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

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

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

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

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

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

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

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)

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)

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

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

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

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

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)

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)

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

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

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

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

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)

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

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

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)

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

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

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

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

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

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

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.

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

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

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

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

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)

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

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

'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

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.

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

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.

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.

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

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

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

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.

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.

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)

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

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

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

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

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).

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.

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.)

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

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

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

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.

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.

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

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)

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)

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

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

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

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

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

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

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

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

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

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

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

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

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

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.)

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

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)

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

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

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.

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

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)

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

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

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.)

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

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

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.

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

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.

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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)

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

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.

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

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

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)

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)

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.

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

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

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

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

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

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

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

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

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

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)

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

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)

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)

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.

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

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)

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

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.

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

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

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.

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.

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

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.

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

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

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

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

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

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.

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

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

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

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

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)

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.

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.)

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.)

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

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

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

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

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.

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

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)

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

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.

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.)

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.

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.

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

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

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.

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.)

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

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

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

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

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

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

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

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.

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

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

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

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)

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

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.

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

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

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

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

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

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.)

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).

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

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

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)

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

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)

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.

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.

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.)

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)

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

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.

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)

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

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)

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

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.

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)

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

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

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

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

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)

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

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.)

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.

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

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

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

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

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

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

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

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.)

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.

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

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

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

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

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.)

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

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.

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.

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

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

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)

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

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

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)

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.

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)

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.

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

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)

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.

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

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

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

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

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.

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.

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

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.

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

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.

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)

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)

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

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...

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

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)

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.

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

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

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,

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

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

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.)

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

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

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.

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

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.

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

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.)

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.

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

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

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

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

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

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

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

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

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.

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

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.

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

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.

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

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

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.

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.

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...

Investigating Pigment Radicals in Black Rice Using HPLC and Multi-EPR.

Science.gov (United States)

Nakagawa, Kouichi; Maeda, Hayato

2017-01-01

We investigated the location and distribution of paramagnetic species in black and white rice using electron paramagnetic resonance (EPR), X-band (9 GHz) EPR imaging (EPRI), and HPLC. EPR primarily detected two paramagnetic species in black rice, which were identified as a stable radical and Mn 2+ species, based on the g values and hyperfine components of the EPR signals. The signal from the stable radical appeared at g ≈ 2.00 and was relatively strong and stable. Subsequent noninvasive two-dimensional (2D) EPRI revealed that this stable radical was primarily located in the pigmented region of black rice, while very few radicals were observed in the rice interior. Pigments extracted from black rice were analyzed using HPLC; the major compound was found to be cyanidin-3-glucoside. EPR and HPLC results indicate that the stable radical was only found within the pigmented region of the rice, and that it could either be cyanidin-3-glucoside, or one of its oxidative decomposition products.

Reactor safety research - visible demonstrations and credible computations

Energy Technology Data Exchange (ETDEWEB)

Loewenstein, W B; Divakaruni, S M

1985-11-01

EPRI has been conducting nuclear safety research for a number of years with the primary goal of assuring the safety and reliability of the nuclear plants. The visibility is emphasized by sponsoring or participating in large scale test demonstrations to credibly support the complex computations that are the basis for quantification of safety margins. Recognizing the success of the airline industry in receiving favorable public perception, the authors compare the design and operation practices of the airline industry with those of the nuclear industry practices to identify the elements contributing to public concerns and unfavorable perceptions. In this paper, authors emphasize the importance of proper communications of research results to the public in a manner that non-specialists understand. Further, EPRI supported research and results in the areas of source term, seismic and structural engineering research, analysis using probabilistic risk assessment (PRA), quantification of safety margins, digital technology development and implementation, and plant transient and performance evaluations are discussed in the paper. (orig./HP).

SHARP - a framework for incorporating human interactions into PRA studies

International Nuclear Information System (INIS)

Hannaman, G.W.; Joksimovich, V.; Spurgin, A.J.; Worledge, D.H.

1985-01-01

Recently, increased attention has been given to understanding the role of humans in the safe operation of nuclear power plants. By virtue of the ability to combine equipment reliability with human reliability probabilistic risk assessment (PRA) technology was deemed capable of providing significant insights about the contributions of human interations in accident scenarios. EPRI recognized the need to strengthen the methodology for incorporating human interactions into PRAs as one element of their broad research program to improve the credibility of PRAs. This research project lead to the development and detailed description of SHARP (Systematic Human Application Reliability Procedure) in EPRI NP-3583. The objective of this paper is to illustrate the SHARP framework. This should help PRA analysts state more clearly their assumptions and approach no matter which human reliability assessment technique is used. SHARP includes a structure of seven analysis steps which can be formally or informally performed during PRAs. The seven steps are termed definition, screening, breakdown, representation, impact assessment, quantification, and documentation

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)

International RETRAN conference 1998: Proceedings

International Nuclear Information System (INIS)

Gose, G.; McFadden, J.

1998-09-01

The RETRAN computer code, developed by EPRI through its Contractors, EI International, Inc. (EI) and Computer Simulation and Analysis, Inc. (CSA), is now widely used by the international nuclear community for various types of safety analyses. In order to exchange information concerning the current use of the code by the various organizations, EPRI and CSA sponsored the Ninth International meeting in Monterey, California, on June 7--10, 1998. The opening session featured a panel discussion on Analysis Need for Supporting Nuclear Plants in the 21st Century by representatives of the US Nuclear Industry as well as a review of RETRAN activities since the last International RETRAN Meeting. During the three-day meeting, technical papers were presented by the various participants. The papers generally dealt with the following topics: (1) RETRAN-3D development, verification, and validation; (2) RETRAN-02/RETRAN-3D analysis of PWRs; (3) RETRAN-02/RETRAN-3D analysis of BWRs; and (4) CORETRAN development and analyses activities

Improvement of nuclear reactor component materials by application of hot isostatic processing (HIP). Survey report on Phase 1

International Nuclear Information System (INIS)

Mueller, J.J.

1975-12-01

The report summarizes the results of an EPRI-sponsored state-of-the-art survey of hot isostatic processing (HIP). The purpose of the study was to identify potential nuclear plant applications of HIP with high pay-off through improvement in component quality and reliability. The survey shows that HIP will reduce cost and manufacturing time and improve quality and ease of nondestructive examination of all castings for which porosity is a problem. Nuclear valves are a prime example. Tubing, pipe, and sheet and bar present other possibilities of somewhat less immediate promise. This report includes a review of some of the EPRI motivations for undertaking this research; a brief explanation of HIP, the survey methodology exployed; the basic operations in the processes studied; a review of the historical applications of HIP to problem areas consistent with those addressed in the survey; the results of the survey and associated analyses of the problems; and the recommendations and justifications for the Phase II program

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

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

A methodology and success/failure criteria for determining emergency diesel generator reliability

International Nuclear Information System (INIS)

Wyckoff, H.L.

