones Electricas (IIE)) and the U.S. Electric Power Research Institute (EPRI). The Workshop was attended by 38 delegates from 13 countries [Espanol] Este documento contiene los programas nacionales e internacionales sobre electrificacion fotovoltaica rural y las experiencias en programas fotovoltaicos de empresas electricas. El taller de trabajo IERE fue realizado los dias del 8 al 12 de mayo de 1995 en Cocoyoc, Mexico. Fue organizado por el Instituto de Investigaciones Electricas (IIE) y el U.S. Electric Power Research Institute (EPRI) (Instituto de Investigaciones de Energia Electrica de Estados Unidos). A este taller de trabajo asistieron 38 delegados de 13 paises

  5. Chemical-cleaning process evaluation: Westinghouse steam generators. Final report

    International Nuclear Information System (INIS)

    Cleary, W.F.; Gockley, G.B.

    1983-04-01

    The Steam Generator Owners Group (SGOG)/Electric Power Research Institute (EPRI) Steam Generator Secondary Side Chemical Cleaning Program, under develpment since 1978, has resulted in a generic process for the removal of accumulated corrosion products and tube deposits in the tube support plate crevices. The SGOG/EPRI Project S150-3 was established to obtain an evaluation of the generic process in regard to its applicability to Westinghouse steam generators. The results of the evaluation form the basis for recommendations for transferring the generic process to a plant specific application and identify chemical cleaning corrosion guidelines for the materials in Westinghouse Steam Generators. The results of the evaluation, recommendations for plant-specific applications and corrosion guidelines for chemical cleaning are presented in this report

  6. Survey on the use of configuration risk and safety management tools at nuclear power plants. Final report

    International Nuclear Information System (INIS)

    Fleming, K.N.; Read, J.W.; Dagan, W.J.; Bidwell, D.A.

    1998-09-01

    In order to provide input to Electricite de France's (EDF) evaluation of the use of configuration safety and risk management tools in the French plants and to collect information to guide the EPRI efforts to provide useful tools for the EPRI member utilities and international partners, a joint effort to survey US and selected non-US nuclear power stations was conducted. This survey examined the use of various approaches, techniques, and software tools that are being used to evaluate the safety and risk aspects of plant configuration changes and configuration changes during plant outages as well as during power operation. The use of these tools has increased in recent years as a result of efforts to optimize plant maintenance programs, improve plant safety, and increase plant reliability and availability. This report provides the results of the survey of 37 organizations covering 54 nuclear plant sites and 97 reactor units

  7. U.S. Industry Activities on Inspection of CRDM Penetrations

    International Nuclear Information System (INIS)

    Alley, Tom; Kietzman, Kim; Ammirato, Frank

    2002-01-01

    The discovery of primary water stress corrosion cracking (PWSCC) in control rod drive mechanisms (CRDM) penetrations in U.S. and European plants prompted the U.S. nuclear industry to focus considerable effort on development and implementation of effective inspection methods. In particular, cracking was discovered in butt welds connecting reactor vessel nozzles to main coolant piping and in control rod drive mechanism (CRDM) head penetration base material and attachment welds. The EPRI Materials Reliability Program (EPRI-MRP) formed an Inspection Committee to address development of industry guidance for inspection of these components, development of effective non-destructive examination (NDE) methods, and demonstration of inspection processes. This paper discusses the MRP activities pertaining to inspection of CRDM penetrations. Results of demonstrations and field inspections conducted will also be summarized. (authors)

  8. Commercialization of the modular modeling system

    International Nuclear Information System (INIS)

    Bartells, P.S.

    1987-01-01

    The Modular Modeling System (MMS) was developed by the Electric Power Research Institute (EPRI) to provide an efficient, economical, and user-friendly computer code for use in the analysis of the dynamic performance of nuclear and fossil power plants. The MMS has been under development since 1978 and is now ready for general release to the industry. To most effectively transfer the MSS technology on a worldwide basis, EPRI has licensed the Babcock and Wilcox Company (B and W) to act as the MMS code coordinator and commercial licensing agent. B and W is responsible for promoting the use of MMS and assisting users in the effective utilization of this new analysis tool. The history behind the commercialization of the MMS and the mechanism by which the MMS technology will be effectively transferred to provide for a self-sustaining and technically current analysis tool are outlined

  9. Seminar on heat pump research and applications: proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Steele, R.V. Jr. (ed.)

    1984-11-01

    This volume is a compilation of papers prepared by speakers at a seminar on heat pumps. The seminar was organized by the Electric Power Research Institute (EPRI) in cooperation with Louisiana Power and Light Company and New Orleans Public Service, Inc. The seminar's purpose was to inform utility managers and engineers of the most recent developments in residential heat pump technology and applications. Statements by invited panelists on the outlook for heat pump technology are also included. The speakers, who represented key organizations in the heat pump area, including utilities, industry associations, manufacturers, independent research institutes, government, and EPRI, addressed the following topics: status of heat pump research and development, heat pump testing and rating; field monitoring of heat pumps; heat pump water heaters; heat pump reliability; and marketing programs for pumps. All papers, total of sixteen have been processed for inclusion in the Energy Data Base.

  10. LWR development in the USA

    International Nuclear Information System (INIS)

    Taylor, J.J.; Stahlkopf, K.E.; Noble, D.M.; Dau, G.J.

    1987-01-01

    The U.S. Nuclear Power Industry is developing improved reactor systems to be repared for the expected need of new base load electric generating capacity in the 1990s. The approach being taken is to build upon the large base of existing light water reactor technology, making evolutionary improvements, and finding innovative ways to simplify, shorten construction time, and reduce cost. The U.S. reactor manufacturers, working in collaboration with Japanese utilities, are developing 1300 MWe improved designs. This paper reviews the EPRI ALWR Program which is coordinated with these efforts by the reactor manufactureres. Emphasis is given to that portion of the EPRI Program dealing with conceptual design of smaller rated Advanced Simplified LWRs using passive system design to accomplish major simplification. (author)

  11. Automation of eddy current system for in-service inspection of turbine and generator rotor bores

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The current project (EPRI-RP-1975-5) is a continuation of activities that began several years ago. Those results (EPRI-RP-1957-1) indicated that eddy current testing shows promise for in-service inspection. The current project investigates the degree to which eddy current testing can be used to replace bore magnetic particle testing. For this purpose, correlation studies between eddy current and magnetic particle tests are being undertaken on laboratory rotor sections and field test pieces of rotors. The eddy current data are to be gathered automatically by a combination of the Nortec-25L Eddyscope (to provide the analog eddy current signals) and the General Electric DATAQ/sup TM/ (a registered trademark of the General Electric Co.) System (to perform the automatic data acquisition). This paper describes some test results on a flaked laboratory rotor section

  12. System 80+ design features for severe accident prevention and mitigation

    International Nuclear Information System (INIS)

    Jacob, M.C.; Schneider, R.E.; Finnicum, D.J.

    1993-01-01

    ABB-CE, in cooperation with the US Department of Energy, is working to develop and certify the System 80+ design, which is ABB-CE's standardized evolutionary Advanced Light Water Reactor (ALWR) design. It incorporates design enhancements based on Probabilistic Risk Assessment (PRA) insights, guidance from the EPRI's Utility Requirements Document, and US NRC's Severe Accident Policy. Major severe accident prevention and mitigation design features of the system is discussed along with its conformance to EPRI URD guidance, as applicable. Computer simulation of a best estimate severe accident scenario is presented to illustrate the acceptable containment performance of the design. It is concluded that by considering severe accident prevention and mitigation early in the design process, the System 80+ design represents a robust plant design that has low core damage frequencies, low containment conditional failure probabilities, and acceptable deterministic containment performance under severe accident conditions

  13. Scaling structure loads for SMA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Won; Song, Jeong Guk; Jeon, Sang Ho; Lim, Hak Kyu; Lee, Kwang Nam [KEPCO ENC, Yongin (Korea, Republic of)

    2012-10-15

    When the Seismic Margin Analysis(SMA) is conducted, the new structural load generation with Seismic Margin Earthquake(SME) is the time consuming work. For the convenience, EPRI NP 6041 suggests the scaling of the structure load. The report recommend that the fixed base(rock foundation) structure designed using either constant modal damping or modal damping ratios developed for a single material damping. For these cases, the SME loads can easily and accurately be calculated by scaling the spectral accelerations of the individual modes for the new SME response spectra. EPRI NP 6041 provides two simple methodologies for the scaling structure seismic loads which are the dominant frequency scaling methodology and the mode by mode scaling methodology. Scaling of the existing analysis to develop SME loads is much easier and more efficient than performing a new analysis. This paper is intended to compare the calculating results of two different methodologies.

  14. A Parametric Study on Welding Process Simulation for Multi-pass welds in a Plate

    Energy Technology Data Exchange (ETDEWEB)

    Park, Won Dong; Bahn, Chi Bum; Kim, Ji Hun [Pusan National University, Busan (Korea, Republic of)

    2016-05-15

    EPRI (MRP-316, 317) (1,2) and USNRC (NUREG-2162)(3) have performed related studies for FEA models to predict the weld residual stress distribution. In this work, a systematic parametric study was performed to find out how major assumptions and conditions used in the simulation could affect the weld residual stress distribution. 2- dimensional simulation was conducted by using commercial FEA software, ABAQUS(4) , for multi-pass Alloy 82 welds performed in a stainless steel plate (EPRI MRP-316, P-4, phase 1). From the previous results, we could make the following conclusions. 1. The method of applying power density is more realistic than predefined temperature. 2. It seems that annealing effect reduces the transverse direction weld residual stress (S33). However more detailed analyses for annealing effect are needed.

  15. Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

    International Nuclear Information System (INIS)

    Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C.

    1995-01-01

    In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation

  16. Simulator data on human error probabilities

    International Nuclear Information System (INIS)

    Kozinsky, E.J.; Guttmann, H.E.

    1981-01-01

    Analysis of operator errors on NPP simulators is being used to determine Human Error Probabilities (HEP) for task elements defined in NUREG/CR-1278. Simulator data tapes from research conducted by EPRI and ORNL are being analyzed for operator error rates. The tapes collected, using Performance Measurement System software developed for EPRI, contain a history of all operator manipulations during simulated casualties. Analysis yields a time history or Operational Sequence Diagram and a manipulation summary, both stored in computer data files. Data searches yield information on operator errors of omission and commission. This work experimentally determined HEP's for Probabilistic Risk Assessment calculations. It is the only practical experimental source of this data to date

  17. A correlation for safety valve blowdown and ring settings

    International Nuclear Information System (INIS)

    Singh, A.; Shak, D.

    1982-01-01

    The blowdown of a spring loaded safety valve is defined as the difference between the pressure at which the valve opens and the pressure at which the valve fully closes under certain fluid flow conditions. Generally, the blowdown is expressed in terms of percentage of the opening pressure. An extensive series of tests carried out in the EPRI/PWR Utilities Valve Test Program has shown that the blowdown of safety valves can in general be strongly dependent upon the valve geometry and other parameters such as ring adjustments, spring stiffness, backpressure etc. In the present study, correlations have been developed using the EPRI safety valve test data to predict the expected blowdown as a function of adjustment ring settings for geometrically similar valves under steam discharge conditions. The correlation is validated against two different size Dresser valves

  18. Scaling structure loads for SMA

    International Nuclear Information System (INIS)

    Lee, Dong Won; Song, Jeong Guk; Jeon, Sang Ho; Lim, Hak Kyu; Lee, Kwang Nam

    2012-01-01

    When the Seismic Margin Analysis(SMA) is conducted, the new structural load generation with Seismic Margin Earthquake(SME) is the time consuming work. For the convenience, EPRI NP 6041 suggests the scaling of the structure load. The report recommend that the fixed base(rock foundation) structure designed using either constant modal damping or modal damping ratios developed for a single material damping. For these cases, the SME loads can easily and accurately be calculated by scaling the spectral accelerations of the individual modes for the new SME response spectra. EPRI NP 6041 provides two simple methodologies for the scaling structure seismic loads which are the dominant frequency scaling methodology and the mode by mode scaling methodology. Scaling of the existing analysis to develop SME loads is much easier and more efficient than performing a new analysis. This paper is intended to compare the calculating results of two different methodologies

  19. Penentuan Kebijakan Perawatan dan Optimasi Persediaan Suku Cadang pada Coal Handling System PLTU Paiton

    Directory of Open Access Journals (Sweden)

    Fadeli Muhammad F

    2012-09-01

    Full Text Available Fasilitas yang terdapat pada sebuah pembangkit listrik membutuhkan perawatan agar dapat berfungsi  sesuai dengan kapasitasnya. Salah satu fasilitas yang membutuhkan perawatan pada PLTU Paiton adalah fasilitas coal handling system. Perusahaan perlu menerapkan strategi perawatan yang tepat agar biaya perawatan yang dikeluarkan dapat optimal. Permasalahan yang ada pada PLTU Paiton adalah strategi perawatan yang ada masih belum bisa mengatasi kemungkinan kegagalan yang terjadi dan aktivitas perawatan yang dilakukan tidak didukung oleh ketersediaan suku cadang yang dibutuhkan. Hal tersebut menyebabkan biaya perawatan yang dikeluarkan menjadi tidak optimal. Penelitian ini menggunakan metode reliability centered maintenance (RCM II yang dikombinasikan dengan metode evaluasi dari electrical power research institute (EPRI untuk menentukan strategi perawatan yang tepat terhadap coal handling system. Permasalahan persediaan untuk mendukung implementasi penerapan strategi perawatan akan diselesaikan dengan metode probabilistic economic order quantity (EOQ model. Penggunaan metode RCM II yang dikombinasikan dengan metode evaluasi dari EPRI dan penggunaan metode probabilistic EOQ model bertujuan untuk mengoptimalkan biaya perawatan yang dikeluarkan.

  20. Air toxics and the 1990 Clean Air Act: Managing trace element emissions

    International Nuclear Information System (INIS)

    Chow, W.; Levin, L.; Miller, M.J.

    1992-01-01

    The US Environmental Protection Agency (EPA) has historically regulated air toxics (hazardous air pollutants) under Section 112 of the Clean Air Act. To date, EPA has established emission standards for 8 hazardous air pollutants (arsenic, asbestos, benzene, beryllium, mercury, radionuclides, coke oven emissions and vinyl chloride). The US electric utility industry was not determined to be a source category requiring regulation for any of the eight chemicals. Of the eight, radionuclides were the last species for which EPA established hazardous emissions standards. In this instance, EPA determined that the risks associated with electric utility fossil fuel power plant emissions were sufficiently low that they should not be regulated. However, the 1990 Clean Air Act Amendments require a new evaluation of the electric utility industry emissions of hazardous air pollutants. This paper summarizes the key features of the air toxics provisions of the Clean Air Act Amendments, describes EPRI's activities on the subject, and provides some preliminary insights from EPRI's research to date

  1. Photovoltaic rural electrification and the electric power utility. Workshop. [Selected Papers

    Energy Technology Data Exchange (ETDEWEB)

    Huacuz, J M; Villasenor, F; Urrutia, M [eds.; Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1996-12-31

    This document contains the national and international programs about photovoltaic systems for rural electrification and the electric power utility experiences about PV programs. The IERE Workshop was hold from May 8 to 12, 1995 in Cocoyoc, Mexico. It was organized by the Electrical Research Institute of Mexico (Instituto de Investigaciones Electricas (IIE)) and the U.S. Electric Power Research Institute (EPRI). The Workshop was attended by 38 delegates from 13 countries [Espanol] Este documento contiene los programas nacionales e internacionales sobre electrificacion fotovoltaica rural y las experiencias en programas fotovoltaicos de empresas electricas. El taller de trabajo IERE fue realizado los dias del 8 al 12 de mayo de 1995 en Cocoyoc, Mexico. Fue organizado por el Instituto de Investigaciones Electricas (IIE) y el U.S. Electric Power Research Institute (EPRI) (Instituto de Investigaciones de Energia Electrica de Estados Unidos). A este taller de trabajo asistieron 38 delegados de 13 paises

  2. Steam generator reliability improvement project

    International Nuclear Information System (INIS)

    Blomgren, J.C.; Green, S.J.

    1987-01-01

    Upon successful completion of its research and development technology transfer program, the Electric Power Research Institute's (EPRI's) Steam Generator Owners Group (SGOG II) will disband in December 1986, and be replaced in January 1987, by a successor project, the Steam Generator Reliability Project (SGRP). The new project, funded in the EPRI base program, will continue to emphasize reliability and life extension, which were carried forward by SGOG II. The objectives of SGOG II have been met. Causes and remedies have been identified for tubing corrosion problems such as stress corrosion cracking and pitting, and steam generator technology has been improved in areas such as tube wear prediction and nondestructive evaluation. These actions have led to improved reliability of steam generators. Now the owners want to continue with a centrally managed program that builds on what has been learned. The goal is to continue to improve steam generator reliability and to solve small problems before they become large problems

  3. Guidelines for performance-based supplier audits (NCIG-16)

    International Nuclear Information System (INIS)

    Lauderdale, J.R.; Mattu, R.K.; Roman, W.S.

    1990-06-01

    This document provides guidelines for planning and conducting performance-based audits of suppliers of items used in nuclear power plants. A common purpose of audits is to provide a basis for confidence in the supplier's controls to ensure that products received will perform their intended functions satisfactorily. Performance-based audits offer means of raising the level of confidence. This confidence comes from evaluation of important features of the product and the processes and activities that produce it. This document does not add requirements to those in existing codes, standards, or regulations. The guidance herein is intended to complement the information in existing industry standards and practices. Performance-based audits are one element of an effective procurement program. A companion EPRI/NCIG document, EPRI NP-6629, Guidelines for the Procurement and Receipt of Items for Nuclear Power Plants (NCIG-15), provides guidance for other elements of an effective procurement program

  4. Development to requirements for a procedures software tool

    International Nuclear Information System (INIS)

    Yasutake, J.Y.; Hachiro Isoda

    1993-01-01

    In 1989, the Electric Power Research Institute (EPRI) and the Central Research Institute of the Electric Power Industry (CRIEPI) in Japan initiated a joint research program to investigate various interventions to reduce personnel errors and inefficiencies in the maintenance of nuclear power plants. This program, consisting of several interrelated projects, was initiated because of the mutual recognition of the importance of the human element in the efficient and safe operation of utilities and the continuing need to enhance personnel performance to sustain plant safety and availability. This paper summarizes one of the projects, jointly funded by EPRI and CRIEPI, to analyze the requirements for, and prepare a functional description of, a procedures software tool (PST). The primary objective of this project was to develop a description of the features and functions of a software tool that would help procedure writers to improve the quality of maintenance and testing procedures, thereby enhancing the performance of both procedure writers and maintenance personnel

  5. Advanced light water reactors for the nineties

    International Nuclear Information System (INIS)

    Ross, F.A.; Sugnet, W.R.

    1987-01-01

    The EPRI/Industry advanced light water reactor (ALWR) program and the US Department of Energy ALWR program are closely coordinated to meet the common objective which is the availability of improved and simplified light water reactor plants that may be ordered in the next decade to meet new or replacement capacity requirements. The EPRI/Industry objectives, program participants, and foreign participants, utility requirements document, its organization and content, small plant conceptual design program, the DOE ALWR program, design verification program, General Electric ABWR design features, Combustion Engineering system design, mid-size plant development, General Electric SBWR objectives, Westinghouse/Burns and Roe design objectives, construction improvement, and improved instrumentation and control are discussed in the paper

  6. History of Fire Events in the U.S. Commercial Nuclear Industry

    International Nuclear Information System (INIS)

    Bijan Najafi; Joglar-Biloch, Francisco; Kassawara, Robert P.; Khalil, Yehia

    2002-01-01

    Over the past decade, interest in performance-based fire protection has increased within the nuclear industry. In support of this growing interest, in 1997 the Electric Power Research Institute (EPRI) developed a long-range plan to develop/improve data and tools needed to support Risk-Informed/Performance-Based fire protection. This plan calls for continued improvement in collection and use of information obtained from fire events at nuclear plants. The data collection process has the objectives of improving the insights gained from such data and reducing the uncertainty in fire risk and fire modeling methods in order to make them a more reliable basis for performance based fire protection programs. In keeping with these objectives, EPRI continues to collect, review and analyze fire events in support of the nuclear industry. EPRI collects these records in cooperation with the Nuclear Electric Insurance Limited (NEIL), by compiling public fire event reports and by direct solicitation of U.S. nuclear facilities. EPRI fire data collection project is based on the principle that the understanding of history is one of the cornerstones of improving fire protection technology and practice. Therefore, the goal has been to develop and maintain a comprehensive database of fire events with flexibility to support various aspects of fire protection engineering. With more than 1850 fire records over a period of three decades and 2400 reactor years, this is the most comprehensive database of nuclear power industry fire events in existence today. In general, the frequency of fires in the U.S. commercial nuclear industry remains constant. In few cases, e.g., transient fires and fires in BWR offgas/recombiner systems, where either increasing or decreasing trends are observed, these trends tend to slow after 1980. The key issues in improving quality of the data remain to be consistency of the recording and reporting of fire events and difficulties in collection of records. EPRI has

  7. Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C. [Oak Ridge National Lab., TN (United States). Technical Programs and Services; Brock, W.R.; Denton, D.R. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

    1995-12-31

    In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation.