1986-01-01

In the U.S., comprehensive records of nationwide emergency diesel generator (EDG) reliability at nuclear power plants have not been consistently collected. Those surveys that have been undertaken have not always been complete and accurate. Moreover, they have been based On an extremely conservative methodology and success/failure criteria that are specified in U.S. Nuclear Regulatory Commission Reg. Guide 1.108. This Reg. Guide was one of the NRCs earlier efforts and does not yield the caliber of statistically defensible reliability values that are now needed. On behalf of the U.S. utilities, EPRI is taking the lead in organizing, investigating, and compiling a realistic database of EDG operating success/failure experience for the years 1983, 1984 and 1985. These data will be analyzed to provide an overall picture of EDG reliability. This paper describes the statistical methodology and start and run success/- failure criteria that EPRI is using. The survey is scheduled to be completed in March 1986. (author)

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)

Stem thrust prediction model for W-K-M double wedge parallel expanding gate valves

Energy Technology Data Exchange (ETDEWEB)

Eldiwany, B.; Alvarez, P.D. [Kalsi Engineering Inc., Sugar Land, TX (United States); Wolfe, K. [Electric Power Research Institute, Palo Alto, CA (United States)

1996-12-01

An analytical model for determining the required valve stem thrust during opening and closing strokes of W-K-M parallel expanding gate valves was developed as part of the EPRI Motor-Operated Valve Performance Prediction Methodology (EPRI MOV PPM) Program. The model was validated against measured stem thrust data obtained from in-situ testing of three W-K-M valves. Model predictions show favorable, bounding agreement with the measured data for valves with Stellite 6 hardfacing on the disks and seat rings for water flow in the preferred flow direction (gate downstream). The maximum required thrust to open and to close the valve (excluding wedging and unwedging forces) occurs at a slightly open position and not at the fully closed position. In the nonpreferred flow direction, the model shows that premature wedging can occur during {Delta}P closure strokes even when the coefficients of friction at different sliding surfaces are within the typical range. This paper summarizes the model description and comparison against test data.

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.

Investigation of CTF void fraction prediction by ENTEK BM experiment data

International Nuclear Information System (INIS)

Hoang Minh Giang; Hoang Tan Hung; Nguyen Phu Khanh

2015-01-01

Recently, CTF, a version of COBRA-TF code is reviewed to validate its simulation models by several experiments such as Castellana 4x4 rod bundle, EPRI 5x5 bundle tests, PSBT bundle tests and TPTF experiment. These above experiments provide enthalpy, mass flux (Castellana), temperature (EPRI) and void fraction (PSBT, TPTF) at exit channel only. In order to simulate PWR rod bundle flow behavior, it is necessary to review CTF with more experiment in high pressure condition and it is found that the ENTEK BM facility is suitable for this purpose. The ENTEK BM facility is used to simulate Russia RBMK and VVER rod bundle two phase flow with pressure at 3 and 7 MPa and it gives measured void fraction distribution along the channel. This study focus on two points: (a) accuracy assessment between CTF void fraction distribution predictions versus experiment void fraction distributions and (b) investigation of void fraction prediction uncertainty from propagation of input deviations caused by measured accuracy. (author)

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.

RSIC after 14 years - where do we go from here

International Nuclear Information System (INIS)

Trubey, D.K.; Maskewitz, B.F.; Roussin, R.W.

1977-01-01

During the fourteen years since the Radiation Shielding Information Center (RSIC) started operations, many changes have taken place in the nuclear industry, both government and commercial, and in shielding technology. With the present need to meet energy demands through nuclear power, and yet to minimize radiation exposure to operating personnel and the public, there is great need to increase radiation analysis capabilities among the utilities and other segments of the industry. During 1975, RSIC had an Electric Power Research Institute (EPRI) contract to integrate the shielding and technology information exchange of the nuclear power industry with that of the government and its contractors. Included in work performed by RSIC on behalf of EPRI was a survey of the radiation protection, radiation transport, and shielding information needs of the nuclear power industry. Such needs include computing technology, nuclear data, special information needs, such as fission product and 'crud' transport, and expansion more generally into radiation protection areas such as environmental radiological analysis. (orig./RW) [de

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

A methodology and success/failure criteria for determining emergency diesel generator reliability

Energy Technology Data Exchange (ETDEWEB)

Wyckoff, H. L. [Electric Power Research Institute, Palo Alto, California (United States)

1986-02-15

In the U.S., comprehensive records of nationwide emergency diesel generator (EDG) reliability at nuclear power plants have not been consistently collected. Those surveys that have been undertaken have not always been complete and accurate. Moreover, they have been based On an extremely conservative methodology and success/failure criteria that are specified in U.S. Nuclear Regulatory Commission Reg. Guide 1.108. This Reg. Guide was one of the NRCs earlier efforts and does not yield the caliber of statistically defensible reliability values that are now needed. On behalf of the U.S. utilities, EPRI is taking the lead in organizing, investigating, and compiling a realistic database of EDG operating success/failure experience for the years 1983, 1984 and 1985. These data will be analyzed to provide an overall picture of EDG reliability. This paper describes the statistical methodology and start and run success/- failure criteria that EPRI is using. The survey is scheduled to be completed in March 1986. (author)

Real time water chemistry monitoring and diagnostics

International Nuclear Information System (INIS)

Gaudreau, T.M.; Choi, S.S.

2002-01-01

EPRI has produced a real time water chemistry monitoring and diagnostic system. This system is called SMART ChemWorks and is based on the EPRI ChemWorks codes. System models, chemistry parameter relationships and diagnostic approaches from these codes are integrated with real time data collection, an intelligence engine and Internet technologies to allow for automated analysis of system chemistry. Significant data management capabilities are also included which allow the user to evaluate data and create automated reporting. Additional features have been added to the system in recent years including tracking and evaluation of primary chemistry as well as the calculation and tracking of primary to secondary leakage in PWRs. This system performs virtual sensing, identifies normal and upset conditions, and evaluates the consistency of on-line monitor and grab sample readings. The system also makes use of virtual fingerprinting to identify the cause of any chemistry upsets. This technology employs plant-specific data and models to determine the chemical state of the steam cycle. (authors)

Stem thrust prediction model for W-K-M double wedge parallel expanding gate valves

International Nuclear Information System (INIS)

Eldiwany, B.; Alvarez, P.D.; Wolfe, K.