  8. Improvement of a portable high-energy radiographic inspection system: Final report

    International Nuclear Information System (INIS)

    Owen, R.D.

    1987-02-01

    This report describes the development of miniaturized linear accelerator (MINAC) technology, including descriptions of all major developments sponsored by EPRI subsequent to previously sponsored work. In addition, this report describes MINAC-related developments in both real-time x-ray imaging and radiographic image data processing systems which were sponsored by EPRI concurrently. The objectives of this program have been to achieve modifications identified as desirable improvements to the basic ''MINAC 3'' equipment; to expand the range and effectiveness of MINAC applications through design improvements, achievement of wider energy/output capabilities, and the development of suitable imaging and digital processing technologies; and to provide technical information on high-energy radiographic equipment useful to scientists, educators, institutions, NDE technicians and others who may benefit from detailed information on the special equipment. Program, equipment and technical descriptions are followed by conclusions and recommendations for future work

  9. The economics of amine usage

    International Nuclear Information System (INIS)

    Fountain, M.J.

    1994-01-01

    The EPRI computer programm, 'Aminemod', a PWR chemistry model, has been used to compare the technical advantages of the 'advanced' amines, ethanolamine, 1,2 diaminoethane and 5 aminopentanol over morpholine in generating an elevated pH in the moisture separator and the economics of using these amines has been assessed by using an MS Excel spreadsheet in conjunction with Aminemod. The advanced amines are capable of achieving 1 pH unit above neutrality, the EPRI target for prevention of erosion-corrison, at acceptable cost and, compared with 'conventional' amines, at considerably reduced ionic load on the condensate polisher. The exercise demonstrates that it is essential to evaluate the effect of an amine dosing regime on the total operating cost and that it is not possible to prejudge the economic outcome on the basis of an amine's purchase price. (orig.)

  10. Risk Assessment of the Main Control Room Fire Using Fire Simulations

    International Nuclear Information System (INIS)

    Kang, Dae Il; Kim, Kilyoo; Jang, Seung Cheol

    2013-01-01

    KAERI is performing a fire PSA for a reference plant, Ulchin Unit 3, as part of developing the Korean site risk profile (KSRP). Fire simulations of the MCR fire were conducted using the CFAST (Consolidated Fire Growth and Smoke Transport) model and FDS (fire dynamic simulator) to improve the uncertainty in the MCR fire risk analysis. Using the fire simulation results, the MCR abandonment risk was evaluated. Level 1 PSA (probabilistic safety assessment) results of Ulchin Unit 3 using the EPRI PRA (probabilistic risk assessment) implementation guide showed that the MCR (main control room) fire was the main contributor to the core damage frequency. Recently, U. S. NRC and EPRI developed NUREG/CR-6850 to provide state-of-the-art methods, tools, and data for the conduct of a fire PSA for a commercial NPP

  11. Potential human factors research relating to modern technology in nuclear power plants

    International Nuclear Information System (INIS)

    Ketchel, J.; Fink, R.; Hanes, L.; Williges, R.; Williges, B.

    1994-01-01

    This paper discusses proposed human factors research to address advanced human-machine interface technology in nuclear power plants. It relates to a current EPRI project to identify a prioritized list of specific research issues that could be assessed to improve control room and other user interface areas. The project seeks to bridge the gap between the functional requirements of advanced design initiatives and the human factors research needed to support them. It seeks to identify potential benefits to be expected, as well as potential problems that might be introduced by advanced technology. It provides an organized approach to identifying human factors research needs, information already available, and measures of performance and effectiveness that might be used to assess the value of potential improvements. Those parts of the proposed plan that are subsequently approved by EPRI management and by the utility advisory committee will provide a basis for recommending research priorities

  12. Validation of a methodology for the study of generation cost of electric power for nuclear power plants

    International Nuclear Information System (INIS)

    Ortega C, R.F.; Martin del Campo M, C.

    2004-01-01

    It was developed a model for the calculation of costs of electric generation of nuclear plants. The developed pattern was validated with the one used by the United States Council for Energy Awareness (USCEA) and the Electric Power Research Institute (EPRI), in studies of comparison of alternatives for electric generation of nuclear plants and fossil plants with base of gas and of coal in the United States described in the guides calls Technical Assessment Guides of EPRI. They are mentioned in qualitative form some changes in the technology of nucleo electric generation that could be included in the annual publication of Costs and Parameters of Reference for the Formulation of Projects of Investment in the Electric Sector of the Federal Commission of Electricity. These changes are in relation to the advances in the technology, in the licensing, in the construction and in the operation of the reactors called advanced as the A BWR built recently in Japan. (Author)

  13. Operator reliability assessment system (OPERAS)

    International Nuclear Information System (INIS)

    Spurgin, A.J.; Hallam, J.W.; Spurgin, J.P.; Singh, A.

    1991-01-01

    The paper gives an overview of the OPERAS project. It discusses the background which led to the design of the PC-based data collection and analysis system connected to plant training simulators including those used for nuclear power plants. The usefulness of a system like OPERAS was perceived during an earlier EPRI project, the Operator Reliability Experiments project, by EPRI and PG and E. The data collection and analysis approaches used in OPERAS were developed during the ORE project. The paper not only discusses the design of OPERAS but discusses the functions performed and the current experiences with the two prototype systems. Also listed are potential uses of OPERAS by utility personnel in Operations, Training and PRA groups

  14. Restoring life to acidified lakes

    Energy Technology Data Exchange (ETDEWEB)

    Shepard, M

    1986-05-01

    In 1983 EPRI initiated the lake acidification mitigation project (LAMP) in order to examine the long-term ecosystem effects of liming lakes, and to develop a model for calculating optimal liming doses. Investigations were carried out at lakes under 3 sets of conditions: reacidification, maintenance liming and preventive maintenance liming. The research so far has indicated that liming is a safe and effective technique.

  15. Achieving CANDU excellence through collaboration

    Energy Technology Data Exchange (ETDEWEB)

    Dermarkar, F. [CANDU Owners Group Inc., Toronto, Ontario (Canada)

    2015-07-01

    All Operators of CANDU/PHWR Worldwide, and AECL, are members of Candu Owners Group (COG). COG has evolved to become primarily an Operators Owners Group with annual turnover of $75M. It is all about value to the members providing a diverse offering of services to meet a broad spectrum of member needs, linking our members together prioritizing and organizing to enable members to access what they need, when they need it. Collaboration benefits both COG and EPRI.

  16. Evaluation of PWR and BWR pin cell benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Pilgroms, B.J.; Gruppelaar, H.; Janssen, A.J. (Netherlands Energy Research Foundation (ECN), Petten (Netherlands)); Hoogenboom, J.E.; Leege, P.F.A. de (Interuniversitair Reactor Inst., Delft (Netherlands)); Voet, J. van der (Gemeenschappelijke Kernenergiecentrale Nederland NV, Dodewaard (Netherlands)); Verhagen, F.C.M. (Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands))

    1991-12-01

    Benchmark results of the Dutch PINK working group on the PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs.; 9 figs.; 30 tabs.

  17. Proceedings of the Sixth International Conference on Fluidized Bed Combustion. Volume 1. Plenary sessions

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-08-01

    The Sixth International Conference on Fluidized Bed Combustion was held at the Atlanta Hilton, Atlanta, Georgia, April 9-11, 1980. The papers in this volume involved presentation of the research and development programs of the US (US DOE, TVA, EPRI and US EPA), United Kingdom, Federal Republic of Germany and the People's Republic of China. Eight papers from Vol. 1 (Plenary Sessions) of the proceedings have been entered individually into EDB and ERA. (LTN)

  18. Main-coolant-pump shaft-seal guidelines. Volume 1. Maintenance-manual guidelines. Final report

    International Nuclear Information System (INIS)

    Fair, C.E.; Greer, A.O.

    1983-03-01

    This report presents a set of guidelines and a listing of information and data which should be included in maintenance manuals and procedures for Main Coolant Pump Shaft Seals. The noted guidelines and data listing are developed from EPRI sponsored nuclear plant seal operating experience studies. The maintenance oriented results of the most recent such study is summarized. The shaft seal and its auxiliary supporting systems are discussed from both technical and maintenance related viewpoints

  19. Electric Power Research Institute Environmental Control Technology Center: Report to the Steering Committee, June 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    Operations and maintenance continued this month at the Electric Power Research Institute`s (EPRI`s) Environmental Control Technology Center (ECTC). Testing for the Hazardous Air Pollutant (HAP) test block was conducted using the 4.0 MW Spray Dryer Absorber System (SDA) and Pulse Jet Fabric Filter (PJFF) - Carbon Injection System. Investigations also continued across the B&W/CHX Heat Exchanger unit, while the 1.0 MW Selective Catalytic Reduction (SCR) unit remained idle this month in a cold-standby mode as monthly inspections were conducted. Pilot Testing Highlights Testing efforts in June were focused on the HAP test block and the Trace Elements Removal (TER) test block. Both programs were conducted on the 4.0 MW wet FGD pilot unit and PJFF unit. The HAP test block was temporarily concluded in June to further review the test data. This program began in March as part of the DOE Advanced Power Systems Program; the mission of this program is to accelerate the commercialization of affordable, high-efficiency, low-emission, coal-fueled electric generating technologies. The 1996 HAP test block focuses on three research areas, including: Catalytic oxidation of vapor-phase elemental mercury; Enhanced particulate-phase HAPs removal by electrostatic charging of liquid droplets; and Enhanced mercury removal by addition of additives to FGD process liquor. The TER test block is part of EPRI`s overall program to develop control technology options for reduction of trace element emissions. This experimental program investigates mercury removal and mercury speciation under different operating conditions.

  20. VIPRE-01: a thermal-hydraulic analysis code for reactor cores. Volume 3. Programmer's manual. Final report

    International Nuclear Information System (INIS)

    Stewart, C.W.; Koontz, A.S.; Cuta, J.M.; Montgomery, S.D.

    1983-05-01

    VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear-reactor-core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This is Volume 3, the Programmer's Manual. It explains the codes' structures and the computer interfaces

  1. VIPRE-01. a thermal-hydraulic analysis code for reactor cores. Volume 1. Mathematical modeling

    International Nuclear Information System (INIS)

    Stewart, C.W.; Cuta, J.M.; Koontz, A.S.; Kelly, J.M.; Basehore, K.L.; George, T.L.; Rowe, D.S.

    1983-04-01

    VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This volume (Volume 1: Mathematical Modeling) explains the major thermal hydraulic models and supporting correlations in detail

  2. Recommended E3 HEMP Heave Electric Field Waveform for the Critical Infrastructures. Volume 2

    Science.gov (United States)

    2017-07-31

    horizontal electric (E) field, as this field can effectively couple to long power and communications lines and induce quasi-dc currents in these systems ...Department of Defense E electric field EMP electromagnetic pulse EPRI Electric Power Research Institute FERC Federal Energy Regulatory Commission GMD...North American Electric Reliability Corporation nT nanotesla S/m siemens/m UV ultraviolet V Volt ix PREFACE This EMP Commission Report

  3. FRANX. Application for analysis and quantification of the APS fire; FRANK. Aplicacion para el analisis y cuantificacion de los APS de incendios

    Energy Technology Data Exchange (ETDEWEB)

    Snchez, A.; Osorio, F.; Ontoso, N.

    2014-07-01

    The FRANX application has been developed by EPRI within the Risk and Reliability User Group in order to facilitate the process of quantification and updating APS Fire (also covers floods and earthquakes). By applying fire scenarios are quantified in the central integrating the tasks performed during the APS fire. This paper describes the main features of the program to allow quantification of an APS Fire. (Author)

  4. Integrated gasification combined cycle and steam injection gas turbine powered by biomass joint-venture evaluation

    International Nuclear Information System (INIS)

    Sterzinger, G.J.

    1994-05-01

    This report analyzes the economic and environmental potential of biomass integrated gasifier/gas turbine technology including its market applications. The mature technology promises to produce electricity at $55--60/MWh and to be competitive for market applications conservatively estimated at 2000 MW. The report reviews the competitiveness of the technology of a stand-alone, mature basis and finds it to be substantial and recognized by DOE, EPRI, and the World Bank Global Environmental Facility

  5. Transient Analysis for Evaluating the Potential Boiling in the High Elevation Emergency Cooling Units of PWR Following a Hypothetical Loss of Coolant Accident (LOCA) and Subsequent Water Hammer Due to Pump Restart

    International Nuclear Information System (INIS)

    Husaini, S. Mahmood; Qashu, Riyad K.

    2004-01-01

    The Generic Letter GL-96-06 issued by the U.S. Nuclear Regulatory Commission (NRC) required the utilities to evaluate the potential for voiding in their Containment Emergency Cooling Units (ECUs) due to a hypothetical Loss Of Coolant Accident (LOCA) or a Main Steam Line Break (MSLB) accompanied by the Loss Of Offsite Power (LOOP). When the offsite power is restored, the Component Cooling Water (CCW) pumps restart causing water hammer to occur due to cavity closure. Recently EPRI (Electric Power Research Institute) performed a research study that recommended a methodology to mitigate the water hammer due to cavity closure. The EPRI methodology allows for the cushioning effects of hot steam and released air, which is not considered in the conventional water column separation analysis. The EPRI study was limited in scope to the evaluation of water hammer only and did not provide any guidance for evaluating the occurrence of boiling and the extent of voiding in the ECU piping. This paper presents a complete methodology based on first principles to evaluate the onset of boiling. Also, presented is a methodology for evaluating the extent of voiding and the water hammer resulting from cavity closure by using an existing generalized computer program that is based on the Method of Characteristics. The EPRI methodology is then used to mitigate the predicted water hammer. Thus it overcomes the inherent complications and difficulties involved in performing hand calculations for water hammer. The heat transfer analysis provides an alternative to the use of very cumbersome modeling in using CFD (computational fluid dynamics) based computer programs. (authors)

  6. Recent advances in intelligent machine technologies

    International Nuclear Information System (INIS)

    Bartholet, T.G.

    1987-01-01

    Further developments in intelligent machine technologies have recently been accomplished under sponsorship by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), the U.S. Army and NASA. This paper describes these developments and presents actual results achieved and demonstrated. These projects encompass new developments in manipulators, vision and walking machines. Continuing developments will add increasing degrees of autonomy as appropriate to applications in the fields of nuclear power, space, defense and industrial or commercial marketplaces

  7. Survey VS audit by using method 2 to dedicate commercial grade services

    International Nuclear Information System (INIS)

    Martinez ayucar, F. J.

    2014-01-01

    Since the start of the commercial grade dedications, both 10CFR21 and EPRI documents, plus the dedication of commercial grade components, and the stage of commercial grade dedication of the services contemplated. And recently the NRC through various communications and answers trafficking among other issues the commercial grade dedication service. The NRC has detected repeatedly incorrect application of the survey as a method of commercial grade dedication and instead has done an audit of the program elements of commercial quality. (Author)

  8. Winning the battle against IGSCC

    International Nuclear Information System (INIS)

    Riccardella, P.C.; Giannuzzi, A.J.; Childs, W.J.

    1992-01-01

    Intergranular stress corrosion cracking (IGSCC) in austenitic stainless steel piping began to be a widespread problem in Boiling Water Reactors (BWRs) in 1974. Now utility-sponsored research efforts through EPRI, the NRC and the nuclear steam supply vendor in the USA, have produced significant progress in understanding the causes of IGSC. These research projects have also yielded remedial measures which have been effective in reducing or eliminating the problem in both new and most operating BWRs. (author)

  9. A better approach to the MDNBR concept

    International Nuclear Information System (INIS)

    Crecy, F. de.

    1993-01-01

    This paper recalls the statistical origins of the MDNBR concept and Owen's coefficients, as used in CHF studies. The way in which they are currently used may be incorrect and we shall present a better approach, in which the lower tolerance interval limit depends on parameters. Use with least-square regressions and smoothing splines is explained. We also include an example, based on a CHF EPRI test, from the Columbia University data bank. (author). 1 fig., 6 refs

  10. SG (steam generators) reliability project builds on Owners Group successes

    International Nuclear Information System (INIS)

    Green, S.

    1988-01-01

    In 1987, a five-year Steam Generator Reliability Project was established at the Electric Power Research Institute (EPRI) to deal with outstanding issues, following on from work initiated by the previous utility industry groupings (Steam Generator Owners Groups I and II). The work done by these groups is discussed and a listing of the major objectives of the new project is provided. (U.K.)

  11. Decommissioning economic risk advisor: DERAD Version 1.0 user's manual. Final report

    International Nuclear Information System (INIS)

    Gjerde, A.R.; Qian, M.; Govil, P.; Balson, W.E.

    1995-04-01

    DERAD - Decommissioning Economic and Risk ADvisor - is a decision support tool designed to help utility decision makers analyze economics and financial risk of decommissioning nuclear power plants. Your current copy of DERAD, Version 1.0, is customized for PWR configurated plants. DERAD has been developed by Decision Focus Incorporated under EPRI sponsorship. If you have ideas or recommendations for how we can improve and enhance future versions of DERAD, we would like to hear from you

  12. Resolution of digital instrumentation and control and human factors technical and regulatory issues for new plants and for modernization of operating plants

    International Nuclear Information System (INIS)

    Naser, J.A.; Torok, R.C.; Canavan, K.T.

    2008-01-01

    There are several technical and regulatory issues in the areas of digital I and C, human factors, and control rooms needing generic resolution. If they are not generically resolved, they can contribute to protracted regulatory reviews for operating plant license amendments and substantial delays and increased costs for new plant COL approvals. Therefore; a coordinated, proactive program has been established to resolve key issues. Both Industry and NRC have roles in resolving these key issues and addressing them in future design efforts and regulatory reviews. The Industry initiative is led by the NEI Digital I and C and Human Factors Working Group. NRC has established Task Working Groups under the NRC Digital I and C Steering Committee to address the issues and interact with Industry. EPRI is providing technical input and resolution leadership for some of the issues being addressed in three of the task working groups. For the Highly Integrated Control Room - Human Factors Task area, EPRI has taken the lead in developing draft industry position technical reports for the following three issues: 1) Minimum inventory of human system interfaces, 2) Computerized procedures and associated topics of automation and soft controls, and 3) Methodology to determine the acceptability of manual operator actions response times for a BTP 7-19 software common cause failure. For the Diversity and Defense-in-Depth area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Integrating defensive measures and diversity attributes to protect against digital common cause failures and 2) Susceptibility of digital devices and components to common cause failures. For the Risk Informing area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Clarifying how to use current methods to model digital systems in a PRA and 2) Application of PRA to specific digital I and C issues

  13. BWR MARK I pressure suppression pool mixing and stratification analysis using GOTHIC lumped parameter modeling methodology

    International Nuclear Information System (INIS)

    Ozdemir, Ozkan Emre; George, Thomas L.

    2015-01-01

    As a part of the GOTHIC (GOTHIC incorporates technology developed for the electric power industry under the sponsorship of EPRI.) Fukushima Technical Evaluation project (EPRI, 2014a, b, 2015), GOTHIC (EPRI, 2014c) has been benchmarked against test data for pool stratification (EPRI, 2014a, b, Ozdemir and George, 2013). These tests confirmed GOTHIC’s ability to simulate pool mixing and stratification under a variety of anticipated suppression pool operating conditions. The multidimensional modeling requires long simulation times for events that may occur over a period of hours or days. For these scenarios a lumped model of the pressure suppression chamber is desirable to maintain reasonable simulation times. However, a lumped model for the pool is not able to predict the effects of pool stratification that can influence the overall containment response. The main objective of this work is on the development of a correlation that can be used to estimate pool mixing and stratification effects in a lumped modeling approach. A simplified lumped GOTHIC model that includes a two zone model for the suppression pool with controlled circulation between the upper and lower zones was constructed. A pump and associated flow connections are included to provide mixing between the upper and lower pool volumes. Using numerically generated data from a multidimensional GOTHIC model for the suppression pool, a correlation was developed for the mixing rate between the upper and lower pool volumes in a two-zone, lumped model. The mixing rate depends on the pool subcooling, the steam injection rate and the injection depth

  14. Inventory of on-line efficiency control software for coal-fired power plants; Inventarisatie on-line rendementsbewakingspakketten voor kolengestookte centrales

    Energy Technology Data Exchange (ETDEWEB)

    Hulshof, H; Tim, R [KEMA Fossiele Opwekking, Arnhem (Netherlands)

    1994-12-31

    Based on the results of a literature study and the assessment of currently applied and operational systems an overview is given of existing, commercially available, efficiency control computer programs for coal-fired electric power plants. The programs Siemens, Kaye Plant Monitoring Analyses, Plant Monitoring Workstations (EPRI), and the Langerlo Method are specified and compared for speed, flexibility, accuracy, the required own efforts to apply the program, and the estimated costs for acquisition

  15. Main-coolant-pump shaft-seal guidelines. Volume 2. Operational guidelines. Final report

    International Nuclear Information System (INIS)

    Fair, C.E.; Greer, A.O.