1996-01-01

An analytical model for determining the required valve stem thrust during opening and closing strokes of W-K-M parallel expanding gate valves was developed as part of the EPRI Motor-Operated Valve Performance Prediction Methodology (EPRI MOV PPM) Program. The model was validated against measured stem thrust data obtained from in-situ testing of three W-K-M valves. Model predictions show favorable, bounding agreement with the measured data for valves with Stellite 6 hardfacing on the disks and seat rings for water flow in the preferred flow direction (gate downstream). The maximum required thrust to open and to close the valve (excluding wedging and unwedging forces) occurs at a slightly open position and not at the fully closed position. In the nonpreferred flow direction, the model shows that premature wedging can occur during ΔP closure strokes even when the coefficients of friction at different sliding surfaces are within the typical range. This paper summarizes the model description and comparison against test data

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

Study on Economic Evaluation of Nuclear Power Plant's SSC

International Nuclear Information System (INIS)

Yun, Eun-Sub; Park, Young-Sheop

2007-01-01

As the operating year of nuclear power plant increases, more improvement plans on degraded SSCs(Structure, System, and Component) are suggested. Because of safety concern, the maintenance and replacing cost of nuclear power plant's SSCs are usually high and it can be a burden to financial control. To satisfy both safety and economic problems, systematic and efficient plans are needed. For this reason, KHNP is now developing the LTAM (Long Term Asset Management) program to establish the long term improvement plans for SSCs, from safety and economic point of views. Actually LTAM program is one of the steps of INPO ER (Equipment Reliability) process. In USA, EPRI (Electric Power Research Institute) has developed the LCM (Life Cycle Management) program and it was applied to some nuclear power plants. In this program, several alternatives are candidated. Then, economic evaluation is applied to each alternative. The result of economic evaluation affects to the final alternative decision. In this study, EPRI's economic evaluation method is reviewed

Boraflex test results and evaluation

International Nuclear Information System (INIS)

Lindquist, K.; Kline, D.E.; Haley, T.C.

1993-02-01

New data developed, collected, and evaluated to further assess the in-pool performance of the neutron absorber material, Boraflex. The data are from new EPRI test programs, utility surveillance programs, and blackness testing at a number of plants. This new data provides a basis for quantifying the gap phenomenon in full length panels of Boraflex in spent fuel racks; the maximum anticipated gap size, frequency of gap occurrence, and axial distribution of gaps. Methods have been developed to assess the reactivity effects of gaps and Boraflex shrinkage. The analyses presented demonstrates that the reactivity effect of gaps is very small, not much larger than the statistical variations inherent in the calculational method. The data and analyses presented serve to close the issue of gap formation and shrinkage in panels of Boraflex and the effect of such gaps and shrinkage on the reactivity of the fuel/rack configuration. Ongoing EPRI programs to assess the long term performance of Boraflex in spent fuel storage racks are described

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

A review on progress of man-machine interface system designs for Japanese PWRs

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu; Yamamoto, Yoshihiro; Magari, Takayuki.

1994-01-01

Historical development of Instrumentation and Control (I and C) system designing for the PWR plants in Kansai Electric Co. Ltd is firstly reviewed with respect to the conventional PWRs in the past, brand-new PWRs (Ohi 3/4 units) and advanced PWRs (APWR) in Japan. The major features of the APWR I and C system design are extensive application of digital computer control technology and advanced man-machine interface in order to enhance safety and reliability of total I and C system and to improve human factors in nuclear power plant operation. Comparative study of the APWR's I and C system design with the EPRI's User Requirement Definitions (URD) resulted in that the current Japanese APWR I and C system design meets generally with the EPRI URD conditions except for those items mainly set by the present national regulatory guidelines. The remaining problems in the current I and C system design are discussed which include the issues on future direction of man-machine interface development. (author)

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.

Reactor safety research - visible demonstrations and credible computations

International Nuclear Information System (INIS)

Loewenstein, W.B.; Divakaruni, S.M.

1985-01-01

EPRI has been conducting nuclear safety research for a number of years with the primary goal of assuring the safety and reliability of the nuclear plants. The visibility is emphasized by sponsoring or participating in large scale test demonstrations to credibly support the complex computations that are the basis for quantification of safety margins. Recognizing the success of the airline industry in receiving favorable public perception, the authors compare the design and operation practices of the airline industry with those of the nuclear industry practices to identify the elements contributing to public concerns and unfavorable perceptions. In this paper, authors emphasize the importance of proper communications of research results to the public in a manner that non-specialists understand. Further, EPRI supported research and results in the areas of source term, seismic and structural engineering research, analysis using probabilistic risk assessment (PRA), quantification of safety margins, digital technology development and implementation, and plant transient and performance evaluations are discussed in the paper. (orig./HP)

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)

Zinc injection helps reduce radiation field buildup in BWRs

International Nuclear Information System (INIS)

Wood, C.

1991-01-01

The injection of zinc into the reactor water of BWRs (Boiling Water Reactors) was a technique developed by General Electric (GE) and the Electric Power Research Institute (EPRI) to control the buildup of radiation fields from cobalt-60 on out-of-core piping. The presence of 5-10ppb zinc in the reactor water reduces the growth of oxide films on stainless steel surfaces, thereby reducing the number of sites available for the incorporation of cobalt; zinc also competes with cobalt for the sites. In September 1990, EPRI organized a workshop at the request of several US utilities to provide a forum to discuss experiences with zinc injection. The meeting focused on six main issues: the effect of zinc on radiation fields in normal water chemistry; the radiation buildup in hydrogen water chemistry, with and without zinc; the effects of zinc-65; the corrosion of fuel cladding and structural materials; the performance of zinc injection and monitoring equipment; and planning for zinc injection. (author)

Steam purity in PWRs

International Nuclear Information System (INIS)

Hopkinson, J.; Passell, T.

1982-01-01

Reports that 2 EPRI studies of PWRs prove that impure steam triggers decay of turbine metals. Reveals that EPRI is attempting to improve steam monitoring and analysis, which are key steps on the way to deciding the most cost-effective degree of steam purity, and to upgrade demineralizing systems, which can then reliably maintain that degree of purity. Points out that 90% of all cracks in turbine disks have occurred at the dry-to-wet transition zone, dubbed the Wilson line. Explains that because even very clean water contains traces of chemical impurities with concentrations in the parts-per-billion range, Crystal River-3's secondary loop was designed with even more purification capability; a deaerator to remove oxygen and prevent oxidation of system metals, and full-flow resin beds to demineralize 100% of the secondary-loop water from the condenser. Concludes that focusing attention on steam and water chemistry can ward off cracking and sludge problems caused by corrosion

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)

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...

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

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.

"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.

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

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

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

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.)

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

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

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.

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

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.)

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

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

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)

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)

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

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.

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

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

A basis for standardized seismic design (SSD) for nuclear power plants/critical facilities

International Nuclear Information System (INIS)

O'Hara, T.F.; Jacobson, J.P.; Bellini, F.X.