    1983-03-01

    This report presents a set of guidelines and criteria for improving main coolant pump shaft seal operational reliability. The noted guidelines are developed from EPRI sponsored nuclear power plant seal operating experience studies. Usage procedures/practices and operational environment influence on seal life and reliability from the most recent such survey are summarized. The shaft seal and its auxiliary supporting systems are discussed both from technical and operational related viewpoints

  16. 1985 seminar on power plant digital control and fault-tolerant microcomputers: proceedings

    International Nuclear Information System (INIS)

    Divakaruni, S.M.

    1986-09-01

    An EPRI Seminar to address Power Plant Digital Controls and Fault-Tolerant Microcomputers Technology was hosted by Arizona Public Service Company in Phoenix, Arizona on April 9-12, 1986. The attendees represented a broad spectrum of US and foreign utilities, architect and consulting firms, and NSSS and computer system hardware vendors. These proceedings contain the text of the formal presentations as well as the papers and slides used during the short courses offered

  17. Development of a simplified piping support system

    International Nuclear Information System (INIS)

    Leung, J.; Anderson, P.H.; Tang, Y.K.; Kassawara, R.P.; Tang, H.T.

    1987-01-01

    This paper presents the results of experimental and analytical studies for developing a simplified piping support system (SPSS) for nuclear power piping in place of snubbers. The basic concept of the SPSS is a passive seismic support system consisting of limit stops. Large gaps are provided to allow for free thermal expansion during normal plant operation while preventing excessive displacement during a seismic event. The results are part of a research and development program sponsored by EPRI. (orig./HP)

  18. Advanced Light Water Reactor Program: Program management and staff review methodology

    International Nuclear Information System (INIS)

    Moran, D.H.

    1986-12-01

    This report summarizes the NRC/EPRI coordinated effort to develop design requirements for a standardized advanced light water reactor (ALWR) and the procedures for screening and applying new generic safety issues to this program. The end-product will be an NRC-approved ALWR Requirements Document for use by the nuclear industry in generating designs of LWRs to be constructed for operation in the 1990s and beyond

  19. Managing corporate assets to maximize value

    International Nuclear Information System (INIS)

    Rubin, L.

    1992-01-01

    As the utility industry environment becomes more complex, pressures grow for managers to make more effective use of all their assets - including fuel, equipment, and personnel. Improving the management of assets leads to the delivery of greater value to ratepayers, stockholders, and society. EPRI is sponsoring a broad research program to help utilities effectively apply the tools needed in these changing business conditions, especially the latest in cost and quality management and asset management techniques

  20. Proceedings: 2003 Workshop on Life Cycle Management Planning for Systems, Structures, and Components

    International Nuclear Information System (INIS)

    2003-01-01

    These proceedings of the 2003 EPRI Life Cycle Management Workshop provide nuclear plant owners with an overview of the state of development of methods and tools for performing long-term planning for maintenance, aging management, and obsolescence management of systems, structures, and components important to a plant's long-term safety, power production, and value in a market-driven industry. The proceedings summarize the results of applying life cycle management at several plants

  1. Proceedings: 2003 Radiation Protection Technology Conference

    International Nuclear Information System (INIS)

    2004-01-01

    Health physics professionals within the nuclear industry are continually upgrading their programs with new methods and technologies. The Third Annual EPRI Radiation Protection Technology Conference facilitated this effort by communicating technical developments, program improvements, and experience throughout the nuclear power industry. When viewed from the perspective of shorter outages, diminishing numbers of contract RP technicians and demanding emergent work, this information flow is critical for the industry

  2. Human reliability: an evaluation of its understanding and prediction

    International Nuclear Information System (INIS)

    Joksimovich, V.

    1987-01-01

    This paper presents a viewpoint on the state-of-the-art in human reliability. The bases for this viewpoint are, by and large, research projects conducted by the NUS for the Electric Power Research Institute (EPRI) primarily with the objective of further enhancing the credibility of PRA methodology. The presentation is divided into the following key sections: Background and Overview, Methodology and Data Base with emphasis on the simulator data base

  3. Buying and selling power in the age of competition

    International Nuclear Information System (INIS)

    Douglas, J.

    1994-01-01

    This article describes the market management which is the subject of pioneering research being conducted by EPRI. On the wholesale side, this research centers on the development of powerful analytical methods to support utility decisions regarding new opportunities in the bulk power market. Research on retail market management is concentrated on developing innovative price-differentiated services that can enhance the value of electricity to customers and also foster a utility's long-term financial competitiveness

  4. The utilization of VUJE specialists non-destructive testing qualification at international cooperation with company TECNATOM

    International Nuclear Information System (INIS)

    Kuna, M.

    2006-01-01

    The utilization of VUJE specialists non-destructive testing qualification at cooperation with company TECNATOM. The obtain of QDA qualification for ET examination for possibility of qualified evaluation in the foreign NPP (USA, Brazil). The acquired practical experiences by evaluation of ET data from NPP Angra Brazil and Waltz Mill USA. The obtain of SNT-TC-1A and EPRI qualification for the UT evaluation of penetration tube welds measurements. The practical experience during the measurement on NPP Shearon Harris (Author)

  5. Nuclear power newsletter Vol. 3, no. 4, December 2006

    International Nuclear Information System (INIS)

    2006-12-01

    The topics presented in this newsletter are: The 1st Joint IAEA-EPRI Workshop on Modernization of Instrumentation and Control Systems in Nuclear Power Plants; Message from the Director of the Division of Nuclear Power; Nuclear power plant operation; Management system, infrastructure and training; International Project on Innovative Nuclear Reactors and Fuel Cycles; Technology developments and applications for advanced reactors; Planned meetings in 2007

  6. FRANX. Application for analysis and quantification of the APS fire

    International Nuclear Information System (INIS)

    Snchez, A.; Osorio, F.; Ontoso, N.

    2014-01-01

    The FRANX application has been developed by EPRI within the Risk and Reliability User Group in order to facilitate the process of quantification and updating APS Fire (also covers floods and earthquakes). By applying fire scenarios are quantified in the central integrating the tasks performed during the APS fire. This paper describes the main features of the program to allow quantification of an APS Fire. (Author)

  7. Solar Photovoltaic and Liquid Natural Gas Opportunities for Command Naval Region Hawaii

    Science.gov (United States)

    2014-12-01

    panels made of monocrystalline (c-Si) panels (EPRI, 2010). The price breakdown is as follows: Table 8. Utility-Scale Solar PV Power Plant O&M Costs...Battery Energy Storage System CBA Cost Benefit Analysis CNG Containerized Natural Gas CNRH Command Naval Region Hawaii c-Si Monocrystalline ...of ground-mounted solar-PV panels on the West Loch Peninsula, on Pearl Harbor Naval Base. The second proposed project is a land lease to an

  8. Achieving CANDU excellence through collaboration

    International Nuclear Information System (INIS)

    Dermarkar, F.

    2015-01-01

    All Operators of CANDU/PHWR Worldwide, and AECL, are members of Candu Owners Group (COG). COG has evolved to become primarily an Operators Owners Group with annual turnover of $75M. It is all about value to the members providing a diverse offering of services to meet a broad spectrum of member needs, linking our members together prioritizing and organizing to enable members to access what they need, when they need it. Collaboration benefits both COG and EPRI.

  9. Ergonomic Application on the Work Station Layout

    International Nuclear Information System (INIS)

    Suharyo Widagdo; Darlis

    2003-01-01

    Work station layout in the ideal way has been made. The dimension of the work station is 9.4 m x 7.1 m. The workers to be stationed should feel comfort. This can be done by honoring the dimensions and the sum of the tools that should be stationed and also the free space that should be mention between the tools as state in EPRI, NP-2411. (author)

  10. Application of biotechnology to fossil fuels explored

    Energy Technology Data Exchange (ETDEWEB)

    Haggin, J

    1989-02-13

    A review is presented of the December 1988 symposium on coal, oil and gas biotechnology held in New Orleans, organised by the Institute of Gas Technology. Papers discussed include: opportunities for R D in desulfurization, coal gasification and environmental cleanup; an assessment of the economic constraints that new energy biotechnology must overcome; biotechnology research at EPRI; microbial conversion of coal; bioconversion of low rank coal; and bioremediation of ground containing PAHs. 2 figs.

  11. Walkdown procedure: Seismic adequacy review of safety class 3 ampersand 4 commodities in 2736-Z ampersand ZB buildings at PFP facility

    International Nuclear Information System (INIS)

    Ocoma, E.C.

    1995-01-01

    Seismic evaluation of existing safety class (SC) 3 and non-SC 4 commodities at the Plutonium Finishing Plant (PFP) is integrated into an area walkdown program. Field walkdowns of potential PFP seismic deficiencies associated with structural failure and falling will be performed using the DOE SQUG/EPRI methodology. Potential proximity interactions are also addressed. Objective of the walkdown is to qualify as much of the equipment as practical and to identify candidates for further evaluation

  12. Main-coolant-pump shaft-seal guidelines. Volume 3. Specification guidelines. Final report

    International Nuclear Information System (INIS)

    Fair, C.E.; Greer, A.O.

    1983-03-01

    This report presents a set of guidelines and criteria to aid in the generation of procurement specifications for Main Coolant Pump Shaft Seals. The noted guidelines are developed from EPRI sponsored nuclear power plant seal operating experience studies, a review of pump and shaft seal literature and discussions with pump and seal designers. This report is preliminary in nature and could be expanded and finalized subsequent to completion of further design, test and evaluation efforts

  13. BWR and PWR chemistry operating experience and perspectives

    International Nuclear Information System (INIS)

    Fruzzetti, K.; Garcia, S.; Lynch, N.; Reid, R.

    2014-01-01

    It is well recognized that proper control of water chemistry plays a critical role in ensuring the safe and reliable operation of Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). State-of-the-art water chemistry programs reduce general and localized corrosion of reactor coolant system, steam cycle equipment, and fuel cladding materials; ensure continued integrity of cycle components; and reduce radiation fields. Once a particular nuclear plant component has been installed or plant system constructed, proper water chemistry provides a global tool to mitigate materials degradation problems, thereby reducing the need for costly repairs or replacements. Recognizing the importance of proper chemistry control and the value in understanding the relationship between chemistry guidance and actual operating experience, EPRI continues to collect, monitor, and evaluate operating data from BWRs and PWRs around the world. More than 900 cycles of valuable BWR and PWR operating chemistry data has been collected, including online, startup and shutdown chemistry data over more than 10 years (> 20 years for BWRs). This paper will provide an overview of current trends in BWR and PWR chemistry, focusing on plants in the U.S.. Important chemistry parameters will be highlighted and discussed in the context of the EPRI Water Chemistry Guidelines requirements (i.e., those parameters considered to be of key importance as related to the major goals identified in the EPRI Guidelines: materials integrity; fuel integrity; and minimizing plant radiation fields). Perspectives will be provided in light of recent industry initiatives and changes in the EPRI BWR and PWR Water Chemistry Guidelines. (author)

  14. The future of GPS-based electric power system measurements, operation and control

    Energy Technology Data Exchange (ETDEWEB)

    Rizy, D.T. [Oak Ridge National Lab., TN (United States); Wilson, R.E. [Western Area Power Administration, Golden, CO (United States); Martin, K.E.; Litzenberger, W.H. [Bonneville Power Administration, Portland, OR (United States); Hauer, J.F. [Pacific Northwest National Lab., Richland, WA (United States); Overholt, P.N. [Dept. of Energy, Washington, DC (United States); Sobajic, D.J. [Electric Power Research Inst., Palo Alto, CA (United States)

    1998-11-01

    Much of modern society is powered by inexpensive and reliable electricity delivered by a complex and elaborate electric power network. Electrical utilities are currently using the Global Positioning System-NAVSTAR (GPS) timekeeping to improve the network`s reliability. Currently, GPS synchronizes the clocks on dynamic recorders and aids in post-mortem analysis of network disturbances. Two major projects have demonstrated the use of GPS-synchronized power system measurements. In 1992, the Electric Power Research Institute`s (EPRI) sponsored Phase Measurements Project used a commercially available Phasor Measurements Unit (PMU) to collect GPS-synchronized measurements for analyzing power system problems. In 1995, Bonneville Power Administration (BPA) and Western Area Power Administration (WAPA) under DOE`s and EPRI`s sponsorship launched the Wide Area Measurements (WAMS) project. WAMS demonstrated GPS-synchronized measurements over a large area of their power networks and demonstrated the networking of GPS-based measurement systems in BPA and WAPA. The phasor measurement technology has also been used to conduct dynamic power system tests. During these tests, a large dynamic resistor was inserted to simulate a small power system disturbance.

  15. Qualification of RETRAN for simulator applications

    International Nuclear Information System (INIS)

    Harrison, J.F.

    1988-01-01

    The use of full-scope control room replica simulators increased substantially following the accident at Three Mile Island Unit 2. The technical capability required to represent severe events has been included, in varying degrees, in most simulators purchased since the TMI-2 accident. The ability of the instructor to create a large variety of combinations of malfunctions has also greatly expanded. The nuclear industry has developed a standard which establishes the minimum functional requirements for full-scope nuclear control room simulators used for operator training. This standard, ANSI/ANS-3.5, was first issued in 1981 and was reissued in 1985. A method for performing simulator qualification with best estimate analytical data has been proposed in EPRI NP-4243, Analytic Simulator Qualification Methodology. The idea presented there is to choose a set of transients which drive the simulator into all the system conditions (dynamic states) likely to be encountered during operator training. The key observable parameters for each state are compared to analyses performed with the best estimate analytical model The closeness of the comparison determines the fidelity of the simulator. The approach described in EPRI NP-4243 has been adapted for evaluating RETRAN's capability for use in simulator qualification. RETRAN analyses which compare the RETRAN results to plant or test facility data are evaluated with respect to the simulator test matrix documented in EPRI NP-4243

  16. Online Monitoring of Large Centrifugal Pumps in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Emmanuel, Efenji A.; Faragalla, Mohamed M.; Awwal, Arigi M.; Lee, Yong-kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    Online Monitoring detects and diagnoses incipient faults, performs predictive maintenance, and can estimate the Remaining Useful Life (RUL) of Active and Passive Components before they fail. In an effort towards assisting Utility Partners to be proactive in the management of their Assets, the Electric Power Research Institute (EPRI) collaborated with the Idaho National Laboratory (INL) to develop a Fleet-Wide Prognostic and Health Monitoring (FW-PHM) Software Suite. The FW-PHM is a web based diagnostic tools and databases designed for use in commercial NPP. The AFS development process as designed by EPRI can be adapted to Large Centrifugal Pumps (LCP) in Nuclear Power Plants (NPP). For the purpose of this endeavor, the set of LCP considered are Safety Class-Motor Driven-Vertical Centrifugal Pumps for primary flow which includes Safety Injection, Containment Spray, and Residual Heat Removal. Fault Signatures of the LCP for OLM has been developed following the INCOSE V-model systems development approach. The fault types, fault features, and their detection methods and effectiveness for the LCP were established by diligently following the guidelines recommended by EPRI. An optimization of the FS for OLM has been suggested for implementation. As a way of extending this work, a Cost-Benefit Analysis between OLM and the conventional Periodic Maintenance for the LCP in NPP is proposed.

  17. Criteria and methods for estimating external effective dose equivalent from personnel monitoring results: EDE implementation guide. Final report

    International Nuclear Information System (INIS)

    Owen, D.

    1998-09-01

    Title 10 Part 20 of the Code of Federal regulations requires that nuclear power plant licensees evaluate worker radiation exposure using a risk-based methodology termed the effective dose equivalent (EDE). EDE is a measure of radiation exposure that represents an individual's risk of stochastic injury from their exposure. EPRI has conducted research into how photons interact with the body. These results have been coupled with information on how the body's organs differ in their susceptibility to radiation injury, to produce a methodology for assessing the effective dose equivalent. The research and the resultant methodology have been described in numerous technical reports, scientific journal articles, and technical meetings. EPRI is working with the Nuclear Energy Institute to have the EPRI effective dose equivalent methodology accepted by the Nuclear Regulatory Commission for use at US nuclear power plants. In order to further familiarize power plant personnel with the methodology, this report summarizes the EDE research and presents some simple guidelines for its implementing the methodology

  18. Utility requirements for advanced LWR passive plants

    International Nuclear Information System (INIS)

    Yedidia, J.M.; Sugnet, W.R.

    1992-01-01

    LWR Passive Plants are becoming an increasingly attractive and prominent option for future electric generating capacity for U.S. utilities. Conceptual designs for ALWR Passive Plants are currently being developed by U.S. suppliers. EPRI-sponsored work beginning in 1985 developed preliminary conceptual designs for a passive BWR and PWR. DOE-sponsored work from 1986 to the present in conjunction with further EPRI-sponsored studies has continued this development to the point of mature conceptual designs. The success to date in developing the ALWR Passive Plant concepts has substantially increased utility interest. The EPRI ALWR Program has responded by augmenting its initial scope to develop a Utility Requirements Document for ALWR Passive Plants. These requirements will be largely based on the ALWR Utility Requirements Document for Evolutionary Plants, but with significant changes in areas related to the passive safety functions and system configurations. This work was begun in late 1988, and the thirteen-chapter Passive Plant Utility Requirements Document will be completed in 1990. This paper discusses the progress to date in developing the Passive Plant requirements, reviews the top-level requirements, and discusses key issues related to adaptation of the utility requirements to passive safety functions and system configurations. (orig.)

  19. Statistical core design methodology using the VIPRE thermal-hydraulics code

    International Nuclear Information System (INIS)

    Lloyd, M.W.; Feltus, M.A.

    1995-01-01

    An improved statistical core design methodology for developing a computational departure from nucleate boiling ratio (DNBR) correlation has been developed and applied in order to analyze the nominal 1.3 DNBR limit on Westinghouse Pressurized Water Reactor (PWR) cores. This analysis, although limited in scope, found that the DNBR limit can be reduced from 1.3 to some lower value and be accurate within an adequate confidence level of 95%, for three particular FSAR operational transients: turbine trip, complete loss of flow, and inadvertent opening of a pressurizer relief valve. The VIPRE-01 thermal-hydraulics code, the SAS/STAT statistical package, and the EPRI/Columbia University DNBR experimental data base were used in this research to develop the Pennsylvania State Statistical Core Design Methodology (PSSCDM). The VIPRE code was used to perform the necessary sensitivity studies and generate the EPRI correlation-calculated DNBR predictions. The SAS package used for these EPRI DNBR correlation predictions from VIPRE as a data set to determine the best fit for the empirical model and to perform the statistical analysis. (author)

  20. Counterfeit and Fraudulent Items - Mitigating the risk

    International Nuclear Information System (INIS)

    Tannenbaum, Marc

    2011-01-01

    This presentation (slides) provides an overview of the industry's challenges and activities. Firstly, it outlines the differences between counterfeit, fraudulent, suspect, and also substandard items. Notice is given that items could be found not to meet the standard, but the difference in the intent to deceive with counterfeit and fraudulent items is the critical element. Examples from other industries are used which also rely heavily on the assurance of quality for safety. It also informs that EPRI has just completed a report in October 2009 in coordination with other US government agencies and industry organizations; this report, entitled Counterfeit, Substandard and Fraudulent Items, number 1019163, is available for free on the EPRI web site. As a follow-up to this report, EPRI is developing a CFSI Database; any country interested in a collaborative agreement is invited to use and contribute to the database information. Finally, it stresses the importance of the oversight of contractors, training to raise the awareness of the employees and the inspectors, and having a response plan for identified items

  1. U.S. industry response to surry corrosion event

    International Nuclear Information System (INIS)

    Chexal, V.K.; Dietrich, E.B.; Torok, R.C.; Randall, G.A.; Shevde, V.C.; Horowitz, J.S.

    1990-01-01

    On December 9, 1986, a 460 mm (18 inch) diameter carbon steel elbow in the condensate system at Surry Unit-2 failed. The failure occurred as a consequence of thinning of the elbow by erosion-corrosion. Inspections revealed significant thinning of carbon steel sections at numerous locations in the condensate and feedwater piping of both Surry units. The subsequent discovery of thinning at other plants established erosion-corrosion as a generic issue for nuclear and fossil plants. To quickly resolve industry and regulatory concerns associated with single-phase erosion-corrosion, EPRI sought to: (1) find ways to determine where single phase erosion-corrosion is most likely to occur; (2) define accurate and low-cost inspection methods; and (3) identify techniques for preventing further pipe degradation. Erosion-corrosion programs have been conducted in a number of laboratories world-wide. The associated phenomena are complex and depend on the interrelationship of water temperature, water chemistry, component material, flow velocity and the geometry of the flow path (straight, bend, tee, etc.). EPRI supplemented existing data and developed technical products tailored for utility use on the erosion-corrosion issue. This paper describes the U.S. industry response to the Surry event and the related EPRI activities in the corrosion area

  2. Improving performance and reducing costs of cooling towers

    International Nuclear Information System (INIS)

    Bartz, J.A.

    1992-01-01

    Cooling towers represent a significant capital investment at a steam electric power station. In addition, deficiencies in thermal performance can result in major operating penalties of fuel cost, replacement energy, and capacity addition. This paper summarizes two recent EPRI research projects aimed at reducing thermal performance deficiencies and decreasing installed costs of evaporative cooling towers. First, EPRI Research Project 2113, Cooling Tower Performance Prediction and Improvement, is summarized. This project has resulted in published data sets on the measured thermal performance characteristics of a variety of cooling tower packings, computer codes to predict tower performance, and computer code validation through large-scale tower performance measurements. Principal results are contained in an EPRIGEMS software module, Cooling Tower Advisor. This PC- based software contains a tutorial plus codes to predict tower thermal performance, arranged in a user-friendly format. The second EPRI effort, Research Project 2819-10/11, Fabric Structures for Power Plant Applications, has resulted in designs and costs of large structures with shells constructed of recently-developed fabrics. Primary power plant applications for such structures are the shells of natural draft cooling towers and coal-pile covers. Fabric structures offer low initial cost, acceptable life, and seismic superiority, among other advantages. Detailed conceptual designs and installed cost data are reviewed. 8 refs., 9 figs., 3 tabs

  3. Online Monitoring of Large Centrifugal Pumps in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Emmanuel, Efenji A.; Faragalla, Mohamed M.; Awwal, Arigi M.; Lee, Yong-kwan

    2016-01-01

    Online Monitoring detects and diagnoses incipient faults, performs predictive maintenance, and can estimate the Remaining Useful Life (RUL) of Active and Passive Components before they fail. In an effort towards assisting Utility Partners to be proactive in the management of their Assets, the Electric Power Research Institute (EPRI) collaborated with the Idaho National Laboratory (INL) to develop a Fleet-Wide Prognostic and Health Monitoring (FW-PHM) Software Suite. The FW-PHM is a web based diagnostic tools and databases designed for use in commercial NPP. The AFS development process as designed by EPRI can be adapted to Large Centrifugal Pumps (LCP) in Nuclear Power Plants (NPP). For the purpose of this endeavor, the set of LCP considered are Safety Class-Motor Driven-Vertical Centrifugal Pumps for primary flow which includes Safety Injection, Containment Spray, and Residual Heat Removal. Fault Signatures of the LCP for OLM has been developed following the INCOSE V-model systems development approach. The fault types, fault features, and their detection methods and effectiveness for the LCP were established by diligently following the guidelines recommended by EPRI. An optimization of the FS for OLM has been suggested for implementation. As a way of extending this work, a Cost-Benefit Analysis between OLM and the conventional Periodic Maintenance for the LCP in NPP is proposed

  4. The Angra 1 fire PRA project

    International Nuclear Information System (INIS)

    Silva, Luiz E. Massiere de C.; Kassawara, Robert

    2009-01-01

    The Angra 1 Fire PRA (Probabilistic Risk Assessment) is under development by ELETRONUCLEAR jointly with EPRI (Electric Power Research Institute). The project was started January of 2007 and it is foreseen to be finished in the middle of the next year. The study is being conducted according to the newest methodology developed by EPRI and NRC/RES (U.S. Nuclear Regulatory Commission - Office of Regulatory Research) published in 2005 as Fire PRA Methodology for Nuclear Power Facilities (NUREG/CR-6850 or EPRI TR-1011989) [1]. Starting from the Internal Events Angra 1 PRA model Level 1 the project aims to be a comprehensive plant-specific fire analysis to identify the possible consequences of a fire in the plant vital areas which threaten the integrity of systems relevant to the safety, challenging the safety functions and representing a risk of accident that can lead to a core damage. The main tasks include the plant boundary and partitioning, the fire PRA component selection and the identification of the possible fire scenarios (ignition, propagation, detection, extinction and hazards) considering human failure events to establish the fire-induced risk model for quantification of the risk for nuclear core damage taking into account the plant design and its fire protection resources. This work presents a general discussion on the methodology applied to the completed steps of the project. (author)

  5. A Study on the Frequency of Initiating Event of OPR-1000 during Outage Periods

    Energy Technology Data Exchange (ETDEWEB)

    Hong Jae Beol; Jae, Moo Sung [Hanyang Univ., Seoul (Korea, Republic of)

    2013-10-15

    These sources of data did not reflect the latest event data which have occurred during the PWR outage to the frequencies of initiating event Electric Power Research Institute(EPRI) in USA collected the data of loss of decay heat removal during outage from 1989 to 2009 and published technical report. Domestic operating experiences for LOOP is gathered in Operational Performance Information System for Nuclear Power Plant(OPIS). To reduce conservatism and obtain completeness for LPSD PSA, those data should be collected and used to update the frequencies. The frequencies of LOSDC and LOOP are reevaluated using the data of EPRI and OPIS in this paper. Quantification is conducted to recalculate core damage frequency(CDF), since the rate is changed. The results are discussed below. To make an accurate estimate of the initiating events of LPSD PSA, the event data were collected and the frequencies of initiating events were updated using Bayesian approach. CDF was evaluated through quantification. Δ CDF is -40% and the dominant contributor is pressurizer PSV stuck open event. The most of the event data in EPRI TR were collected from US nuclear power plant industry. Those data are not enough to evaluate outage risk precisely. Therefore, to reduce conservatism and obtain completeness for LPSD PSA, the licensee event report and domestic data should be collected and reflected to the frequencies of the initiating events during outage.

  6. Plastic influence functions for calculating J-integral of complex-cracks in pipe

    International Nuclear Information System (INIS)

    Jeong, Jae-Uk; Choi, Jae-Boong; Kim, Moon-Ki; Huh, Nam-Su; Kim, Yun-Jae

    2016-01-01

    In this study, the plastic influence functions, h_1, for estimates of J-integral of a pipe with a complex crack were newly proposed based on the systematic 3-dimensional (3-D) elastic-plastic finite element (FE) analyses by using Ramberg-Osgood (R-O) relation, in which global bending moment, axial tension and internal pressure were considered as loading conditions. Based on the present plastic influence functions, the GE/EPRI-type J-estimation scheme for complex-cracked pipes was suggested, and the results from the proposed J-estimation were compared with the FE results using both R-O fit parameters and actual tensile data of SA376 TP304 stainless steel. The comparison results demonstrate that although the proposed scheme provided sensitive J estimations according to fitting ranges of R-O parameters, it showed overall good agreements with the FE results using R-O relation. Thus, the proposed engineering J prediction method can be utilized to assess instability of a complex crack in pipes for R-O material. - Highlights: • New h_1values of GE/EPRI method for complex-cracked pipes are proposed. • The plastic limit loads of complex-cracked pipes using Mises yield criterion are provided. • The new J estimates of complex-cracked pipes are proposed based on GE/EPRI concept. • The proposed estimates for J are validated against 3-D finite element results.

  7. Comparative Evaluation of In-cabinet Amplification Factor for Devices Mounted in Electrical Cabinets

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Sung Gook; So, Gihwan; Han, Min Soo [Innose Tech Co. LTD., Incheon (Korea, Republic of); Kim, Dookie [Kunsan National University, Kunsan (Korea, Republic of)

    2016-10-15

    This study estimated the in-cabinet amplification factors by using various methods. Comparative results are presented in this paper. These instruments must continue to operate during an earthquake and are seismically qualified by a shake table test in which the earthquake input is defined in terms of an in-cabinet response spectrum (ICRS). The ICRS should be estimated prior to seismic qualification of devices mounted in electrical cabinets. EPRI report introduces a simple method to estimate seismic demand on relays mounted on or within such cabinets (in-cabinet seismic demand). If the ICRS generated by amplifying floor response spectra through a constant factor of EPRI report is found to be much higher than the vendor’s test data for relay then a more accurate method is used for generating ICRS. The more accurate methods can range from using finite element analysis, in-situ testing and analysis, and shake table testing of similar cabinets. This study compares the differences of the in-cabinet response spectra estimated by a simple method and a rigorous method. A simple method of EPRI yields larger amplification factors by 4 times than the rigorous method for the same cabinet. If the ICRS generated by amplifying floor response spectra through a constant factor is found to be much higher than the vendor’s test data for relay then a more accurate method is used for generating ICRS.

  8. PM-HIP research for structural and pressuring retaining applications within the electric power industry

    International Nuclear Information System (INIS)

    Gandy, David W.

    2015-01-01

    For more than 60 years now, the nuclear power industry has relied on structural and pressure retaining materials generated via established manufacturing practices such as casting, plate rolling-and-welding, forging, drawing, and/or extrusion. During the past three years, EPRI has been leading the development and introduction of another established process, powder metallurgy and hot Isostatic pressing (PM/HIP), for pressure retaining applications in electric power industry. The research includes assessment of two primary alloys: 316L stainless steel and Grade 91 creep-strength enhanced ferritic steels, for introduction into the ASME Boiler and Pressure Vessel Code. Continuing DOE and EPRI research on other structural/pressure retaining alloys such as Alloy 690, SA 508 Class 1, Alloy 625, hard-facing materials, and others are also underway. This research will have a tremendous impact as we move forward over the next few decades on the selection of new alloys and components for advanced light water reactors and small modular reactors. Furthermore, fabrication of high alloy materials/components may require the use of new manufacturing processes to achieve acceptable properties for higher temperature applications such as those in Generation IV applications. Current research by EPRI and DOE will be reviewed and emphasis will be targeted at advanced applications where PM/HIP may be applied in the future. (authors)

  9. Proceedings of a C.S.N.I. specialist meeting on instrumented pre-cracked Charpy testing

    Energy Technology Data Exchange (ETDEWEB)

    Wullaert, R A [Fracture Control Corp., 340 South Kellogg Avenue, Suite G, Goleta, California 93017 (United States)

    1981-11-15

    This report presents the status of the testing and data analysis procedures for the instrumented pre-cracked Charpy test with emphasis on the application of the test technique to the nuclear industry. The report (Proceedings) consist of invited technical papers by specialists in the field and a synopsis of the comments, conclusions, and recommendations reached in a workshop session. The CSNl-sponsored and EPRI-hosted meeting confirmed both the popularity of the test technique in the nuclear industry and the problems associated with the test technique due to the lack of a national or international consensus standard. Major emphasis in the meeting was devoted to evaluating the existing industry testing procedure (EPRI procedure) and proposed national standards (ASTM, ASK). The EPRI procedures were considered adequate by specialists concerned with engineering applications, but too restrictive by specialists concerned with research applications. As a result of the conference, a compilation of state-of-the-art papers is now available to code and standard committees. Specific comments concerning test and data analysis procedures, applications in the nuclear industry, and future research areas are also contained in the proceedings

  10. Quantitative imaging of pO2 in orthotopic murine gliomas: hypoxia correlates with resistance to radiation.

    Science.gov (United States)

    Yasui, Hironobu; Kawai, Tatsuya; Matsumoto, Shingo; Saito, Keita; Devasahayam, Nallathamby; Mitchell, James B; Camphausen, Kevin; Inanami, Osamu; Krishna, Murali C

    2017-10-01

    Hypoxia is considered one of the microenvironmental factors associated with the malignant nature of glioblastoma. Thus, evaluating intratumoural distribution of hypoxia would be useful for therapeutic planning as well as assessment of its effectiveness during the therapy. Electron paramagnetic resonance imaging (EPRI) is an imaging technique which can generate quantitative maps of oxygen in vivo using the exogenous paramagnetic compound, triarylmethyl and monitoring its line broadening caused by oxygen. In this study, the feasibility of EPRI for assessment of oxygen distribution in the glioblastoma using orthotopic U87 and U251 xenograft model is examined. Heterogeneous distribution of pO 2 between 0 and 50 mmHg was observed throughout the tumours except for the normal brain tissue. U251 glioblastoma was more likely to exhibit hypoxia than U87 for comparable tumour size (median pO 2 ; 29.7 and 18.2 mmHg, p = .028, in U87 and U251, respectively). The area with pO 2 under 10 mmHg on the EPR oximetry (HF10) showed a good correlation with pimonidazole staining among tumours with evaluated size. In subcutaneous xenograft model, irradiation was relatively less effective for U251 compared with U87. In conclusion, EPRI is a feasible method to evaluate oxygen distribution in the brain tumour.

  11. A study on the steam generator data base and the evaluation of chemical environment

    International Nuclear Information System (INIS)

    Yang, Kyung Rin; Yoo, Je Hyoo; Lee, Eun He; Hong, Kwang Pum

    1990-01-01

    In order to make steam generator data base, the basic plant information and water quality control data on the steam generators of the PWR nuclear power plant operating in the world have been collected by EPRI. In this project, the basic information and water quality control data of the domestic PWR nuclear power plants were collected to make steam generator data base on the basic of the EPRI format table, and the computerization of them was performed. Also, the technical evaluation of chemical environments on steam generator of the Kori 2 plant chemists. Workers and researchers working at the research institute and universities and so on. Especially, it is able to be used as a basic plant information in order to develop an artificial intellegence development system in the field on the technical development of the chemical environment. The scope and content of the project are following. The data base on the basic information data in domestic PWR plant. The steam generator data base on water quality control data. The evaluation on the chemical environment in the steam generators of the Kori 2 plant. From previous data, it is concluded as follows. The basic plant information on the domestic PWR power plant were computerized. The steam generator data base were made on the basis of EPRI format table. The chemical environment of the internal steam generators could be estimated from the analytical evaluation of water quality control data of the steam generator blowdown. (author)

  12. Full system chemical decontamination used in nuclear decommissioning

    International Nuclear Information System (INIS)

    Elder, George; Rottner, Bernard; Braehler, Georg

    2012-01-01

    The decommissioning of nuclear power stations at the end of the operational period of electricity generation offers technical challenges in the safe dismantling of the facility and the minimization of radioactive waste arising from the decommissioning activities. These challenges have been successfully overcome as demonstrated by decommissioning of the first generation of nuclear power plants. One of the techniques used in decommissioning is that of chemical decontamination which has a number of functions and advantages as given here: 1. Removal of contamination from metal surfaces in the reactors cooling systems. 2. Reduction of radioactive exposure to decommissioning workers 3. Minimization of metal waste by decontamination and recycling of metal components 4. Control of contamination when dismantling reactor and waste systems 5. Reduction in costs due to lower radiation fields, lower contamination levels and minimal metal waste volume for disposal. One such chemical decontamination technology was developed for the Electric Power Research Institute (EPRI) by Bradtec (Bradtec is an ONET Technologies subsidiary) and is known as the EPRI DFD system. This paper gives a description of the EPRI DFD system, and highlights the experience using the system. (orig.)

  13. Diagnostic and Prognostic Models for Generator Step-Up Transformers

    Energy Technology Data Exchange (ETDEWEB)

    Vivek Agarwal; Nancy J. Lybeck; Binh T. Pham

    2014-09-01

    In 2014, the online monitoring (OLM) of active components project under the Light Water Reactor Sustainability program at Idaho National Laboratory (INL) focused on diagnostic and prognostic capabilities for generator step-up transformers. INL worked with subject matter experts from the Electric Power Research Institute (EPRI) to augment and revise the GSU fault signatures previously implemented in the Electric Power Research Institute’s (EPRI’s) Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software. Two prognostic models were identified and implemented for GSUs in the FW-PHM Suite software. INL and EPRI demonstrated the use of prognostic capabilities for GSUs. The complete set of fault signatures developed for GSUs in the Asset Fault Signature Database of the FW-PHM Suite for GSUs is presented in this report. Two prognostic models are described for paper insulation: the Chendong model for degree of polymerization, and an IEEE model that uses a loading profile to calculates life consumption based on hot spot winding temperatures. Both models are life consumption models, which are examples of type II prognostic models. Use of the models in the FW-PHM Suite was successfully demonstrated at the 2014 August Utility Working Group Meeting, Idaho Falls, Idaho, to representatives from different utilities, EPRI, and the Halden Research Project.

  14. The market for photovoltaic (PV) technology

    International Nuclear Information System (INIS)

    Frantzis, L.; Vejtasa, K.M.

    1993-01-01

    This paper describes a study that was intended to provide the Electric Power Research Institute (EPRI) with a market analysis for photovoltaic (PV) technologies under development by EPRI and others. The analysis was to focus on markets and factors leading to significant incremental growth for PV demand, large enough to support more efficient scale PV manufacturing capacity. EPRI anticipates that PV ultimately could provide grid-connected power, however, the 1995--2010 market dynamics are uncertain. The specific objectives of this study, therefore, were to: determine what major future domestic US markets for PV technologies will emerge and provide enough volume to support significant improvements in manufacturing costs through manufacturing economies of scale; provide insight on what is needed to gain acceptance of PV technologies for electric power generation in those major markets; provide insight on when investments in demonstration and manufacturing facilities should be made and what is needed to be successful in each element of the business that these markets could support (e.g., technology development, manufacturing, sales, installation, and service); and provide key insights on the requirements for commercial success of PV in the utility sector

  15. Nondestructive Evaluation Program: Progress in 1986

    International Nuclear Information System (INIS)

    1987-07-01

    The increasing cost of equipment for power generating plants and the potential increases in productivity and safety available through rapidly developing Nondestructive Evaluation (NDE) technology led EPRI to initiate a Nondestructive Evaluation Program in 1974. To date, the major focus has been on light water reactor inspection problems; however, increased application to other systems is now under way. This report presents a comprehensive review of the EPRI effort in the NDE area. Most of the report consists of contractor-supplied progress reports on each current project. An organizational plan of the program is presented in overview. In addition, organization from several viewpoints is presented, e.g., in-service inspection operators, R and D personnel, and utility representatives. The report summarizes significant progress made since the previous EPRI Special Report NP-4315-SR was issued in May 1986. Section 1 contains information about the program organization, and the sections that follow contain contractor-supplied progress reports of each current project. The progress reports are grouped by plant components - pipe, pressure vessel, steam generator and boiler tubes, and turbine. In addition, Part 6 is devoted to discussions of technology transfer

  16. Annular array technology for nondestructive turbine inspection. Final report

    International Nuclear Information System (INIS)

    Light, G.M.