1991-01-01

US Nuclear Power Plants (NPP's) are designed, engineered and constructed to stringent standards. Their seismic adequacy is assured by compliance with regulatory standards and demonstrated by both probabilistic risk assessments (PRAs) and seismic margin studies. However, present seismic siting criteria requires improvement. Proposed changes to siting criteria discussed here will provide a predictable licensing process and a stable regulatory environment. Two recent state-of-the-art studies evaluate the seismic design for all eastern US (EUS) NPP'S: a Lawrence Livermore National Labs study (LLNL, 1989) funded by the NRC and similar research by the Electric Power Research Institute (EPRI, 1989) supported by the utilities. Both confirm that Appendix A 10CFR Part 100 has not provided consistent seismic design levels for all sites. Standardized Seismic Design (SSD) uses a probabilistic framework to accommodate alternative deterministic interpretations. It uses seismic hazard input from EPRI or LLNL to produce consistent bases for future seismic design. SSD combines deterministic and probabilistic insights to provide a comprehensive approach for determining a future site's acceptable seismic design basis

High-resolution mapping of 1D and 2D dose distributions using X-band electron paramagnetic resonance imaging

International Nuclear Information System (INIS)

Kolbun, N.; Lund, E.; Adolfsson, E.; Gustafsson, H.

2014-01-01

Electron paramagnetic resonance imaging (EPRI) was performed to visualise 2D dose distributions of homogeneously irradiated potassium dithionate tablets and to demonstrate determination of 1D dose profiles along the height of the tablets. Mathematical correction was applied for each relative dose profile in order to take into account the inhomogeneous response of the resonator using X-band EPRI. The dose profiles are presented with the spatial resolution of 0.6 mm from the acquired 2D images; this value is limited by pixel size, and 1D dose profiles from 1D imaging with spatial resolution of 0.3 mm limited by the intrinsic line-width of potassium dithionate. In this paper, dose profiles from 2D reconstructed electron paramagnetic resonance (EPR) images using the Xepr software package by Bruker are focussed. The conclusion is that using potassium dithionate, the resolution 0.3 mm is sufficient for mapping steep dose gradients if the dosemeters are covering only ±2 mm around the centre of the resonator. (authors)

Additives for pH control in PWR secondary water

International Nuclear Information System (INIS)

Cobble, J.W.; Turner, P.J.

1985-08-01

The purpose of this project is the development of methods for identifying the most promising materials for use as pH control agents in steam generator and auxiliary hot water systems. The methods developed in the first project year to select new pH control agents have been explored in more detail in an effort to assess and improve their reliability. In addition, some new classes of compounds which were not treatable before have been examined on the basis of new experimental results. Predictions of pH and volatility to 300 0 C have now been made for a total of 79 organic bases. Some of the newer classes of compounds studied present properties which may make them of interest either as secondary additives or as principal agents in the event of change in the approach to water treatment. While there have been no substantial changes in number of compounds which meet all EPRI criteria, there are other species which may meet the EPRI criteria after further research. 19 refs., 31 tabs

Improved Accuracy for Two-Phase Downflow Scenarios

Energy Technology Data Exchange (ETDEWEB)

Cliff B. Davis

2012-10-01

Problems have been reported for very high downflows in small and intermediate pipes in the bubbly and slug flow regimes. When the flow rate is near critical, the calculated mass flow rate depends strongly on the flow orientation for small and intermediate pipes, whereas the flow rate is nearly independent of flow direction for large pipes. At very high flow rates, the flow is expected to be nearly homogenous and hence to be nearly independent of flow direction. The flow rates calculated by RELAP5-3D agree with this expectation except for downflow in small and intermediate pipes, where the calculated flows in the downward direction are about 20% lower than the flows in the upward and horizontal directions. The problem was traced to an extrapolation of the EPRI drift flux correlation beyond the range of its database. The problem was corrected by creating a very high downflow regime. The EPRI correlation is replaced by the Zuber-Findlay churn turbulent and Kataoka-Ishii drift flux correlations in the very high downflow regime for small and intermediate pipes.

Assessment of market potential of compressed air energy storage systems

Science.gov (United States)

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

1983-12-01

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. Previously announced in STAR as N83-25121

EPR imaging and HPLC characterization of the pigment-based organic free radical in black soybean seeds.

Science.gov (United States)

Nakagawa, Kouichi; Maeda, Hayato

2017-02-01

We investigated the location and distribution of paramagnetic species in dry black, brown, and yellow (normal) soybean seeds using electron paramagnetic resonance (EPR), X-band (9 GHz) EPR imaging (EPRI), and HPLC. EPR primarily detected two paramagnetic species in black soybean. These two different radical species were assigned as stable organic radical and Mn 2+  species based on the g values and hyperfine structures. The signal from the stable radical was noted at g ≈ 2.00 and was relatively strong and stable. Subsequent noninvasive two-dimensional (2D) EPRI of the radical present in black soybean revealed that the stable radical was primarily located in the pigmented region of the soybean coat, with very few radicals observed in the soybean cotyledon (interior). Pigments extracted from black soybean were analyzed using HPLC. The major compound was found to be cyanidin-3-glucoside. Multi-EPR and HPLC results indicate that the stable radical was only found within the pigmented region of the soybean coat, and it could be cyanidin-3-glucoside or an oxidative decomposition product.

Development of a Base Model for the New Fire PSA Training

International Nuclear Information System (INIS)

Kim, Kilyoo; Kang, Daeil; Kim, Wee Kyong; Do, Kyu Sik

2013-01-01

US NRC/EPRI issued a new fire PSA method represented by NUREG/CR 6850, and have been training many operators and inspectors to widely spread the new method. However, there is a limitation in time and efficiency for many foreigners, who generally have communication problem, to participate in the EPRI/NRC training to learn the new method. Since it is about time to introduce the new fire PSA method as a regulatory requirement for the fire protection in Korea, a simple and easy-understandable base model for the fire PSA training is required, and KAERI-KINS is jointly preparing the base model for the new fire PSA training. This paper describes how the base model is developed. Using an imaginary simple NPP, a base model of fire PSA following the new fire PSA method was developed in two ways from the internal PSA model. Since we have the base model and know the process of making the fire PSA model, the training for the new fire PSA method can be in detail performed in Korea

Development of Wall Thinning Distinction Method using the Multi-inspecting UT Data of Carbon Steel Piping

Energy Technology Data Exchange (ETDEWEB)

Hwang, Kyeong Mo; Yun, Hun; Lee, Chan Kyoo [KEPCO E and C, Yongin (Korea, Republic of)

2012-05-15

To manage the wall thinning of carbon steel piping in nuclear power plants, the utility of Korea has performed thickness inspection for some quantity of pipe components during refueling outages and determined whether repair or replacement after evaluating UT (Ultrasonic Test) data. When the existing UT data evaluation methods, such as Band, Blanket, PTP (Point to Point) Methods, are applied to a certain pipe component, unnecessary re-inspecting situations may be generated even though the component does not thinned. In those cases, economical loss caused by repeated inspection and problems of maintaining the pipe integrity followed by decreasing of newly inspected components may be generated. EPRI (Electric Power Research Institute) in USA has suggested several statistical methods, TPM (Total Point Method), LSS (Least Square Slope) Method, etc. to distinguish whether multiple inspecting components have thinned or not. This paper presents the analysis results for multiple inspecting components over three times based on both NAM (Near Area of Minimum) Method developed by KEPCO-E and C and the other methods suggested by EPRI.