    1986-05-01

    The Electric Power Research Institute (EPRI) funded Southwest Research Institute (SwRI) to fabricate and functionally test phased array transducers and an electronic control system with the intent of evaluating the phased array technology for use in the inspection of turbine disks. During this program a 13-element annular array and associated phased array electronics were fabricated and tested and the results of the tests compared to those predicted by theory. The prototype system performed well within the expected limits, and EPRI funded further work to fabricate and test a production unit. The production system consisted of a 25-element annular array and a 25-channel electronics system that had both pulser and receiver delay circuitry. In addition, during the program it was determined that miniaturized hybrid pulser/preamps would be needed to allow the phased array to work over distances exceeding 9.1 meters (30 feet) from the electronics. A circuit developed by SwRI was utilized and found to produce good pulsing capability that did not suffer from impedance mismatch. EPRI also funded (under a separate contract) the fabrication of a small scale static turbine test bed and a full scale dynamic test bed that contained full scale turbine geometries. These test beds were fabricated to enable the production phased array system to be evaluated on turbine disk surfaces. 26 figs

  17. On-line monitoring applications at nuclear power plants. A risk informed approach to calibration reduction

    International Nuclear Information System (INIS)

    Shankar, Ramesh; Hussey, Aaron; Davis, Eddie

    2003-01-01

    On-line monitoring of instrument channels provides increased information about the condition of monitored channels through accurate, more frequent evaluation of each cannel's performance over time. This type of performance monitoring is a methodology that offers an alternate approach to traditional time-directed calibration. EPRI's strategic role in on-line monitoring is to facilitate its implementation and cost-effective use in numerous applications at power plants. To this end, EPRI has sponsored an on-line monitoring implementation project at multiple nuclear plants specifically intended to install and use on-line monitoring technology. The selected on-line monitoring method is based on the Multivariate State Estimation Technique. The project has a planned three-year life; seven plants are participating in the project. The goal is to apply on-line monitoring to all types of power plant applications and document all aspects of the implementation process in a series of EPRI reports. These deliverables cover installation, modeling, optimization, and proven cost-benefit. This paper discusses the actual implementation of on-line monitoring to various nuclear plant instrument systems. Examples of detected instrument drift are provided. (author)

  18. Task 2 - Limits for High-Frequency Conducted Susceptibility Testing - CS114 (NRC-HQ-60-14-D-0015)

    Energy Technology Data Exchange (ETDEWEB)

    Wood, Richard Thomas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ewing, Paul D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Moses, Rebecca J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-09-01

    A principal focus of Task 2 under this project was for ORNL to evaluate the basis for susceptibility testing against high-frequency conducted interference and to establish recommendations to resolve concerns about the severity of test limits for the conducted susceptibility (CS) test, CS114, from MIL-STD-461. The primary concern about the test limit has been characterized by the EPRI EMI Working Group in the following terms: Demonstrating compliance with the CS114 test limits recommended in TR-102323 has proven to be problematic, even for components that have been tested to commercial standards and demonstrated proper operation in industrial applications [6]. Specifically, EPRI notes that the CS114 limits approved in regulatory documents are significantly higher than those invoked by the US military and similar commercial standards in the frequency range below 200 kHz. For this task, ORNL evaluated the original approach to establishing the test limit, EPRI technical findings from a review of the limit, and the regulatory basis through which the currently approved limits were accepted. Based on this analysis, strategies have been developed regarding changes to the CS114 limit that can resolve the technical concerns raised by the industry. Guided by the principles that reasonable assurance of safety must not be compromised but excessive conservatism should be reduced, recommendations on a suitable basis for a revised limit have been developed and can be incorporated into the planned Revision 2 of RG 1.180.

  19. Considerations in the development and implementation of a maintenance robot for nuclear power facilities

    International Nuclear Information System (INIS)

    Rohrabacher, A.; Carlton, R.; Gelhaus, F.

    1987-01-01

    The Nuclear Power Division of the Electric Power Research Institute (EPRI) began its automated nuclear plant maintenance research (research project 2232) in 1982 with surveys of domestic and Japanese ongoing and potential uses of robotic systems in nuclear power facilities. After studying these potential research areas, EPRI initiated a three-pronged effort. All surveys concluded that a mobile system for general environmental, visual, and auto surveillance would be beneficial, and EPRI contracted for the development and evaluation of the Surveyor robot. Work also began to catalog existing systems and to quantify the methodology that a utility could use to optimally complete the plant-mission, robot-system selection process. The conceptualizing phase of the effort defined the necessary physical attributes for the machine to perform a variety of maintenance tasks. Characteristics such as mobility, strength, conditions of service, materials of construction, tool functional requirements, facility interfaces, and operator interface were defined to the extent practical. Substantial versatility is required for the variability of the targeted maintenance tasks and for the variability of facility layouts and designs found throughout the nuclear industry. A key contribution to this development effort comes from the project's Utility Advisors Group. The contract's host utility provides membership to lead this group, and that company will train in the use of the machine for 6 months prior to utilizing it in their power plant for 2 yr

  20. Simulation for estimation of hydrogen sulfide scavenger injection dose rate for treatment of crude oil

    Directory of Open Access Journals (Sweden)

    T.M. Elshiekh

    2015-12-01

    Full Text Available The presence of hydrogen sulfide in the hydrocarbon fluids is a well known problem in many oil and gas fields. Hydrogen sulfide is an undesirable contaminant which presents many environmental and safety hazards. It is corrosive, malodorous, and toxic. Accordingly, a need has been long left in the industry to develop a process which can successfully remove hydrogen sulfide from the hydrocarbons or at least reduce its level during the production, storage or processing to a level that satisfies safety and product specification requirements. The common method used to remove or reduce the concentration of hydrogen sulfide in the hydrocarbon production fluids is to inject the hydrogen sulfide scavenger into the hydrocarbon stream. One of the chemicals produced by the Egyptian Petroleum Research Institute (EPRI is EPRI H2S scavenger. It is used in some of the Egyptian petroleum producing companies. The injection dose rate of H2S scavenger is usually determined by experimental lab tests and field trials. In this work, this injection dose rate is mathematically estimated by modeling and simulation of an oil producing field belonging to Petrobel Company in Egypt which uses EPRI H2S scavenger. Comparison between the calculated and practical values of injection dose rate emphasizes the real ability of the proposed equation.

  1. Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012

    Energy Technology Data Exchange (ETDEWEB)

    Nancy J. Lybeck; Vivek Agarwal; Binh T. Pham; Heather D. Medema; Kirk Fitzgerald

    2012-09-01

    The Light Water Reactor Sustainability program at Idaho National Laboratory (INL) is actively conducting research to develop and demonstrate online monitoring (OLM) capabilities for active components in existing Nuclear Power Plants. A pilot project is currently underway to apply OLM to Generator Step-Up Transformers (GSUs) and Emergency Diesel Generators (EDGs). INL and the Electric Power Research Institute (EPRI) are working jointly to implement the pilot project. The EPRI Fleet-Wide Prognostic and Health Management (FW-PHM) Software Suite will be used to implement monitoring in conjunction with utility partners: the Shearon Harris Nuclear Generating Station (owned by Duke Energy for GSUs, and Braidwood Generating Station (owned by Exelon Corporation) for EDGs. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for GSUs. GSUs are main transformers that are directly connected to generators, stepping up the voltage from the generator output voltage to the highest transmission voltages for supplying electricity to the transmission grid. Technical experts from Shearon Harris are assisting INL and EPRI in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the FW-PHM Software Suite and tested using data from Shearon-Harris. Parallel research on EDGs is being conducted, and will be reported in an interim report during the first quarter of fiscal year 2013.

  2. Standardization of the cumulative absolute velocity

    International Nuclear Information System (INIS)

    O'Hara, T.F.; Jacobson, J.P.

    1991-12-01

    EPRI NP-5930, ''A Criterion for Determining Exceedance of the Operating Basis Earthquake,'' was published in July 1988. As defined in that report, the Operating Basis Earthquake (OBE) is exceeded when both a response spectrum parameter and a second damage parameter, referred to as the Cumulative Absolute Velocity (CAV), are exceeded. In the review process of the above report, it was noted that the calculation of CAV could be confounded by time history records of long duration containing low (nondamaging) acceleration. Therefore, it is necessary to standardize the method of calculating CAV to account for record length. This standardized methodology allows consistent comparisons between future CAV calculations and the adjusted CAV threshold value based upon applying the standardized methodology to the data set presented in EPRI NP-5930. The recommended method to standardize the CAV calculation is to window its calculation on a second-by-second basis for a given time history. If the absolute acceleration exceeds 0.025g at any time during each one second interval, the earthquake records used in EPRI NP-5930 have been reanalyzed and the adjusted threshold of damage for CAV was found to be 0.16g-set

  3. Seismic hazard characterization of the Eastern United States

    International Nuclear Information System (INIS)

    Bernreuter, D.L.; Savy, J.B.; Mensing, R.W.

    1989-01-01

    The methodology or the authors study evolved from two earlier studies that the Lawrence Livermore National Laboratory (LLNL) performed for the NRC. One study was part of the NRC's Systematic Evaluation Program (SEP) and is simply referred hereafter to as the SEP study. The other study was part of the Seismic Safety Margins Research Program (SSMRP). By the time the authors methodology was firmed up and the calculations performed (i.e. by 1985), the Electric Power Research Institute (EPRI) had embarked on a parallel study. The authors performed a comparative study to help in understanding the reasons for differences in results between the LLNL and the EPRI studies. The three main differences were found to be the minimum magnitude value of the earthquakes contributing to the hazard in the EUS, the ground motion attenuation models, and the fact that LLNL accounted for local site characteristics and EPRI did not. Several years passed between the 1985 study and the application of the methodology to all the sites in the EUS. In recognition of the fact that during that time a considerable amount of research in seismotectonics and in the field of strong ground motion prediction, in particular with the development of the so called random vibration or stochastic approach, NRC decided to follow their recommendations and have a final round of feedback with all their experts prior to finalizing the input to the analysis

  4. Creep fracture mechanics analysis for through-wall cracked pipes under widespread creep condition

    International Nuclear Information System (INIS)

    Huh, Nam Su; Kim, Yun Jae; Kim, Young Jin

    2003-01-01

    This paper compares engineering estimation schemes of C * and creep COD for circumferential and axial through-wall cracked pipes at elevated temperatures with detailed 3-D elastic-creep finite element results. Engineering estimation schemes included the GE/EPRI method, the reference stress method where reference stress is defined based on the plastic limit load and the enhanced reference stress method where the reference stress is defined based on the optimized reference load. Systematic investigations are made not only on the effect of creep-deformation behaviour on C * and creep COD, but also on effects of the crack location, the pipe geometry, the crack length and the loading mode. Comparison of the FE results with engineering estimations provides that for idealized power law creep, estimated C * and COD rate results from the GE/EPRI method agree best with FE results. For general creep-deformation laws where either primary or tertiary creep is important and thus the GE/EPRI method is hard to apply, on the other hand, the enhanced reference stress method provides more accurate and robust estimations for C * and COD rate than the reference stress method

  5. Effects of illumination on image reconstruction via Fourier ptychography

    Science.gov (United States)

    Cao, Xinrui; Sinzinger, Stefan

    2017-12-01

    The Fourier ptychographic microscopy (FPM) technique provides high-resolution images by combining a traditional imaging system, e.g. a microscope or a 4f-imaging system, with a multiplexing illumination system, e.g. an LED array and numerical image processing for enhanced image reconstruction. In order to numerically combine images that are captured under varying illumination angles, an iterative phase-retrieval algorithm is often applied. However, in practice, the performance of the FPM algorithm degrades due to the imperfections of the optical system, the image noise caused by the camera, etc. To eliminate the influence of the aberrations of the imaging system, an embedded pupil function recovery (EPRY)-FPM algorithm has been proposed [Opt. Express 22, 4960-4972 (2014)]. In this paper, we study how the performance of FPM and EPRY-FPM algorithms are affected by imperfections of the illumination system using both numerical simulations and experiments. The investigated imperfections include varying and non-uniform intensities, and wavefront aberrations. Our study shows that the aberrations of the illumination system significantly affect the performance of both FPM and EPRY-FPM algorithms. Hence, in practice, aberrations in the illumination system gain significant influence on the resulting image quality.

  6. Demonstration of reliability centered maintenance

    International Nuclear Information System (INIS)

    Schwan, C.A.; Morgan, T.A.

    1991-04-01

    Reliability centered maintenance (RCM) is an approach to preventive maintenance planning and evaluation that has been used successfully by other industries, most notably the airlines and military. Now EPRI is demonstrating RCM in the commercial nuclear power industry. Just completed are large-scale, two-year demonstrations at Rochester Gas ampersand Electric (Ginna Nuclear Power Station) and Southern California Edison (San Onofre Nuclear Generating Station). Both demonstrations were begun in the spring of 1988. At each plant, RCM was performed on 12 to 21 major systems. Both demonstrations determined that RCM is an appropriate means to optimize a PM program and improve nuclear plant preventive maintenance on a large scale. Such favorable results had been suggested by three earlier EPRI pilot studies at Florida Power ampersand Light, Duke Power, and Southern California Edison. EPRI selected the Ginna and San Onofre sites because, together, they represent a broad range of utility and plant size, plant organization, plant age, and histories of availability and reliability. Significant steps in each demonstration included: selecting and prioritizing plant systems for RCM evaluation; performing the RCM evaluation steps on selected systems; evaluating the RCM recommendations by a multi-disciplinary task force; implementing the RCM recommendations; establishing a system to track and verify the RCM benefits; and establishing procedures to update the RCM bases and recommendations with time (a living program). 7 refs., 1 tab

  7. Borated stainless steel joining technology. Final report

    International Nuclear Information System (INIS)

    Smith, R.J.

    1994-12-01

    EPRI had continued investigating the application of borated stainless steel products within the US commercial nuclear power industry through participation in a wide range of activities. This effort provides the documentation of the data obtained in the development of the ASTM-A887 Specification preparation effort conducted by Applied Science and Technology and the most recent efforts for the development of joining technologies conducted under a joint effort by EPRI, Carpenter Technologies and Sandia National Laboratory under a US DOE CRADA program. The data presented in this report provides the basis for the ASTM specification which has been previously unpublished by EPRI and the data generated in support of the Joining Technology research effort conducted at Sandia. The results of the Sandia research, although terminated prior to the completion, confirms earlier data that the degradation of material properties in fusion welded borated stainless steels occurs in the heat affected zone of the weld area and not in the base material. The data obtained also supports the conclusion that the degradation of material properties can be overcome by post weld heat treatment which can result in material properties near the original unwelded metal

  8. Ultrasonic boiler inspection and economic analysis guidelines

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    Boiler tube failures cause approximately 6% availability loss of large fossil-fired power generating plants. This loss can be reduced by systematic approaches using ultrasonic examination and root cause failure analysis methods. Two projects sponsored by EPRI have provided utility engineers with guidelines for performing ultrasonic examinations and with details on 22 types of tube failure mechanisms. A manual has been published that provides descriptions of typical locations, superficial appearances, damage mechanisms, metallurgy, microstructural changes, likely root causes, and potential corrective actions. Application of the principles in the manual is being demonstrated in an EPRI-funded project at 10 electric utilities over the next two years. Guidelines have been published that prescribe the activities necessary for ultrasonic examinations of boiler tubes. Eight essential elements of a boiler examination should be performed to assure that possible economic benefits are obtained. Work was supported by EPRI under RP 1890 and RP 1865. A software package has been developed for effectively planning inspections for wall thinning in fossil-fired boiler tubing. The software assists in minimizing costs associated with maintenance, such as inspection and repair, while the life of the boiler is maximized

  9. Usage of Commercial Grade Programmable Digital Systems in Safety Related Applications

    International Nuclear Information System (INIS)

    Mandic, D.

    2006-01-01

    This paper explains methods and conditions, which if completely and correctly fulfilled, enable an operating NPP (Nuclear Power Plant) licensed and operating in accordance with the US codes and US regulatory requirements to use a commercial grade programmable digital device (PLC - Programmable Digital Controller, digital controller, digital computer or process computer) in a safety related application in a NPP. In mid 80's, when an intensive construction cycle of the new NPPs in the U.S.A. was completed, many equipment manufacturers either disappeared from the market or they abandoned their product lines that were designed and manufactured under 10 CFR Part 50 Appendix B quality assurance program. The quality assurance as defined by 10 CFR Part 50 Appendix B comprises all those planned and systematic actions necessary to provide adequate confidence that a Structure, System or Component (SSC) will perform satisfactorily in service . The operating NPPs faced the problem related to the availability of qualified equipment, components and spare parts. The US NRC (Nuclear Regulatory Commission) recognized that problem timely (Oct. 1978 revision of 10CFR21) and required a commercial grade item to be dedicated before it could be used as a basic component. A special process named Dedication of CGI - Commercial Grade Items if conducted properly, provides reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety related function and, in this respect, is deemed equivalent to an item designed and manufactured under 10 CFR Part 50 Appendix B. After that, the Dedication of CGI has been widely used mostly for relatively simple mechanical, electrical, and IandC components and spare parts. In order to provide guidance to the dedication process, EPRI has issued two documents (EPRI NP-5652 and Supplemental Guidance for EPRI NP-5652). All nuclear power plants, which comply with the US nuclear regulatory requirements, hindered as

  10. Irradiated stainless steel material constitutive model for use in the performance evaluation of PWR pressure vessel internals

    Energy Technology Data Exchange (ETDEWEB)

    Rashid, J.Y.; Dunham, R.S. [ANATECH (United States); Demma, A. [Electric Power Research Institute - EPRI (United States)

    2011-07-01

    Demonstration of component functionality requires analytical simulations of reactor internals behavior. Towards that aim, EPRI has undertaken the development of irradiated material constitutive model and damage criteria for use in global and local finite-element based functionality analysis methodology. The constitutive behavioral regimes of irradiated stainless steel types 316 and 304 materials included in the model consist of: elastic-plastic material response considering irradiation hardening of the stress-strain curve, irradiation creep, stress relaxation, and void swelling. IASCC and degradation of ductility with irradiation are the primary damage mechanisms considered in the model. The material behavior model development consists of two parts: the first part is a user-material subroutine that can interface with a general-purpose finite element computer program to adapt it to the special-purpose of functionality analysis of reactor internals. The second part is a user utility in the form of Excel Spread sheets that permit users to extract a given property, e.g. the elastic-plastic stress-strain curve, creep curve, or void-swelling curve, as function of the relevant independent variables. The development of the model takes full advantage of the significant work that has been undertaken within EPRI's Material Reliability Program (MRP) to improve the knowledge of the material properties of irradiated stainless steels. Data from EPRI's MRP database have been utilized to develop equations that characterize the yield strength, ultimate tensile strength, uniform elongation, total elongation, reduction in area, void swelling and irradiation creep of stainless steels in a PWR environment. It is noted that, while the development of the model's equations has been statistically faithful to the material database, approximations were introduced in the model to ensure appropriate conservatism in the model's application consistently with accepted

  11. Sequestration Resins for Accelerating Removal of Radioactive Contaminants

    International Nuclear Information System (INIS)

    Frattini, Paul-L.; Wells, Daniel-M.; Garcia, Susan-E.; Richard, Kohlmann; Asay, Roger; Yengoyan, Leon

    2012-09-01

    The Electric Power Research Institute (EPRI) is developing sequestration resins that can be used in the treatment of nuclear plant water streams for the enhanced removal of ionic cobalt. EPRI is focusing on three key areas of success: 1. Plant safety. The resins that are synthesized must be fully tested to determine that no leachable species or decomposition products (in the event of a resin bed failure) would be introduced to the plant. 2. Acceptable system performance. The resins are currently being synthesized in a powdered form for use in the reactor water clean-up and fuel pool clean-up systems that utilize pre-coatable filter elements. The resins must have effective flocking behavior; uniform application over the underlay resin and efficient removal from the septa elements after use. Bead type resins are also under development. 3. Enhanced cobalt removal. The resins are expected to out-perform the currently used ion exchange resins in the removal of ionic cobalt. During nuclear plant maintenance or refueling outages, current ion exchange resins may require several days to reduce concentrations of cobalt (for example, radio-cobalt 60 Co and 58 Co) and other activated corrosion products to safe levels in reactor coolant streams. This performance limitation often delays key maintenance activities. EPRI's resins are expected to provide at least a three-fold increase in removal capacity in light water reactor coolants. These resins also offer the potential for higher overall removal efficiencies reducing occupational exposures and waste management costs. This paper addresses issues from the range of novel resin development for radio-cobalt removal from synthesis at the bench-top level through scale-up to demonstration of use in an actual operating nuclear power plant. (authors)

  12. Technical and economic evaluation of controlled disposal options for very low level radioactive wastes

    International Nuclear Information System (INIS)

    Robinson, P.J.; Vance, J.N.

    1990-08-01

    Over the past several years, there has been considerable interest by the nuclear industry in the Nuclear Regulatory Commission (NRC) explicitly defined an activity level in plant waste materials at which the radiological impacts would be so low as to be considered Below Regulatory Concern (BRC). In January 1989, Electric Power Research Institute (EPRI) completed an extensive industry research effort to develop the technical bases for establishing criteria for the disposal of very low activity wastes in ordinary disposal facilities. The Nuclear Management and Resources Council (NUMARC), with assistance from the Edison Electric Institute (EEI) and the Electric Power Research Institute (EPRI), drafted a petition titled: ''Petition for Rulemaking Regarding Disposal of Below Regulatory Concern Radioactive Wastes from Commercial Nuclear Power Plants.'' Subsequent to the industry making a final decision for submittal of the drafted BRC petition, EPRI was requested to evaluate the technical and economic impact of six BRC options. These options are: take no action in pursuing a BRC waste exemption, petition the NRC for authorization to disposal of any BRC waste in any ordinary disposal facility, limit disposal of BRC waste to the nuclear power plant site, limit disposal of BRC waste to the nuclear power plant site and other utility owned property, petition for a mixed waste exemption, and petition for single waste stream exemptions in sequence (i.e. soil, followed by sewage sludge, etc.). The petition and technical bases were written to support the disposal of any BRC waste type in any ordinary disposal facility. These documents do not provide all of the technical and economic information needed to completely assessment the BRC options. This report provides the technical and economic basis for a range of options concerning disposal of very low activity wastes. 3 figs., 20 tabs

  13. Study to define NDE research for inspection of stainless steels

    International Nuclear Information System (INIS)

    Reinhart, E.R.

    1978-08-01

    After the boiling water reactor (BWR) stress corrosion cracking incidents on 4- and 10-inch stainless steel piping, the Electric Power Research Institute (EPRI) organized a round-robin ultrasonic examination of piping removed from service (TPS-75-609). Five inspection teams participated in this program, using both a standard procedure and the individual team procedure. The original intent was to section the piping after the program to evaluate the effectiveness of state-of-the-art ultrasonics in finding stress corrosion cracking. The sectioning was delayed, however, to allow research and development (R and D) groups time to perform basic measurements aimed at determining optimum search unit and instrument characteristics for the ultrasonic examination of stainless steel piping and to study the applicability of various advanced inspection methods. This additional effort was funded as part of an EPRI technical planning study (TPS-75-620), A Study to Define NDE Research for Inspection of Stainless Steels. Inspection methods evaluated in this study included (1) processing of manual scan data using a miniature programmable calculator (Aerojet Nuclear); (2) investigation into the performance characteristics of three experimental ultrasonic transducers (Battelle-Columbus Laboratories); (3) analysis of fundamental ultrasonic response data from intergranular stress corrosion cracks in stainless steels (Southwest Research Institute); and (4) a feasibility study of advanced signal processing and pattern recognition for analyzing flaws in stainless steel piping (Ultrasonics International). The results of the studies compiled in the report have indicated the direction for future research and development and have formed the basis for the recently initiated EPRI Research Project 892, Ultrasonic System Optimization

  14. Considerations in applying on-line IC techniques to BWR's

    International Nuclear Information System (INIS)

    Kaleda, R.J.

    1992-01-01

    Ion-Chromatography (IC) has moved from its traditional role as a laboratory analytical tool to a real time, dynamic, on-line measurement device to follow ppb and sub-ppb concentrations of deleterious impurities in nuclear power plants. Electric Power Research Institute (EPRI), individual utilities, and industry all have played significant roles in effecting the transition. This paper highlights considerations and the evolution in current on-line Ion Chromatography systems. The first applications of on-line techniques were demonstrated by General Electric (GE) under EPRI sponsorship at Rancho Seco (1980), Calvert Cliffs, and McGuire nuclear units. The primary use was for diagnostic purposes. Today the on-line IC applications have been expanded to include process control and routine plant monitoring. Current on-line IC's are innovative in design, promote operational simplicity, are modular for simplified maintenance and repair, and use field-proven components which enhance reliability. Conductivity detection with electronic or chemical suppression and spectrometric detection techniques are intermixed in applications. Remote multi-point sample systems have addressed memory effects. Early applications measured ionic species in the part per billion range. Today reliable part per trillion measurements are common for on-line systems. Current systems are meeting the challenge of EPRI guideline requirements. Today's on-line IC's, with programmed sampling systems, monitor fluid streams throughout a power plant, supplying data that can be trended, stored and retrieved easily. The on-line IC has come of age. Many technical challenges were overcome to achieve today's IC

  15. Technical and regulatory challenges for digital instrumentation and control and control room systems in nuclear plants

    International Nuclear Information System (INIS)

    Torok, R.; Naser, J.; Harris, T.; Keithline, K.

    2006-01-01

    There are several unsettled technical and licensing issues in the areas of instrumentation and control (I and C), human factors, and updated control room designs that need coordinated, proactive industry attention. Some of these issues are already causing protracted regulatory reviews for existing plants, and left untreated, may cause substantial delays and increased costs for new plant combined construction and operating license approvals. Both industry and the NRC will have roles in resolving the key issues and addressing them in future design efforts and regulatory reviews. Where action is needed, the industry will want to minimize costs and risks by defining industry consensus solutions with corresponding technical bases. NEI has formed a working group to coordinate industry efforts and communications with NRC staff. The working group will also help determine priorities and coordinate both new and existing plant resources. EPRI will provide technical input and guidance for the working group. In order to be able to conduct reviews in a timely fashion, the NRC will likely need to enhance and expand staff resources as existing plants are upgraded and new plant reviews become more active. The industry initiative began with a workshop sponsored by EPRI and NEI on March 28-29, 2006, which led to the creation of the NEI working group. The working group has now identified and prioritized important generic issues, established resolution paths and schedules, and identified the roles of various stakeholders including utility companies, EPRI, NEI, vendors and the NRC. Through the course of this initiative I and C issues for both existing and new plants are being addressed. This paper describes the key I and C related technical and regulatory issues and their implications for new and operating plants, and provides a status report on the efforts to resolve them. (authors)

  16. Longitudinal imaging studies of tumor microenvironment in mice treated with the mTOR inhibitor rapamycin.

    Directory of Open Access Journals (Sweden)

    Keita Saito

    Full Text Available Rapamycin is an allosteric inhibitor of mammalian target of rapamycin, and inhibits tumor growth and angiogenesis. Recent studies suggested a possibility that rapamycin renormalizes aberrant tumor vasculature and improves tumor oxygenation. The longitudinal effects of rapamycin on angiogenesis and tumor oxygenation were evaluated in murine squamous cell carcinoma (SCCVII by electron paramagnetic resonance imaging (EPRI and magnetic resonance imaging (MRI to identify an optimal time after rapamycin treatment for enhanced tumor radioresponse. Rapamycin treatment was initiated on SCCVII solid tumors 8 days after implantation (500-750 mm(3 and measurements of tumor pO(2 and blood volume were conducted from day 8 to 14 by EPRI/MRI. Microvessel density was evaluated over the same time period by immunohistochemical analysis. Tumor blood volume as measured by MRI significantly decreased 2 days after rapamycin treatment. Tumor pO(2 levels modestly but significantly increased 2 days after rapamycin treatment; whereas, it decreased in non-treated control tumors. Furthermore, the fraction of hypoxic area (pixels with pO(2<10 mm Hg in the tumor region decreased 2 days after rapamycin treatments. Immunohistochemical analysis of tumor microvessel density and pericyte coverage revealed that microvessel density decreased 2 days after rapamycin treatment, but pericyte coverage did not change, similar to what was seen with anti-angiogenic agents such as sunitinib which cause vascular renormalization. Collectively, EPRI/MRI co-imaging can provide non-invasive evidence of rapamycin-induced vascular renormalization and resultant transient increase in tumor oxygenation. Improved oxygenation by rapamycin treatment provides a temporal window for anti-cancer therapies to realize enhanced response to radiotherapy.

  17. Final Assessment of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, Michael T.; Diaz, Aaron A.; Cinson, Anthony D.; Crawford, Susan L.; Prowant, Matthew S.; Doctor, Steven R.

    2014-03-24

    PNNL conducted a technical assessment of the NDE issues and protocols that led to missed detections of several axially oriented flaws in a steam generator primary inlet dissimilar metal weld at North Anna Power Station, Unit 1 (NAPS-1). This particular component design exhibits a significant outside-diameter (OD) taper that is not included as a blind performance demonstration mock-up within the industry’s Performance Demonstration Initiative, administered by EPRI. For this reason, the licensee engaged EPRI to assist in the development of a technical justification to support the basis for a site-specific qualification. The service-induced flaws at NAPS-1 were eventually detected as a result of OD surface machining in preparation for a full structural weld overlay. The machining operation uncovered the existence of two through-wall flaws, based on the observance of primary water leaking from the dissimilar metal weld. A total of five axially oriented flaws were detected in varied locations around the weld circumference. The field volumetric examination that was conducted at NAPS-1 was a non-encoded, real-time manual ultrasonic examination. PNNL conducted both an initial assessment, and subsequently, a more rigorous technical evaluation (reported here), which has identified an array of NDE issues that may have led to the subject missed detections. These evaluations were performed through technical reviews and discussions with NRC staff, EPRI NDE Center personnel, industry and ISI vendor personnel, and ultrasonic transducer manufacturers, and laboratory tests, to better understand the underlying issues at North Anna.

  18. Concrete containment tests: Phase 2, Structural elements with liner plates: Interim report

    International Nuclear Information System (INIS)

    Hanson, N.W.; Roller, J.J.; Schultz, D.M.; Julien, J.T.; Weinmann, T.L.

    1987-08-01

    The tests described in this report are part of Phase 2 of the Electric Power Research Institute (EPRI) program. The overall objective of the EPRI program is to provide a test-verified analytical method of estimating capacities of concrete reactor containment buildings under internal overpressurization from postulated degraded core accidents. The Phase 2 testing included seven large-scale specimens representing structural elements from reinforced and prestressed concrete reactor containment buildings. Six of the seven test specimens were square wall elements. Of these six specimens, four were used for biaxial tension tests to determine strength, deformation, and leak-rate characteristics of full-scale wall elements representing prestressed concrete containment design. The remaining two square wall elements were used for thermal buckling tests to determine whether buckling of the steel liner plate would occur between anchorages when subjected to a sudden extreme temperature differential. The last of the seven test specimens for Phase 2 represented the region where the wall and the basemat intersect in a prestressed concrete containment building. A multi-directional loading scheme was used to produce high bending moments and shear in the wall/basemat junction region. The objective of this test was to determine if there is potential for liner plate tearing in the junction region. Results presented include observed behavior and extensive measurements of deformations and strains as a function of applied load. The data are being used to confirm analytical models for predicting strength and deformation of containment structures in a separate parallel analytical investigation sponsored by EPRI

  19. Characteristics Testing of the ECT Bobbin Probe for S/G Tube Inspection

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Min Woo; Lee, Hee Jong; Cho, Chan Hee; Yoo, Hyun Joo [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    2010-05-15

    The bobbin probe technique is basically one of the important ECT methods for the steam generator tube integrity assessment that is practiced during each plant outage. The bobbin probe also is the essential component which consists of the whole ECT examination system, and provides a decisive data for the evaluation of tube integrity in compliance with acceptance criteria described in specific procedures. The selection of probe is especially important because the quality of acquired ECT data is determined by the probe design characteristics, such as geometry and operation frequency, and has an important effect on examination results. The Electric Power Research Institute (EPRI) has recently defined the procedures for the qualification of eddy current hardware and technique. These procedures provide two basic methods for qualification. Flawed tube removed from operation, or artificial flaw is required for the original qualification of technique combined with related flaw mechanism. In case where the original qualification has been completed, the concept of equivalency may be used to extend the original qualification to similar probe designs. The qualified acquisition technique may be modified to substitute or replace instruments or probes without re-qualification provided that the range of essential variables defined in the examination technique specification sheet are met. In this case, both the original and replaced instrument or probe shall be characterized utilizing EPRI Guideline supplement 'H1'. This study is the result of the comparative performance evaluation of bobbin coil eddy current probes manufactured by KEPRI and a foreign manufacturer. As a result of this study, although there were minor differences between the two probe types, it was evaluated that the two probes were almost identical in the significant performance characteristics described in the EPRI guideline

  20. Evaluation of internal boiler components and gases using a high-temperature infrared (IR) lens

    Science.gov (United States)

    Hammaker, Robert G.; Colsher, Richard J.; Miles, Jonathan J.; Madding, Robert P.

    1996-03-01

    Fuel accounts for an average of seventy percent of the yearly operational and maintenance costs of all the fossil stations in the United States. This amounts to 30 billion dollars spent for fuel each year. In addition, federal and state environmental codes have been enforcing stricter regulations that demand cleaner environments, such as the reduction of nitrogen oxides (NOx), which are a by-product of the fossil fuel flame. If the burn of the flame inside a boiler could be optimized, the usage of fuel and the amounts of pollution produced would be significantly reduced, and many of the common boiler tube failures can be avoided. This would result in a major dollar savings to the utility industry, and would provide a cleaner environment. Accomplishing these goals will require a major effort from the designers and operators that manufacture, operate, and maintain the fossil stations. Over the past few years re-designed burners have been installed in many boilers to help control the temperatures and shape of the flame for better performance and NOx reduction. However, the measurement of the processes and components inside the furnace, that could assist in determining the desired conditions, can at times be very difficult due to the hostile hot environment. In an attempt to resolve these problems, the EPRI M&D Center and a core group of EPRI member utilities have undertaken a two-year project with various optical manufacturers, IR manufacturers, and IR specialists, to fully develop an optical lens that will withstand the high furnace temperatures. The purpose of the lens is to explore the possibilities of making accurate high temperature measurements of the furnace processes and components in an ever-changing harsh environment. This paper provides an introduction to EPRI's internal boiler investigation using an IR high temperature lens (HTL). The paper describes the objectives, approach, benefits, and project progress.

  1. Low-level waste disposal site selection demonstration

    International Nuclear Information System (INIS)

    Rogers, V.C.

    1984-01-01

    This paper discusses the results of recent studies undertaken at EPRI related to low-level waste disposal technology. The initial work provided an overview of the state of the art including an assessment of its influence upon transportation costs and waste form requirements. The paper discusses work done on the overall system design aspects and computer modeling of disposal site performance characteristics. The results of this analysis are presented and provide a relative ranking of the importance of disposal parameters. This allows trade-off evaluations to be made of factors important in the design of a shallow land burial facility. To help minimize the impact of a shortage of low-level radioactive waste disposal sites, EPRI is closely observing the development of bellweather projects for developing new sites. The purpose of this activity is to provide information about lessons learned in those projects in order to expedite the development of additional disposal facilities. This paper describes most of the major stems in selecting a low-level radioactive waste disposal site in Texas. It shows how the Texas Low-Level Radioactive Waste Disposal Authority started with a wide range of potential siting areas in Texas and narrowed its attention down to a few preferred sites. The parameters used to discriminate between large areas of Texas and, eventually, 50 candidate disposal sites are described, along with the steps in the process. The Texas process is compared to those described in DOE and EPRI handbooks on site selection and to pertinent NRC requirements. The paper also describes how an inventory of low-level waste specific to Texas was developed and applied in preliminary performance assessments of two candidate sites. Finally, generic closure requirements and closure operations for low-level waste facilities in arid regions are given

  2. Air toxics: A new concern for the utility industry

    International Nuclear Information System (INIS)

    Torrens, I.; Chow, W.

    1992-01-01

    The 1990 Clean Air Acts Amendments call for EPA studies on utility emissions of potentially hazardous air pollutants and their impact, prior to any decision on regulation of these emissions. The Electric Power Research Institute is carrying out a comprehensive assessment of air toxics risk assessment, consisting of data compilation and analysis, field measurements of priority air toxics at power plants and test facilities, atmospheric transport and deposition, and health/ecological risk assessment. The paper reports on progress to data and objectives of the EPRI assessment

  3. Advanced light water reactor program at ABB-Combustion Engineering Nuclear Power

    International Nuclear Information System (INIS)

    Cahn, H.

    1990-01-01

    To meet the needs of Electric Utilities ordering nuclear power plants in the 1990s, ABB-Combustion Engineering is developing two designs which will meet EPRI consensus requirements and new licensing issues. The System 80 Plus design is an evolutionary pressurized water reactor plant modelled after the successful System 80 design in operation in Palo Verde and under construction in Korea. System Plus is currently under review by the US Nuclear Regulatory Commission with final design approval expected in 1991 and design certification in 1992. The Safe Integral Reactor (SIR) plant is a smaller facility with passive safety features and modular construction intended for design certification in the late 1990s. (author)

  4. Estimation of damage by inmates of a PWR Reactor neutron irradiation. Project ZIRP; Estimacion del Dano por Irradiacion Neutronica en los Internos de un Reactor PWR. Proyecto ZIRP

    Energy Technology Data Exchange (ETDEWEB)

    Cadenas Mendicoa, A. M.

    2013-07-01

    The study presented here focuses on the analysis of neutron and gamma irradiation damage suffered by the inmates of the JC NPP reactor metallic materials throughout its operational life. Such analysis of radiation are part of a project of great international impact, led by EPRI (Electric Power Research Institute) from the MRP (Materials Reliability Program), which aims to relate the degradation of the properties of metallic materials of the inmates of the reactor, with the conditions of operation and irradiation to which have been subjected during the operational life of the plant.

  5. Implementation of multimode release criteria and dose standard alternatives

    International Nuclear Information System (INIS)

    Klett, R.

    1993-01-01

    The current standard that regulates the disposal of high-level radioactive wastes (HLW) and transuranic (TRU) wastes evaluates the cumulative risk of all repositories with a single derived set of generic release limits. This paper reviews the technical basis, attributes, and deficiencies of the present approach and two alternative modifications and extensions. The alternatives are the multimode release limits applied at the point of release and a dose standard alternative suggested at the first Electric Power Research Institute (EPRI) waste disposal workshop. Methods of developing and applying the alternatives are presented and some suggestions are given for incorporating them in the standards

  6. Working group 4B - human intrusion: Design/performance requirements

    International Nuclear Information System (INIS)

    Channell, J.

    1993-01-01

    There is no summary of the progress made by working group 4B (Human Intrusion: Design/performance Requirements) during the Electric Power Research Institute's EPRI Workshop on the technical basis of EPA HLW Disposal Criteria, March 1993. This group was to discuss the waste disposal standard, 40 CFR Part 191, in terms of the design and performance requirements of human intrusion. Instead, because there were so few members, they combined with working group 4A and studied the three-tier approach to evaluating postclosure performance

  7. Advanced passive technology: A global standard for nuclear plant requirements

    International Nuclear Information System (INIS)

    Novak, V.

    1994-01-01

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

  8. Hybrid Reactor designs in the United States

    International Nuclear Information System (INIS)

    Wolkenhauer, W.C.

    1978-01-01

    This paper reviews the current, active, interrelated Hybrid Reactor development programs in the United States, and offers a probable future course of action for the technology. The Department of Energy (DOE) program primarily emphasizes development of Hybrid Reactors that are optimized for proliferation resistance. The Electric Power Research Institute (EPRI) program concentrates on avenues for Hybrid Reactor commercialization. The history of electrical generation technology has been one of steady movement toward higher power densities and higher quality fuels. An apparent advantage of the Hybrid Reactor option is that it follows this trend

  9. Spanish program of advanced Nuclear Power Plants

    International Nuclear Information System (INIS)

    Marco, M.; Redon, R.

    1993-01-01

    The energy Spanish Plan is promoting some actions within the area of advanced reactors. Efforts are focussed onto the European Program of Advanced Reactors, the Program of Passive Plants (EPRI), European Fast Reactor Project and the APWR-1000 Program of INI. Electrical sector utilities and industrial partners supported by the Administration have organized an steering committee. The program of Passive Plants includes activities on Qualification, design and detailed engineering (Qualification project, SBWR project of G.E. and AP600 Project of Westinghouse. The european project on advanced plants has the following Spanish contribution: Analysis of alternative Dossier on European requisites (EUR) and Design of an European Reactor (EPR)

  10. Stem thrust prediction model for Westinghouse wedge gate valves with linkage type stem-to-disk connection

    International Nuclear Information System (INIS)

    Wang, J.K.; Sharma, V.; Kalsi, M.S.

    1996-01-01

    The Electric Power Research Institute (EPRI) conducted a comprehensive research program with the objective of providing nuclear utilities with analytical methods to predict motor operated valve (MOV) performance under design basis conditions. This paper describes the stem thrust calculation model developed for evaluating the performance of one such valve, the Westinghouse flexible wedge gate valve. These procedures account for the unique functional characteristics of this valve design. In addition, model results are compared to available flow loop and in situ test data as a basis for evaluating the performance of the valve model

  11. Analysis of LBM experiments at LOTUS

    International Nuclear Information System (INIS)

    Stepanek, J.; Davidson, J.W.; Dudziak, D.J.; Haldy, P.A.; Pelloni, S.

    1986-01-01

    A Lithium Blanket Module (LBM) has been designed at General Atomic Company [under subcontract to Princeton Plasma Physics Lab. (PPPL), the Electric Power Research Institute (EPRI) contractor] for testing on the Tokamak Fusion Test Reactor (TFTR). The LBM has both realistic fusion blanket materials and configuration and has been designed for detailed experimental analyses of tritium breeding and neutron flux spatial/spectral distributions. It is ∼ 80 cm 3 and the breeding material is Li 2 O. This configuration will be evaluated experimentally at the LOTUS facility and computationally by the LANL/EIR analysis program

  12. 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

  13. Stem thrust prediction model for Westinghouse wedge gate valves with linkage type stem-to-disk connection

    Energy Technology Data Exchange (ETDEWEB)

    Wang, J.K.; Sharma, V.; Kalsi, M.S. [Kalsi Engineering, Inc., Sugar Land, TX (United States)] [and others

    1996-12-01

    The Electric Power Research Institute (EPRI) conducted a comprehensive research program with the objective of providing nuclear utilities with analytical methods to predict motor operated valve (MOV) performance under design basis conditions. This paper describes the stem thrust calculation model developed for evaluating the performance of one such valve, the Westinghouse flexible wedge gate valve. These procedures account for the unique functional characteristics of this valve design. In addition, model results are compared to available flow loop and in situ test data as a basis for evaluating the performance of the valve model.