Use of NDE and FM for the assessment of remaining life of steam turbines

Energy Technology Data Exchange (ETDEWEB)

Alley, T [Duke Power Co., Charlotte, NC (United States); Stone, R [Electric Power Research Inst., Charlotte, NC (United States). Nondestructive Evaluation Center

1988-12-31

Catastrophic failures of rotating turbine components, such as the Gallatin rotor burst in 1974 and the shrunk-on disk rupture at Hinkley Point in 1969, alerted the utility industry to the failure potential of these components. Such failures can cause severe financial loss; endanger personnel; and, in nuclear plants, damage safety related equipment. To adequately predict the remaining life of a turbine rotor requires accurate information about component flaws, material properties, future operating loads, relevant failure mechanisms, and an approach to combine this information to make an assessment of remaining life. EPRI has supported the development of improved ultrasonic test equipment for use from the rotor bore (bore-sonic examination) and a fracture mechanics based life assessment code called SAFER (Stress and Fracture Evaluation of Rotors). The EPRI NDE Center has supported the transfer of this technology to industry. This presentation deals with the NDE Center`s transfer of the NDE and life assessment technology to industry and discusses a particular application by Duke Power Company at their Allen Plant, Unit 1 to extend the operating life of an IP/LP turbine. (author).

Use of NDE and FM for the assessment of remaining life of steam turbines

International Nuclear Information System (INIS)

Alley, T.; Stone, R.

1988-01-01

Catastrophic failures of rotating turbine components, such as the Gallatin rotor burst in 1974 and the shrunk-on disk rupture at Hinkley Point in 1969, alerted the utility industry to the failure potential of these components. Such failures can cause severe financial loss; endanger personnel; and, in nuclear plants, damage safety related equipment. To adequately predict the remaining life of a turbine rotor requires accurate information about component flaws, material properties, future operating loads, relevant failure mechanisms, and an approach to combine this information to make an assessment of remaining life. EPRI has supported the development of improved ultrasonic test equipment for use from the rotor bore (bore-sonic examination) and a fracture mechanics based life assessment code called SAFER (Stress and Fracture Evaluation of Rotors). The EPRI NDE Center has supported the transfer of this technology to industry. This presentation deals with the NDE Center's transfer of the NDE and life assessment technology to industry and discusses a particular application by Duke Power Company at their Allen Plant, Unit 1 to extend the operating life of an IP/LP turbine. (author)

Nuclear plant needs for new process instrumentation

International Nuclear Information System (INIS)

Weiss, J.; Belew, M.

1991-01-01

Electric Power Research Institute (EPRI) is initiating projects to investigate new sensor designs for pressure and hydrogen measurements. The intent is to develop new sensors that are highly accurate with inherently low-maintenance requirements. Criteria have been developed, with utility review and input, for evaluating pressure sensor technology. The first phase will evaluate all pressure-sensing concepts, including new techniques such as fiber optics, digital silicon, reductance, acoustics, and others (exploratory research). Concepts that appear most attractive for meeting the utility criteria will be extended. The second phase would be conceptual development, laboratory testing, market surveys, manufacturing assessments, plant implementation assessments, and a cost/benefits assessment. Assuming positive results from phase 2, phase 3 would be prototype sensor development and host plant testing. Phase 4 (funded outside EPRI) would be qualification testing. Hydrogen sensor assessment studies are under way to determine the need for improved hydrogen sensor designs. If the results of the assessment indicate a need, a project to develop improved hydrogen sensors utilizing a similar multiphase approach will also be initiated

AP1000 construction schedule

International Nuclear Information System (INIS)

Winters, J.W.

2001-01-01

Westinghouse performed this study as part of EPRI interest in advancing the use of computer aided processes to reduce the cost of nuclear power plants. EPRI believed that if one could relate appropriate portions of an advanced light water reactor plant model to activities in its construction sequence, and this relationship could be portrayed visually, then optimization of the construction sequence could be developed as never before. By seeing a 3-D representation of the plant at any point in its construction sequence, more informed decisions can be made on the feasibility or attractiveness of follow on or parallel steps in the sequence. The 3-D representation of construction as a function of time (4-D) could also increase the confidence of potential investors concerning the viability of the schedule and the plant ultimate cost. This study performed by Westinghouse confirmed that it is useful to be able to visualize a plant construction in 3-D as a function of time in order to optimize the sequence of construction activities. (author)

A research project to encourage system-compatible design of end-use appliances

International Nuclear Information System (INIS)

Dorr, D.; Key, T.; Sitzlar, G.

1995-01-01

Cooperative system compatibility research sponsored by the Canadian Electrical Association (CEA) and the Electric Power Research Institute (EPRI) for improving appliance performance deficiencies was described. Power producer and end-user compatibility concerns was addressed through the development of a System Compatibility Research Project. A list of project tasks was provided. The CEA and EPRI initiated a project to establish flicker response of various lighting systems, which included physical tests. Results of this project were presented and discussed. The incentives for developing switch mode power supplies with enhanced immunity to voltage fluctuations and short interruptions was discussed. It was concluded that power quality studies currently underway will provide designers with a profile of the expected utility environment for their products. System compatibility research will identify areas that should be addressed by standards bodies so that designers can apply applicable criteria objectives early in the appliance design process. These efforts were expected to encourage appropriate manufacturer criteria for compatibility by convincing buyers and sellers that there is a real pay back for this investment. 13 refs., 6 figs., 4 tabs

Improved specifications for continuous emission monitoring

International Nuclear Information System (INIS)

Dene, C.E.; Eggleston, T.E.; Gray, W.C. Jr.; Bisha, R.M.

1988-01-01

Continuous emission monitoring (CEM) in the electric utility industry historically has been plagued by poor performance and inconsistent system reliability. These problems have, in part, been caused by the complexity and diversity of the various systems available, and the dissimilarity of continuous emission monitors CEMs relative to conventional power plant instrumentation. Recognizing the problems faced by the utility industry in implementing CEM programs, the Electric Power Research Institute (EPRI) initiated a multi-phase project to define the current state of technology for CEMs and to provide a comprehensive guide for the purchase and installation of a CEM system. The second phase of this project was the application of these guidelines to the actual purchase, installation, and operation of a CEM system for an electric utility generating station. Through this application of the guidelines it has been possible to determine further research needs and areas of the manual which require clarification or enhancement. This paper describes the development of the guidelines and modifications to the guidelines, and discusses EPRI's plans for future activities in the area of continuous emission monitoring

Failure prediction of low-carbon steel pressure vessel and cylindrical models

International Nuclear Information System (INIS)

Zhang, K.D.; Wang, W.