  14. Instrumentation and control upgrade evaluation methodology: Final report. Volume 2: Workbook

    Energy Technology Data Exchange (ETDEWEB)

    Bliss, M.; Brown, E.; Florio, F.; Stofko, M.

    1996-07-01

    This workbook accompanies the methodology manual (EPRI TR-104963-V1) which describes how to develop an Upgrade Evaluation Report (UER). A UER is an evaluation that is performed by a nuclear power plant to decide the most cost-effective upgrade to perform (if any) for a previously identified Upgrade Candidate System. A UER defines the utility`s mission and objectives in regards to upgrade candidates, as well as the systems initial costs, benefits to each upgrade, and an initial upgrade schedule to cost-effectively implement system upgrades.

  15. VIPRE-01: a thermal-hydraulic analysis code for reactor cores. Volume 2. User's manual

    International Nuclear Information System (INIS)

    Cuta, J.M.; Koontz, A.S.; Stewart, C.W.; Montgomery, S.D.

    1983-04-01

    VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear energy reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This volume (Volume 2: User's Manual) describes the input requirements of VIPRE and its auxiliary programs, SPECSET, ASP and DECCON, and lists the input instructions for each code

  16. Human equation in operating a nuclear-power plant

    International Nuclear Information System (INIS)

    Barrett, R.S.

    1982-01-01

    The accident at Three Mile Island has forced the nuclear industry to acknowledge a badly neglected aspect of nuclear-power-plant safety - the human equation. The industry now appears to recognize the importance of operator selection, training, motivation, and licensing, and the need to design a system from the point of view of communication, information retrieval, record keeping, and human factors psychology. As a result, the relatively small initiatives that were begun a few years ago by the EPRI are now being greatly expanded

  17. Evaluation of Instrumentation and Dynamic Thermal Ratings for Overhead Lines

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, A. [New York Power Authority, White Plains, NY (United States)

    2013-01-31

    In 2010, a project was initiated through a partnership between the Department of Energy (DOE) and the New York Power Authority (NYPA) to evaluate EPRI's rating technology and instrumentation that can be used to monitor the thermal states of transmission lines and provide the required real-time data for real-time rating calculations. The project included the installation and maintenance of various instruments at three 230 kV line sites in northern New York. The instruments were monitored, and data collection and rating calculations were performed for about a three year period.

  18. Integrated service of charge activities; Servicio integrado de actividades de recarga

    Energy Technology Data Exchange (ETDEWEB)

    Rojo Perez, P. L.; Llibre Fugueras, E.; Alvarez Gonzalez, P.

    2014-07-01

    The set of works that includes a stop for refueling of a nuclear power plant requires a huge effort of coordination between the central and the different contractors finally running the works. These efforts must be consistent with the objectives of the recharge in terms of safety, quality and completion of the program, all of them are listed in the Guide EPRI Effective Refueling Outage Preparation and Execution Guidance. In this context, Tecnatom, Westinghouse and Enusa created the UTE-TWE with the aim of improving the service provided to ANAV for units of Asco I and II and Vandellos II. (Author)

  19. Basic concept and its aims of E-journal of advanced maintenance

    International Nuclear Information System (INIS)

    Miya, Kenzo

    2009-01-01

    This article describes basic concept and aims of EJAM with history of effort to realize the launching of it. It took about three years until launching of the journal through approach to EPRI and negotiation with international publishing companies. It consists of three major articles. They are 1) general articles, 2) academic papers and 3) maintenance technique to be applied to repairing of components of nuclear power plants. All together of these articles may contribute to understanding of clear image of what maintenance is in this journal. Finally future image of this journal is described in light of maintenance evolution. (author)

  20. Knowledge management: an analysis of the tools of expert knowledge capture

    International Nuclear Information System (INIS)

    Fernandez Larcher, A.

    2009-01-01

    This work proposes the revision of the strategies and tools used to elicit and capture expert knowledge, particularly those suggested by the EPRI and the IAEA. The main objective of this paper consists of examining the effectiveness and scope of the methodologies proposed, in order to apply them and make them suitable according to our institutional context. This article emphasizes the value and usefulness of the interview's methods with the aim of implementing some of them to the activities created and organized by CNEA Nuclear Knowledge Management Group, especially to the ConRRad Project. (author)

  1. 1980 survey and evaluation of utility conservation, load management, and solar end-use projects. Volume 3: utility load management projects. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    The results of the 1980 survey of electric utility-sponsored energy conservation, load management, and end-use solar energy conversion projects are described. The work is an expansion of a previous survey and evaluation and has been jointly sponsored by EPRI and DOE through the Oak Ridge National Laboratory. There are three volumes and a summary document. Each volume presents the results of an extensive survey to determine electric utility involvement in customer-side projects related to the particular technology (i.e., conservation, solar, or load management), selected descriptions of utility projects and results, and first-level technical and economic evaluations.

  2. Evaluation of the Frequencies for Canister Inspections for SCC

    Energy Technology Data Exchange (ETDEWEB)

    Stockman, Christine [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-02-02

    This report fulfills the M3 milestone M3FT-15SN0802042, “Evaluate the Frequencies for Canister Inspections for SCC” under Work Package FT-15SN080204, “ST Field Demonstration Support – SNL”. It reviews the current state of knowledge on the potential for stress corrosion cracking (SCC) of dry storage canisters and evaluates the implications of this state of knowledge on the establishment of an SCC inspection frequency. Models for the prediction of SCC by the Japanese Central Research Institute of Electric Power Industry (CRIEPI), the United States (U.S.) Electric Power Research Institute (EPRI), and Sandia National Laboratories (SNL) are summarized, and their limitations discussed.

  3. A study on prediction of metal loss by flow-accelerated corrosion in the CANDU NPP secondary piping systems

    International Nuclear Information System (INIS)

    Shim, S. H.; Song, J. S.; Yoon, K. B.; Hwang, K. M.; Jin, T. E.; Lee, S. H.; Kim, W. S.

    2001-01-01

    Flow-Accelerated Corrosion(FAC) is a phenomenon that results in metal loss from piping, vessels, and equipment made of carbon steel. FAC occurs only under certain conditions of flow, chemistry, geometry, and material. Unfortunately, those conditions are in much of the high-energy piping in nuclear and fossil-fueled power plants. Also, for domestic NPP secondary pipings whose operating time become longer, more evidences of FAC have been reported. The authors are studying on FAC management using CHECWORKS, computer code developed by EPRI. This paper is on the prediction results of metal loss by FAC in the one of CANDU type NPP secondary piping systems

  4. Survey and assessment of conventional software verification and validation techniques

    International Nuclear Information System (INIS)

    Miller, L.A.; Groundwater, E.; Mirsky, S.M.

    1993-02-01

    Reliable software is required for nuclear power plant applications. Verification and validation (V ampersand V) techniques may be applied during software development to help eliminate errors that can inhibit the proper operation of digital systems and that may cause safety problems. EPRI and the NRC are cosponsoring this investigation to determine the best strategies for V ampersand V of expert system software. The strategy used for a particular system will depend on the complexity of the software and the level of integrity required. This report covers the first task in the investigation of reviewing methods for V ampersand V of conventional software systems and evaluating them for use with expert systems

  5. R and M practices in commercial aviation

    International Nuclear Information System (INIS)

    Matteson, T.D.

    1985-01-01

    During 1982-83, Los Alamos Technical Associates (LATA) and American Management Systems (AMS) conducted an extensive review of design and operations practices in the commercial air transport industry focused on reliability and maintenance for the Electric Power Research Institute (EPRI). The genesis of this review was a discussion of the technical and environmental similarities of the commercial air transport and commercial nuclear power communities and the potential opportunities for experience transfer from air transport to nuclear power. This paper focuses on those similarities believed to be of particular interest to the nuclear power community

  6. Topical Report 5: Sorbent Performance Report

    Energy Technology Data Exchange (ETDEWEB)

    Krutka, Holly; Sjostrom, Sharon

    2011-05-31

    ADA-ES has completed an extensive sorbent screening program funded primarily through DOE NETL cooperative agreement DE-NT0005649 with support from EPRI and industry cost-share participants. Tests were completed on simulated and actual flue gas. The overall project objective is to address the viability and accelerate development of a solid-based postcombustion CO2 capture technology that can be retrofit to the existing fleet of coal-fired power plants. An important component of the viability assessment was to evaluate the state of development of sorbents and measure key performance characteristics under realistic operating conditions.

  7. Critical heat flux correlation analysis for PWR reactors with low mass flow

    International Nuclear Information System (INIS)

    Carajilescov, Pedro

    1996-01-01

    The major limit in the thermalhydraulic design of water cooled reactors consists in the occurrence of critical heat flux, which is verified by correlation of large range of validity. In the present work, the major design correlations were analyzed, through comparisons with experimental data, for utilization in PWR with low mass flux in the core. The results show that the EPRI correlation, with modifications, gives conservative results, from the safety point of view, with lower data spreading, being the most indicated for the reactor thermal design. (author)

  8. Yankee Rowe SPDS development and its validation and verification

    International Nuclear Information System (INIS)

    Candon, D.; Cain, D.

    1986-01-01

    The decision to proceed with EPRI on a prototypical Safety Parameter Display System (SPDS) was made by Yankee Atomic Electric Company management. The general direction to the implementors was to decide from whom would the SPDS be designed, to decide how the SPDS would coincidentally support the twin goals of meeting the regulations and the corporate objective to generate electricity safely and efficiently, and to decide what was known and proven in the arena of computer graphics to minimize cognitive dissonance between the final product SPDS and the operators

  9. Fossil power plant automation

    International Nuclear Information System (INIS)

    Divakaruni, S.M.; Touchton, G.

    1991-01-01

    This paper elaborates on issues facing the utilities industry and seeks to address how new computer-based control and automation technologies resulting from recent microprocessor evolution, can improve fossil plant operations and maintenance. This in turn can assist utilities to emerge stronger from the challenges ahead. Many presentations at the first ISA/EPRI co-sponsored conference are targeted towards improving the use of computer and control systems in the fossil and nuclear power plants and we believe this to be the right forum to share our ideas

  10. Qualification issues: the rest of the iceberg

    International Nuclear Information System (INIS)

    Bonzon, L.L.; Luna, R.E.

    1978-01-01

    Reactor safety has been a primary concern since the beginning of commercial power reactor development. But only since the IEEE became actively involved (circa-1970), through IEEE-323-1971 and its predecessor drafts, has the qualification of selected Class 1 equipment been formalized and intensified. Currently EPRI and the USNRC are funding significant qualification research programs. However, these current research topics address only a few of the issues and there are more to come. A review of recent achievements and a discussion of some issues still to be encountered are presented

  11. Steam Generator Owners Group PWR secondary water chemistry guidelines

    International Nuclear Information System (INIS)

    Welty, C.S. Jr.; Green, S.J.

    1985-01-01

    In 1981 the Steam Generator Owners Group (SGOG), a group of domestic and foreign pressurized water reactor (PWR) owners, developed and issued the PWR secondary water chemistry guidelines. The guidelines were prepared in response to the growing recognition that a majority of the problems causing reduced steam generator reliability (e.g., denting, wasteage, pitting, etc.) were related to secondary (steam) side water purity. The guidelines were subsequently issued as an Electric Power Research Institute (EPRI) report. In 1984 they were revised to reflect industry experience in adopting the original issuance and to incorporate new information on causes of corrosion damage. The guidelines have been endorsed and their adoption recommended by the SGOG

  12. Electropolishing of replacement steam generator channel heads at Millstone-2 PWR

    International Nuclear Information System (INIS)

    Hudson, M.J.B.; Raney, H.; Raney, D.; Spalaris, C.N.

    1992-07-01

    A field application of EPRI-developed steam generator electropolishing technique was performed at Millstone-2 PWR. The process was qualified under previous programs on a laboratory scale, but it was thought appropriate to scale up application to full size components. Replacement of steam generators at Millstone-2 provided a unique opportunity to demonstrate that electropolishing can be applied safely and at a cost which was judged to be recoverable after a small number of fuel cycles. The project, preparation, electropolishing and cleanup, was completed at the reactor site in 25 working days. An alternate, less costly electrolyte solution was qualified for use in future applications

  13. Condenser performance monitoring and cleaning

    International Nuclear Information System (INIS)

    Walden, J.V.

    1998-01-01

    The main condenser at Ginna Station was retubed from admiralty brass to 316 stainless steel. A condenser performance monitoring spreadsheet was developed using EPRI guidelines after fouling was discovered. PEPSE computer models were used to determine the power loss and confirm the spreadsheet results. Cleaning of the condenser was performed using plastic scrubbers. Condenser performance improved dramatically following the cleaning. PEPSE, condenser spreadsheet performance, and actual observed plant data correlated well together. The fouling mechanism was determined to be a common lake bacteria and fungus growth which was combined with silt. Chlorination of the circulating water system at the allowable limits is keeping the biofouling under control

  14. Design tools for computer-generated display of information to operators

    International Nuclear Information System (INIS)

    O'Brien, J.F.; Cain, D.G.; Sun, B.K.H.

    1985-01-01

    More and more computers are being used to process and display information to operators who control nuclear power plants. Implementation of computer-generated displays in power plant control rooms represents a considerable design challenge for industry designers. Over the last several years, the EPRI has conducted research aimed at providing industry designers tools to meet this new design challenge. These tools provide guidance in defining more 'intelligent' information for plant control and in developing effective displays to communicate this information to the operators. (orig./HP)

  15. Machinery Vibration Monitoring Program at the Savannah River Site

    International Nuclear Information System (INIS)

    Potvin, M.M.

    1990-01-01

    The Reactor Maintenance's Machinery Vibration Monitoring Program (MVMP) plays an essential role in ensuring the safe operation of the three Production Reactors at the Westinghouse Savannah River Company (WRSC) Savannah River Site (SRS). This program has increased machinery availability and reduced maintenance cost by the early detection and determination of machinery problems. This paper presents the Reactor Maintenance's Machinery Vibration Monitoring Program, which has been documented based on Electric Power Research Institute's (EPRI) NP-5311, Utility Machinery Monitoring Guide, and some examples of the successes that it has enjoyed

  16. Next Generation Attenuation Relationships for the Eastern United States (NGA-East)

    Energy Technology Data Exchange (ETDEWEB)

    Mahin, Stephen [Univ. of California, Berkeley, CA (United States); Bozorgnia, Yousef [Univ. of California, Berkeley, CA (United States)

    2016-04-11

    This is a progress report to DOE for project Next Generation Attenuation for Central & Eastern US (NGA-East).This progress report consists of numerous monthly progress segments starting June 1, 2010 until December 31, 2015. Please note: the December 2015 progress report was issued in January 2016 due to the final university financial reporting at the end of this project. For each month, there is a technical progress list, and an update on the financial progress of the project. As you know, this project is jointly funded by the DOE, US Nuclear Regulatory Commission (NRC) and Electric Power Research Institute (EPRI). Thus, each segment includes financial progress for these three funding agencies.

  17. Pressurized fluidized-bed combustion technology exchange workshop

    Energy Technology Data Exchange (ETDEWEB)

    ,

    1980-04-01

    The pressurized fluidized-bed combustion technology exchange workshop was held June 5 and 6, 1979, at The Meadowlands Hilton Hotel, Secaucus, New Jersey. Eleven papers have been entered individually into EDB and ERA. The papers include reviews of the US DOE and EPRI programs in this area and papers by Swedish, West German, British and American organizations. The British papers concern the joint program of the USA, UK and FRG at Leatherhead. The key factor in several papers is the use of fluidized bed combustors, gas turbines, and steam turbines in combined-cycle power plants. One paper examines several combined-cycle alternatives. (LTN)

  18. Feasibility study on the rod ejection accident analysis with RETRAN-MASTER code system

    International Nuclear Information System (INIS)

    Kim, Y. H.; Lee, C. S.

    2003-01-01

    KEPRI has been developed the in-house methodology for non-LOCA safety analyses based on the codes and methodologies of vendors and EPRI. Using the methodology, the rod ejection accident, which is classified into the generic accident analysis category of reactivity insertion accident in primary system, has been analyzed with RETRAN-MASTER code system. And the feasibility of the coupled code system has been verified by the review of the results. Furthermore, to assess the important parameters to the accident, the sensitivity analyses have been carried out over some parameters

  19. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1999-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  20. Expert systems for assisting in design reviews

    International Nuclear Information System (INIS)

    Brtis, J.S.; Johnson, W.J.; Weber, N.; Naser, J.

    1990-01-01

    This paper discusses Sargent and Lundy's (S and L's) use of expert system technologies to computerize the procedures used for engineering design reviews. This paper discusses expert systems and the advantages that result from using them to computerize the decision-making process. This paper also discusses the design review expert systems that S and L has developed to perform fire protection and ALARA (as low as reasonably achievable) design reviews, and is currently developing for the Electric Power Research Institute (EPRI) to perform 10 CFR 50.59 safety reviews

  1. Fiscal year 1989 DOE budget authorization: Environmental research and development. Hearing before the Subcommittee on Natural Resources, Agriculture Research and Environment of the Committee on Science, Space, and Technology, US House of Representatives, One Hundredth Congress, Second Session, March 31, 1988

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    A number of government officials from US DOE, US GAO, as well as representatives from EPRI and Martin Marietta Energy Systems, Inc. testified at a hearing on the Department of Energy's FY 1989 budget request for the Environment, Safety and Health Program. The issues of major concern were: whether DOE's facilities pose less of a threat to human health and the environment than they did in 1985; whether DOE facilities are safer places to work than they were in 1985; and whether DOE's facilities are better neighbors to those who live and work in the community than they were in 1985

  2. Evaluation of selected parameters on exposure rates in Westinghouse designed nuclear power plants

    International Nuclear Information System (INIS)

    Bergmann, C.A.

    1989-01-01

    During the past ten years, Westinghouse under EPRI contract and independently, has performed research and evaluation of plant data to define the trends of ex-core component exposure rates and the effects of various parameters on the exposure rates. The effects of the parameters were evaluated using comparative analyses or empirical techniques. This paper updates the information presented at the Fourth Bournemouth Conference and the conclusions obtained from the effects of selected parameters namely, coolant chemistry, physical changes, use of enriched boric acid, and cobalt input on plant exposure rates. The trends of exposure rates and relationship to doses is also presented. (author)

  3. Designing nuclear power plants for improved operation and maintenance

    International Nuclear Information System (INIS)

    1996-09-01

    The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig

  4. Component failures that lead to reactor scrams

    International Nuclear Information System (INIS)

    Burns, E.T.; Wilson, R.J.; Lim, E.Y.

    1980-04-01

    This report summarizes the operating experience scram data compiled from 35 operating US light water reactors (LWRs) to identify the principal components/systems related to reactor scrams. The data base utilized to identify the scram causes is developed from a EPRI-utility sponsored survey conducted by SAI coupled with recent data from the USNRC Gray Books. The reactor population considered in this evaluation is limited to 23 PWRs and 12 BWRs because of the limited scope of the program. The population includes all the US NSSS vendors. It is judged that this population accurately characterizes the component-related scrams in LWRs over the first 10 years of plant operation

  5. Methodology and application of the WIMS-D4M fission product data

    International Nuclear Information System (INIS)

    Mo, S.C.

    1995-01-01

    The WIMS-D4 code has been modified (WIMS-D4m) to generate burn-up dependent microscopic cross sections for use in full core depletion calculations. The calculation of neutron absorption by fission products can be obtained from a reduced fission-product-chain model that includes the 135 Xe and 149 Sm chains, and a lumped fission product to account for the absorption by fission products not explicitly treated. Burn-up calculations were performed for the ANS MEU core using WIMS and EPRI-CELL cross sections. The calculated eigenvalues and material loadings are in good agreements

  6. RackSaver neutron absorbing device development and testing

    International Nuclear Information System (INIS)

    Lambert, R.; O'Leary, P.; Roberts, P.