1987-01-01

The failure loads predicted by failure assessment methods (namely the net-section stress criterion; the EPRI engineering approach for elastic-plastic analysis; the CEGB failure assessment route; the modified R6 curve by Milne for strain hardening; and the failure assessment curve based on J estimation by Ainsworth) have been compared with burst test results on externally, axially sharp notched pressure vessel and open-ended cylinder models made from typical low-carbon steel St45 seamless tube which has a transverse true stress-strain curve of straight-line and parabola type and a high value of ultimate strength to yield. It was concluded from the comparison that whilst the net-section stress criterion and the CEGB route did not give conservative predictions, Milne's modified curve did give a conservative and good prediction; Ainsworth's curve gave a fairly conservative prediction; and EPRI solutions also could conditionally give a good prediction but the conditions are still somewhat uncertain. It is suggested that Milne's modified R6 curve is used in failure assessment of low-carbon steel pressure vessels. (author)

Risk insights from seismic margin reviews

International Nuclear Information System (INIS)

Budnitz, R.J.

1990-01-01

This paper discusses the information that has been derived from the three seismic-margin reviews conducted so far, and the information that is potentially available from using the seismic-margin method more generally. There are two different methodologies for conducting seismic margin reviews of nuclear power plants, one developed under NRC sponsorship and one developed under sponsorship of the Electric Power Research Institute. Both methodologies will be covered in this paper. The paper begins with a summary of the steps necessary to complete a margin review, and will then outline the key technical difficulties that need to be addressed. After this introduction, the paper covers the safety and operational insights derived from the three seismic-margin reviews already completed: the NRC-sponsored review at Maine Yankee; the EPRI-sponsored review at Catawba; and the joint EPRI/NRC/utility effort at Hatch. The emphasis is on engineering insights, with attention to the aspects of the reviews that are easiest to perform and that provide the most readily available insights

Vibration and wear prediction for steam generator tubes: Final report

International Nuclear Information System (INIS)

Rao, M.S.M.; Gupta, G.D.; Eisinger, F.L.

1988-06-01

As part of the overall EPRI program to develop a mechanistic model for tube fretting and wear prediction, Foster Wheeler Development Corporation undertook the responsibility of developing analytical models to predict structural response and wear in a multispan tube. The project objective was to develop the analytical capability to simulate the time-dependent motion of a multispan steam generator tube in the presence of the clearance gaps at each tube baffle or support. The models developed were to simulate nonlinear tube-to-tube support interaction by determining the impact force, the sliding distance, and the resultant tube wear. Other objectives of the project included: validate the models by comparing the analytical results with the EPRI tests done at Combustion Engineering (C-E) on single multispan tubes; test the models for simulating the U-bend region of the steam generator tube, including the antivibration bars; and develop simplified methods to treat the nonlinear dynamic problem of a multispan tube so that computing costs could be minimized. 15 refs., 53 figs., 27 tabs

User-centered design

International Nuclear Information System (INIS)

Baik, Joo Hyun; Kim, Hyeong Heon

2008-01-01

The simplification philosophy, as an example, that both of EPRI-URD and EUR emphasize is treated mostly for the cost reduction of the nuclear power plants, but not for the simplification of the structure of user's tasks, which is one of the principles of user-centered design. A user-centered design is a philosophy based on the needs and interests of the user, with an emphasis on making products usable and understandable. However, the nuclear power plants offered these days by which the predominant reactor vendors are hardly user-centered but still designer-centered or technology-centered in viewpoint of fulfilling user requirements. The main goal of user-centered design is that user requirements are elicited correctly, reflected properly into the system requirements, and verified thoroughly by the tests. Starting from the user requirements throughout to the final test, each requirement should be traceable. That's why requirement traceability is a key to the user-centered design, and main theme of a requirement management program, which is suggested to be added into EPRI-URD and EUR in the section of Design Process. (author)

Demonstrate use of capillary electrophoresis low level transient of anions

International Nuclear Information System (INIS)

Moum, Kari-Lye; Solheim, Torill; McElrath, Joel; Frattini, Paul

2012-09-01

Capillary Electrophoresis (CE) is a well-known analytical method capable of rapid detection of very low concentration of cations and anionic species such as chloride, sulfate and nitrate. These anions are of crucial importance in reducing the potential of stainless steel components to undergo stress corrosion cracking. Currently, Nuclear Power Plants (NPPs) use Ion Chromatography (IC) as the analytical technique to achieve the required detection levels of ionic species. At the Halden Reactor Project (HRP) IC was replaced by CE in 1996, and since then HRP has gained nearly 20 years of operational experience. During the last 15 years, EPRI has done research on the CE technique and has achieved extensive experience in this area. EPRI has demonstrated detection levels at ppt and sub-ppb levels. This paper presents the ability of the CE technique to follow low level transients of anions in Boiling Water Reactor (BWR) coolant. A transient caused by approx. 10 ppb chloride and sulfate was simulated in an experimental circuit simulating BWR conditions. A series of grab samples were taken and analysed using HRPs CE (Agilent G1600). (authors)

Sodium bicarbonate injection: a small-plant SO sub 2 /NO sub x option

Energy Technology Data Exchange (ETDEWEB)

Darmstaedter, E. (NaTec Resources Inc. (USA). Environmental Systems Division)

1990-12-01

The sodium bicarbonate injection process provides a cost effective alternative to flue gas desulfurization for smaller power plants. EPRI and NaTec Resources have been conducting demonstrations on coal-fired utility boilers. 90% SO{sub 2} reduction was achieved in EPRI's High-Sulfur Test Centre 4 MW pilot HYPAS installation near Barker, NY. During 1990 Public Service Company of Colorado and NaTec completed a two-phase commercial demonstration for continuous SO{sub 2}/NO{sub x} control on Cherokee Unit 1 to determine levels of urea and injection locations for urea and sodium bicarbonate to minimise NO{sub 2} and NH{sub 3} emissions while maintaining a high level of SO{sub 2} reduction. Methods for sodium sulphate by-product recovery/sale are described - these are higher value than those from the limestone process. Costs for the whole process, driven by sorbent costs, work out typically for a dry sorbent injection/HYPAS system at $610/ton SO{sub 2} removed. 11 refs., 5 figs., 1 tab.

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.

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.

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

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

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)

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

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

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

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.