    1996-01-01

    Siemens Power Corporation (SPC), in cooperation with the Electric Power Research Institute (EPRI), has developed the RackSaver neutron absorbing insert. The RackSaver insert can be installed onto spent nuclear fuel assemblies to replace deteriorating Boraflex neutron absorbing material installed in some spent-fuel storage racks. This paper describes results of a development and in-pool demonstration program performed to support potential utilization of the RackSaver neutron absorbing insert by affected utilities. The program objective was to advance the RackSaver concept into a field-demonstrated product. This objective was accomplished through three phases: design, licensing and criticality evaluations, and demonstration testing

  7. Electric Power Research Institute Environmental Control Technology Center Report to the Steering Committee

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1998-01-12

    Operations and maintenance continued this month at the Electric Power Research Institute's (EPRI's) Environmental Control Technology Center (ECTC). Testing for the month involved the Dry Sorbent Injection (DSI) test block with the Carbon Injection System. The 1.0 MW Cold-Side Selective Catalytic Reduction (SCR) unit, the 0.4 MW Mini-Pilot Wet Scrubber, and the 4.0 MW Pilot Wet Scrubber remained idle this month in a cold-standby mode and were inspected regularly. These units remain available for testing as future project work is identified.

  8. Overview of the U.S. inspection capability demonstration program for CRDM penetrations

    International Nuclear Information System (INIS)

    Melton, M.; Whitaker, D.; Ammirato, F.; Pathania, R.

    1994-01-01

    The US PWR Owners have developed a coordinated program to demonstrate the effectiveness of procedures for inspection of the Control Rod Drive Mechanism (CRDM) nozzle penetrations. The purpose of the inspections is to detect inside surface Primary Water Stress Corrosion Cracking (PWSCC). Reactor vessel manufacturers, PWR Owners Groups, and EPRI are participating in this cooperative program. Flaw detection, sizing, and location capability will be assessed in the program using realistic full-scale mockups containing intentional defects. The program is expected to be completed by January 1, 1994 and be available for qualification work at that time. The demonstration program is scheduled to become operational in 1993 to support 1994 and future inspections

  9. Enhance pump reliability through improved inservice testing

    International Nuclear Information System (INIS)

    Healy, J.J.

    1990-01-01

    EPRI has undertaken a study to assess the effectiveness of existing testing programs to accurately monitor and predict performance changes before either pump performance degrades or an actual failure occurs. Anticipated changes in inservice testing techniques are directed towards enhancing the validity of test data, ensuring its repeatability, and avoiding deterioration of the pump assembly. There is a new-found interest in test programs of all types that has occurred, in part, because of an increase in reported pump degradation and pump failure. Inservice testing of pumps, which has long been a basis for assuring operability, has apparently produced an opposite effect; namely, the appearance of a reduction in reliability

  10. Millstone 3 condensate dissolved gas monitoring

    International Nuclear Information System (INIS)

    Burns, T.F.; Grondahl, E.E.; Snyder, D.T.

    1988-01-01

    Condensate dissolved oxygen problems at Millstone Point Unit 3 (MP3) were investigated using the Dissolved Gas Monitoring System developed by Radiological and Chemical Technology, Inc. under EPRI sponsorship. Argon was injected into the turbine exhaust basket tips to perform a dissolved gas transport analysis and determine steam jet air ejector gas removal efficiency. The operating configuration of the steam jet air ejector system was varied to determine the effect on gas removal efficiency. Following circulating water chlorination, the gas removal efficiency was determined to evaluate the effect of condenser tube fouling on steam jet air ejector performance

  11. High temperature corrosion in gasifiers

    Directory of Open Access Journals (Sweden)

    Bakker Wate

    2004-01-01

    Full Text Available Several commercial scale coal gasification combined cycle power plants have been built and successfully operated during the last 5-10 years. Supporting research on materials of construction has been carried out for the last 20 years by EPRI and others. Emphasis was on metallic alloys for heat exchangers and other components in contact with hot corrosive gases at high temperatures. In this paper major high temperature corrosion mechanisms, materials performance in presently operating gasifiers and future research needs will be discussed.

  12. Steam generator chemical cleaning demonstration test No. 1 in a pot boiler

    International Nuclear Information System (INIS)

    Key, G.L.; Helyer, M.H.

    1981-04-01

    The effectiveness of the Electric Power Research Institute (EPRI Mark I) chemical cleaning solvent process was tested utilizing a 12 tube pot boiler that had previously been fouled and dented under 30 days of high chloride fault chemistry operation. Specifically, the intent of this chemical cleaning test was to: (1) dissolve sludge from the tubesheet, (2) remove non-protective magnetite from dented tube/support crevice regions, and (3) quantify the extent of corrosion of steam generator material during the test. Two laboratory cleaning demonstrations of 191 and 142 hours were performed

  13. Comparison of On-Line Maintenance Support Tools

    International Nuclear Information System (INIS)

    Simic, Z.; Follen, S. M.; Mikulicic, V.

    1998-01-01

    Modeling approach to on-line risk monitoring is today in a rapid developing phase. For that reason number of different solutions are available. This paper will attempt to present existing approaches to address on-line risk modeling problem Starting with description of on-line risk monitoring issues in general, then following by presentation of existing software tools (EPRI's Safety Monitor, Equipment Out of Service Monitor, and ORAM-SENTINEL) the current state of the art in this area will be demonstrated. Finally, conclusions and ideas will be outlined. (author)

  14. Nuclear energy: Moving ahead with confidence

    International Nuclear Information System (INIS)

    DeVine, J.C. Jr.

    1986-01-01

    This paper presents a perspective on the future of nuclear generated electrical power in this country, from the viewpoint of the electric utility industry. Also discussed is an Advanced Light Water Reactor (ALWR) Program established by the Electric Power Research Institute to provide leadership to utility industry efforts to revive the nuclear power option in the United States. The author describes the scope and structure of the EPRI program, the institute's vision of the main design characteristics of the ALWR, and thoughts about how the conceptual work now in progress can lead to the construction of an actual power plant

  15. A comparative analysis of the effect of gaseous fission products release on the thermal behaviour of oxide fuel rods

    International Nuclear Information System (INIS)

    Totev, T.L.; Kolev, I.G.

    1992-01-01

    Four different models of gaseous fission product release are compared in order to assess the relative effect of thermal characteristics of the fuel rods. The results show that the use of Weisman and EPRI models at a high burnup (over 50000 MW.d/tU) leads to almost the same figures of maximum fuel temperature and gas gap thermal conductivity. The use of Beyer-Hann (Betelle) and Pazdera-Valach (Rzez) models leads to under prediction of the fuel element thermal characteristics. A conclusion has been made that the Weisman model is the most suitable for the WWER-type fuel elements behaviour prediction. 10 refs., 7 figs

  16. The temperature dependence of the tensile properties of thermally treated Alloy 690 tubing

    International Nuclear Information System (INIS)

    Harrod, D.L.; Gold, R.E.; Larsson, B.; Bjoerkman, G.

    1992-01-01

    Tensile tests were run in air on full tube cross-sections of 22.23 mm OD by 1.27 mm wall thickness Alloy 690 steam generator production tubes from ten (10) heats of material at eight (8) temperatures between room temperature and 760 degrees C. The tubing was manufactured to specification requirements consistent with the EPRI guidelines for Alloy 690 tubing. The room temperature stress-strain curves are described quite well by the Voce equation. Ductile fracture by dimpled rupture was observed at all test temperatures. The elevated temperature tensile properties are compared with design data given in the ASME Code

  17. Development of the electroacoustic dewatering (EAD) process for fine/ultrafine coal: Second quarterly progress report period ending 31 March 1989

    Energy Technology Data Exchange (ETDEWEB)

    None

    1989-04-18

    Battelle, in cooperation with the Electric Power Research Institute (EPRI), Ashbrook-Simon-Hartley (ASH), Kaiser Engineers (KE), Lewis Corporation, and Prof. S.H. Chiang of the University of Pittsburgh, is developing an advanced process for the dewatering of fine and ultrafine coals. The advanced process, called Electroacoustic Dewatering (EAD), capitalizes on the adaptation of synergistic effects of electric and acoustic fields to a commercial belt filter press design that is used in many other applications. The EAD equipment is described. 2 figs.

  18. Hydrogen mixing study (HMS) in LWR type containments

    International Nuclear Information System (INIS)

    Travis, J.R.

    1983-01-01

    A numerical technique has been developed for calculating the full three-dimensional time-dependent Navier-Stokes equations with multiple speies transport. The method is a modified form of the Implicit Continuous-fluid Eulerian (ICE) technique to solve the governing equations for low Mach number flows where pressure waves and local variations in compression and expansion are not significant. Large density variations, due to thermal and species concentration gradients, are accounted for without the restrictions of the classical Boussinesq approximation. Calculations of the EPRI/HEDL standard problems verify the feasibility of using this finite-difference technique for analyzing hydrogen mixing within LWR containments

  19. Key issues for low-cost FGD installations

    Energy Technology Data Exchange (ETDEWEB)

    DePriest, W.; Mazurek, J.M. [Sargent & Lundy LLC, Chicago, IL (United States)

    1995-12-01

    This paper will discuss various methods for installing low-cost FGD systems. The paper will include a discussion of various types of FGD systems available, both wet and dry, and will compare the relative cost of each type. Important design issues, such as use of spare equipment, materials of construction, etc. will be presented. An overview of various low-cost construction techniques (i.e., modularization) will be included. This paper will draw heavily from Sargent & Lundy`s database of past and current FGD projects together with information we gathered for several Electric Power Research Institute (EPRI) studies on the subject.

  20. IMAGE information monitoring and applied graphics software environment. Volume 4. Applications description

    International Nuclear Information System (INIS)

    Hallam, J.W.; Ng, K.B.; Upham, G.L.

    1986-09-01

    The EPRI Information Monitoring and Applied Graphics Environment (IMAGE) system is designed for 'fast proto-typing' of advanced concepts for computer-aided plant operations tools. It is a flexible software system which can be used for rapidly creating, dynamically driving and evaluating advanced operator aid displays. The software is written to be both host computer and graphic device independent. This four volume report includes an Executive Overview of the IMAGE package (Volume 1), followed by Software Description (Volume II), User's Guide (Volume III), and Description of Example Applications (Volume IV)

  1. Evaluation of new technology for detection of erosion-corrosion

    International Nuclear Information System (INIS)

    Walker, S.M.; Martinez, E.

    1994-01-01

    Faster and more accurate methods of wall thickness measurement have received considerable attention by utilities. Examination without removing insulation has been of particularly high interest because insulation removal is the largest component of the inspection cost. Several inspection systems have been developed which are touted as applicable to erosion corrosion detection through insulation. The Electric Power Research Institute (EPRI) Nondestructive Evaluation (NDE) Center has recently evaluated two of these systems. During the evaluation, accuracy and repeatability measurements were made on insulated pipe of known thickness

  2. The economic aspect of transition to power units with supercritical steam parameters

    Energy Technology Data Exchange (ETDEWEB)

    V.R. Kotler

    2007-09-15

    Information on the development and use of power units for supercritical and ultrasupercritical steam parameters in the United States, as well as in Europe and Japan, is presented. It is shown that increasing the parameters of steam reduces not only the fuel consumption, but also the specific emissions of toxic and greenhouse gases. Results of a calculation carried out at the EPRI (the United States) are presented, which show that it is advisable to construct power units for supercritical parameters only at certain (sufficiently high) price of the fuel being fired.

  3. Examining work structure in nuclear power plants

    International Nuclear Information System (INIS)

    Bauman, M.B.; Boulette, M.D.; Van Cott, H.P.

    1985-01-01

    This paper describes the assessment of the work structure of ten nuclear power plants. Work structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Questionnaires given to a cross-section of personnel at the plants were the primary source of data collection. Structured ''critical incident'' interviews were conducted to verify the questionnaire results. The study revealed that a variety of work structure factor problem areas do exist in nuclear power plants. The paper highlights a prioritized set of candidate research themes to be considered in EPRI's Work Structure and Performance Research Program

  4. Maintainability design guide

    International Nuclear Information System (INIS)

    Pack, R.W.

    1985-01-01

    The Human Factors Design Guide for Maintainability provides guidance for systematically incorporating good human factors techniques into the design of power plants. The guide describes a means of developing a comprehensive program plan to ensure compliance with the human factors approaches specified by the utility. The guide also provides specific recommendations for design practices, with examples, bases, and references. The recommendations are formatted for easy use by nuclear power plant design teams and by utility personnel involved in specification and design review. The guide was developed under EPRI research project RP2166-4 and is currently being published

  5. Experience on implementing risk-oriented in-service inspection at NPP in USA

    International Nuclear Information System (INIS)

    Grebenyuk, Yu.P.; Zaritskij, N.S.; Kovyrshin, V.G.; Kostenko, S.P.

    2001-01-01

    Experience of implementing risk-oriented in-service inspection (RIISI) of pipelines at the US NPP analyzed. RIISI processes according to the methodologies developed by Westinghouse and EPRI are described and compared. The information is addressed concerning practical matters of RIISI implementing at NPP Beaver Valley and Arkansas Nuclear One. Regulatory activity of the US NRC while implementing NRC at the US NPP. It is shown that using RIISI at NPP is aimed at improvement of examination efficiency, decreasing costs and occupational dose loads while inspecting pipelines

  6. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  7. Experimental prediction of tube support interaction characteristics in steam generators: Volume 2, Westinghouse Model 51 flow entrance region: Topical report

    International Nuclear Information System (INIS)

    Haslinger, K.H.

    1988-06-01

    Tube-to-tube support interaction characterisitics were determined experimentally on a single tube, multi-span geometry, representative of the Westinghouse Model 51 steam generator economizer design. Results, in part, became input for an autoclave type wear test program on steam generator tubes, performed by Kraftwerk Union (KWU). More importantly, the test data reported here have been used to validate two analytical wear prediction codes; the WECAN code, which was developed by Westinghouse, and the ABAQUS code which has been enhanced for EPRI by Foster Wheeler to enable simulation of gap conditions (including fluid film effects) for various support geometries

  8. Evaluation of practicality of ASME code, Section XI

    International Nuclear Information System (INIS)

    Mattu, R.K.; Lauderdale, J.R.; Liu, S.N.; Lance, J.J.

    2004-01-01

    Many nuclear power plants have found that it is impractical or unduly burdensome to comply with some ASME Boiler and Pressure Code provisions and have sought relief from those provisions from the Nuclear Regulatory Commission. An Electric Power Research Institute (EPRI) project is evaluating such Code provisions and alternatives to them that will meet the safety intent of the Code with less burden on utilities. The methodology is to extract data from an on-line data base of relief requests since 1980, analyse the data to identify burdensome provisions for which there are satisfactory alternatives, and recommend changes in the Code to the ASME. (author)

  9. Transactions of the Twentieth Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 20th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 21--23, 1992. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included

  10. Software quality - how is it achieved?

    International Nuclear Information System (INIS)

    Straker, E.A.

    1986-01-01

    Although software quality can't be quantified, the tools and techniques to achieve high quality are available. As management stresses the need for definable software quality programs from vendors and subcontractors and provides the incentives for these programs, the quality of software will improve. EPRI could provide the leadership in establishing guidelines for a balanced software quality program and through workshops provide training to utility staff and management on the methods for evaluating the characteristics of quality software. With the more complex systems discussed at this workshop and particularly with the trend toward the use of artificial intelligence, the importance of quality software will grow dramatically

  11. Study of electric and magnetic fields on transmission lines using a computer simulation program

    International Nuclear Information System (INIS)

    Robelo Mojica, Nelson

    2011-01-01

    A study was conducted to determine and reduce levels of electric and magnetic fields with different configurations used by the Instituto Costarricense de Electricidad in power transmission lines in Costa Rica. The computer simulation program PLS-CADD with EPRI algorithm has been used to obtain field values close to those actual to lines easements that have worked to date. Different configurations have been compared on equal terms and the lowest levels of electric and magnetic fields are determined. The most appropriate configuration of the tower has been obtained and therefore has decreased exposure to electromagnetic fields people, without affecting the energy demand of the population. (author) [es

  12. Invasion of the striped mollusks

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Introduced to this country only five years ago, the prolific zebra mussel has infested the Great Lakes and has already begun to move into fresh waters beyond the region. Dense populations in utility water systems have caused serious problems, reducing plant efficiency and blocking lines used for cooling and fire fighting. Experts say the striped mollusk has the potential to become the industry's worst biological problem, possibly affecting 70% of US power plants. While it appears that the invader is here to stay, EPRI and others continue to develop and refine techniques to control mussel growth

  13. An assessment of seismic margins in nuclear plant piping

    International Nuclear Information System (INIS)

    Chen, W.P.; Jaquay, K.R.; Chokshi, N.C.; Terao, D.

    1995-01-01

    Interim results of an ongoing program to assist the U.S. Nuclear Regulatory Commission (NRC) in developing regulatory positions on the seismic analyses of piping and overall safety margins of piping systems are reported. Results of reviews of previous seismic testing, primarily the Electric Power Research Institute (EPRI)/NRC Piping and Fitting Dynamic Reliability Program, and assessments of the ASME Code, Section III, piping seismic design criteria as revised by the 1994 Addenda are reported. Major issues are identified herein only. Technical details are to be provided elsewhere. (author). 4 refs., 2 figs

  14. Alliance created to study wind-generated power potential

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    Wind-generated power may get a boost from a new consortium of companies that have joined together to expand the potential across the country for this cheap, renewable energy source. Niagara Mohawk Power Corporation has announced that it will join with the Pacific Gas and Electric Company (PG ampersand E), the Electric Power Research Institute (EPRI) and US Windpower, Inc., in developing an advanced, 33-meter, variable-speed wind turbine that reduced the cost and improves the power quality of wind energy. The majority of the estimated $20 million cost will be provided by US Windpower

  15. Down-selection of candidate alloys for further testing of advanced replacement materials for LWR core internals

    Energy Technology Data Exchange (ETDEWEB)

    Was, Gary [Univ. of Michigan, Ann Arbor, MI (United States). Applied Physics Program; Leonard, Keith J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Tan, Lizhen [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-09-01

    Life extension of the existing nuclear reactors imposes irradiation of high fluences to structural materials, resulting in significant challenges to the traditional reactor materials such as type 304 and 316 stainless steels. Advanced alloys with superior radiation resistance will increase safety margins, design flexibility, and economics for not only the life extension of the existing fleet but also new builds with advanced reactor designs. The Electric Power Research Institute (EPRI) teamed up with Department of Energy (DOE) Light Water Reactor Sustainability Program to initiate the Advanced Radiation Resistant Materials (ARRM) program, aiming to identify and develop advanced alloys with superior degradation resistance in light water reactor (LWR)-relevant environments by 2024.

  16. Development of a portable, high-energy radiographic source

    International Nuclear Information System (INIS)

    Reinhart, E.R.; Wenk, S.A.; Schonberg, R.G.; Mixon, G.L.

    1979-01-01

    The Electric Power Research Institute (EPRI) is sponsoring a two-year program to develop a portable, high-energy (3 to 4 MeV) radiographic system for inservice and repair inspections of components at nuclear power stations. The basic design concept uses a lightweight, portable linear accelerator (LINAC). The design objectives, concepts employed, and progress to date are described. Specific potential applications and accompanying radiographic techniques are discussed, along with the novel beam angulation devices to permit utilization in areas of highly restricted access

  17. Advances in water chemistry control for BWRs and PWRs

    International Nuclear Information System (INIS)

    Wood, C.J.

    1997-01-01

    This paper is an overview of the effects of water chemistry developments on the current operation of nuclear power plants in the United States, and the mitigation of corrosion-related degradation processes and radiation field build-up processes through the use of advanced water chemistry. Recent modifications in water chemistry to control and reduce radiation fields are outlined, including revisions to the EPRI water chemistry guidelines for BWRs and PWR primary and secondary systems. The change from a single water chemistry specification for all plants to a set of options, from which a plant-specific chemistry programme can be defined, is described. (author)

  18. The future of nuclear I and C applications

    International Nuclear Information System (INIS)

    Chexal, V.K.; Lang, J.F.; Marston, T.U.; Stahlkopf, K.E.

    1991-01-01

    In response to industry's recognition that a substantial portion of the nuclear plant I and C capability in the U.S. is outdated and without vendor support, EPRI has set a strategic goal to complete the modernization of I and C systems in at least 10 nuclear plants by the year 2000. Cooperation is being sought from suppliers, utilities, and government agencies. The draft I and C plan is now out for industry review and feedback. Based on this paper the plan is revised to take advantage of industry insights. The next step will be to select contractors and alliance partners, and get the work underway

  19. Designing nuclear power plants for improved operation and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig.

  20. Distributed systems for protecting nuclear power stations

    International Nuclear Information System (INIS)

    Jover, P.

    1980-05-01

    The advantages of distributed control systems for the control of nuclear power stations are obviously of great interest. Some years ago, EPRI, (Electric Power Research Institute) showed that multiplexing the signals is technically feasible, that it enables the availability specifications to be met and costs to be reduced. Since then, many distributed control systems have been proposed by the manufacturers. This note offers some comments on the application of the distribution concept to protection systems -what should be distributed- and ends with a brief description of a protection system based on microprocessors for the pressurized power stations now being built in France [fr