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

Long Term Operation R and D to Investigate the Technical Basis for Life Extension and License Renewal Decisions

International Nuclear Information System (INIS)

Gaertner, John

2012-01-01

Establishing an improved technical basis for long term operation of existing plants is a nuclear industry priority. The Electric Power Research Institute (EPRI) has responded with a comprehensive Long Term Operation (LTO) Program addressing this need for existing nuclear power plants world-wide. The program supports both the business decisions necessary to achieve high performance operation and the licensing requirements for operation beyond 60 years. The program selects its R and D priorities in a structured and objective way with much industry input to provide useful results for decisions in the 2014 to 2019 time frame. The program is highly collaborative with U.S. Department of Energy (DOE) and with EPRI-member utilities. The R and D portfolio includes materials aging (metals, concrete, and cables), modernization of information and control technology, enhanced safety analysis, advanced fuel design, demonstration plant activities, life cycle management, and identification of aging management program need for subsequent license renewal. The program has focussed stakeholders world-wide on the technical issues of long term operation, and it is on-track to provide practical results for life extension and license renewal decisions. (author)

Materials choices for the advanced LWR steam generators

International Nuclear Information System (INIS)

Paine, J.P.N.; Shoemaker, C.E.; McIlree, A.R.

1987-01-01

Current light water reactor (LWR) steam generators have been affected by a variety of corrosion and mechanical damage degradation mechanisms. Included are wear caused by tube vibration, intergranular corrosion, pitting, and thinning or wastage of the steam generator tubing and accelerated corrosion of carbon steel supports (denting). The Electric Power Research Institute (EPRI) and the Steam Generator Owners Groups (I, II) have sponsored laboratory and field studies to provide ameliorative actions for the majority of the damage forms experienced to date. Some of the current corrosion mechanisms are aggravated or caused by unique materials choices or materials interactions. New materials have been proposed and at least partially qualified for use in replacement model steam generators, including an advanced LWR design. In so far as possible, the materials choices for the advanced LWR steam generator avoid the corrosion pitfalls seemingly inherent in the current designs. The EPRI Steam Generator Project staff has recommended materials and design choices for a new steam generator. Based on these recommendations we believe that the advanced LWR steam generators will be much less affected by corrosion and mechanical damage mechanisms than are now experienced

A large-scale soil-structure interaction experiment: Part I design and construction

International Nuclear Information System (INIS)

Tang, H.T.; Tang, Y.K.; Wall, I.B.; Lin, E.

1987-01-01

In the simulated earthquake experiments (SIMQUAKE) sponsored by EPRI, the detonation of vertical arrays of explosives propagated wave motions through the ground to the model structures. Although such a simulation can provide information about dynamic soil-structure interaction (SSI) characteristics in a strong motion environment, it lacks seismic wave scattering characteristics for studying seismic input to the soil-structure system and the effect of different kinds of wave composition to the soil-structure response. To supplement the inadequacy of the simulated earthquake SSI experiment, the Electric Power Research Institute (EPRI) and the Taiwan Power Company (Taipower) jointly sponsored a large scale SSI experiment in the field. The objectives of the experiment are: (1) to obtain actual strong motion earthquakes induced database in a soft-soil environment which will substantiate predictive and design SSI models;and (2) to assess nuclear power plant reactor containment internal components dynamic response and margins relating to actual earthquake-induced excitation. These objectives are accomplished by recording and analyzing data from two instrumented, scaled down, (1/4- and 1/12-scale) reinforced concrete containments sited in a high seismic region in Taiwan where a strong-motion seismic array network is located

Differential infrared thermography applied to power generation facilities -- A case history

International Nuclear Information System (INIS)

Kaplan, H.; Zayicek, P.

1995-01-01

The controlled and systematic application of differential thermal imaging (DIT) can be a highly promising tool for condition monitoring and predictive maintenance of electronic, electrical and mechanical elements and can dramatically improve the reliability, maintainability and operational life of certain types of elements in the power generation and distribution community. The expanded applicability of this technique has been brought about by improvements in commercial IR thermal imaging equipment and advances in the related data and image processing capacities. This paper summarizes the advantages and limitations of DIT and describes several variations of the technique. It goes on to provide an update of progress on a program initiated by the Electric Power Research Institute (EPRI) Nondestructive Evaluation (NDE) Center to apply DIT to operating elements within a power generating station environment (Wolf Creek Nuclear Facility). It traces the selection of candidate elements at some of EPRI's member facilities, the implementation of exploratory measurements on selected candidates using available on-site infrared imaging equipment and the analysis of significant findings on one specific critical element. Finally, a projection for the potential future applicability of the DIT technique is provided

Hot dry rock geothermal energy for U.S. electric utilities. Draft final report

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

In order to bring an electric utility component into the study of hot dry rock geothermal energy called for in the Energy Policy Act of 1992 (EPAct), EPRI organized a one-day conference in Philadelphia on January 14,1993. The conference was planned as the first day of a two-day sequence, by coordinating with the U.S. Geological Survey (USGS) and the U.S. Department of Energy (DOE). These two federal agencies were charged under EPAct with the development of a report on the potential for hot dry rock geothermal energy production in the US, especially the eastern US. The USGS was given lead responsibility for a report to be done in association with DOE. The EPRI conference emphasized first the status of technology development and testing in the U.S. and abroad, i.e., in western Europe, Russia and Japan. The conference went on to address the extent of knowledge regarding the resource base in the US, especially in the eastern half of the country, and then to address some practical business aspects of organizing projects or industries that could bring these resources into use, either for thermal applications or for electric power generation.

A nuclear power plant status monitor

International Nuclear Information System (INIS)

Chu, B.B.; Conradi, L.L.; Weinzimmer, F.

1986-01-01

Power plant operation requires decisions that can affect both the availability of the plant and its compliance with operating guidelines. Taking equipment out of service may affect the ability of the plant to produce power at a certain power level and may also affect the status of the plant with regard to technical specifications. Keeping the plant at a high as possible production level and remaining in compliance with the limiting conditions for operation (LCOs) can dictate a variety of plant operation and maintenance actions and responses. Required actions and responses depend on the actual operational status of a nuclear plant and its attendant systems, trains, and components which is a dynamic situation. This paper discusses an Electric Power Research Institute (EPRI) Research Project, RP 2508, the objective of which is to combine the key features of plant information management systems with systems reliability analysis techniques in order to assist nuclear power plant personnel to perform their functions more efficiently and effectively. An overview of the EPRI Research Project is provided along with a detailed discussion of the design and operation of the PSM portion of the project

Probabilistic analysis of turbine missile damage to nuclear power plant structures

International Nuclear Information System (INIS)

Twisdale, L.A.; Dunn, W.L.; Frank, R.A.

1983-01-01

This paper summarizes the results of the EPRI project that focused on the development of the overall probabilistic methodology to assess the risks of turbine missile induced damage to nuclear power plant structures and components. The project was structured to use the results of other EPRI projects that provided information on turbine failure and missile generation frequencies, models to predict the characteristics and exit conditions of the missiles, and experimental data for use in updating empirical impact formulas for reinforced concrete barriers. The research effort included: (1) adaptation and implementation of the missile generation probability and turbine casing impact models developed in Ref. [2]; (2) development of a methodology for the prediction of the motion of the postulated missile fragments that perforate the turbine casing; (3) development of a model using the experimental impact data to predict the effects of fragment impact on nuclear power plant barriers and components; (4) construction of a probabilistic damage assessment methodology using Monte Carlo simulation methodology; and (5) implementation of the methodology into an independent computer program (TURMIS), demonstration of its application to an example case study problem, and assessment of prediction sensitivity. (orig./RW)

Engineering and Economic Analysis of an Advanced Ultra-Supercritical Pulverized Coal Power Plant with and without Post-Combustion Carbon Capture Task 7. Design and Economic Studies

Energy Technology Data Exchange (ETDEWEB)

Booras, George [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Powers, J. [General Electric, Schenectady, NY (United States); Riley, C. [General Electric, Schenectady, NY (United States); Hendrix, H. [Hendrix Engineering Solutions, Inc., Calera, AL (United States)

2015-09-01

This report evaluates the economics and performance of two A-USC PC power plants; Case 1 is a conventionally configured A-USC PC power plant with superior emission controls, but without CO₂ removal; and Case 2 adds a post-combustion carbon capture (PCC) system to the plant from Case 1, using the design and heat integration strategies from EPRI’s 2015 report, “Best Integrated Coal Plant.” The capture design basis for this case is “partial,” to meet EPA’s proposed New Source Performance Standard, which was initially proposed as 500 kg-CO₂/MWh (gross) or 1100 lb-CO₂/MWh (gross), but modified in August 2015 to 635 kg-CO₂/MWh (gross) or 1400 lb-CO₂/MWh (gross). This report draws upon the collective experience of consortium members, with EPRI and General Electric leading the study. General Electric provided the steam cycle analysis as well as v the steam turbine design and cost estimating. EPRI performed integrated plant performance analysis using EPRI’s PC Cost model.

Electron paramagnetic resonance image reconstruction with total variation and curvelets regularization

Science.gov (United States)

Durand, Sylvain; Frapart, Yves-Michel; Kerebel, Maud

2017-11-01

Spatial electron paramagnetic resonance imaging (EPRI) is a recent method to localize and characterize free radicals in vivo or in vitro, leading to applications in material and biomedical sciences. To improve the quality of the reconstruction obtained by EPRI, a variational method is proposed to inverse the image formation model. It is based on a least-square data-fidelity term and the total variation and Besov seminorm for the regularization term. To fully comprehend the Besov seminorm, an implementation using the curvelet transform and the L 1 norm enforcing the sparsity is proposed. It allows our model to reconstruct both image where acquisition information are missing and image with details in textured areas, thus opening possibilities to reduce acquisition times. To implement the minimization problem using the algorithm developed by Chambolle and Pock, a thorough analysis of the direct model is undertaken and the latter is inverted while avoiding the use of filtered backprojection (FBP) and of non-uniform Fourier transform. Numerical experiments are carried out on simulated data, where the proposed model outperforms both visually and quantitatively the classical model using deconvolution and FBP. Improved reconstructions on real data, acquired on an irradiated distal phalanx, were successfully obtained.

Application of risk-based methodologies to prioritize safety resources

International Nuclear Information System (INIS)

Rahn, F.J.; Sursock, J.P.; Hosler, J.

1993-01-01

The Electric Power Research Institute (EPRI) started a program entitled risk-based prioritization in 1992. The purpose of this program is to provide generic technical support to the nuclear power industry relative to its recent initiatives in the area of operations and maintenance (O ampersand M) cost control using state-of-the-art risk methods. The approach uses probabilistic risk assessment (PRA), or similar techniques, to allocate resources commensurate with the risk posed by nuclear plant operations. Specifically, those items or events that have high risk significance would receive the most attention, while those with little risk content would command fewer resources. As quantified in a companion paper,close-quote the potential O ampersand M cost reduction inherent in this approach is very large. Furthermore, risk-based methods should also lead to safety improvements. This paper outlines the way that the EPRI technical work complements the technical, policy, and regulatory initiatives taken by others in the industry and provides an example of the approach as used to prioritize motor-operated valve (MOV) testing in response to US Nuclear Regulatory Commission (NRC) Generic Letter 89-10

Earthquakes and Tectonics Expert Judgment Elicitation Project

International Nuclear Information System (INIS)

Coppersmith, K.J.; Perman, R.C.; Youngs, R.R.

1993-02-01

This report summarizes the results of the Earthquakes and Tectonics Expert Judgement Excitation Project sponsored by the Electric Power Research Institute (EPRI). The objectives of this study were two-fold: (1) to demonstrate methods for the excitation of expert judgement, and (2) to quantify the uncertainties associated with earthquake and tectonics issues for use in the EPRI-HLW performance assessment. Specifically, the technical issue considered is the probability of differential fault displacement through the proposed repository at Yucca Mountain, Nevada. For this study, a strategy for quantifying uncertainties was developed that relies on the judgements of multiple experts. A panel of seven geologists and seismologists was assembled to quantify the uncertainties associated with earthquake and tectonics issues for the performance assessment model. A series of technical workshops focusing on these issues were conducted. Finally, each expert was individually interviewed in order to elicit his judgement regarding the technical issues and to provide the technical basis for his assessment. This report summarizes the methodologies used to elicit the judgements of the earthquakes and tectonics experts (termed ''specialists''), and summarizes the technical assessments made by the expert panel

RELAP5/MOD3 assessment for calculation of safety and relief valve discharge piping hydrodynamic loads

International Nuclear Information System (INIS)

Stubbe, E.J.; VanHoenacker, L.; Otero, R.

1994-02-01

This report presents an assessment study for the use of the code RELAP 5/MOD3/5M5 in the calculation of transient hydrodynamic loads on safety and relief discharge pipes. Its predecessor, RELAP 5/MOD1, was found adequate for this kind of calculations by EPRI. The hydrodynamic loads are very important for the discharge piping design because of the fast opening of the valves and the presence of liquid in the upstream loop seals. The code results are compared to experimental load measurements performed at the Combustion Engineering Laboratory in Windsor (US). Those measurements were part of the PWR Valve Test Program undertaken by EPRI after the TMI-2 accident. This particular kind of transients challenges the applicability of the following code models: two-phase choked discharge; interphase drag in conditions with large density gradients; heat transfer to metallic structures in fast changing conditions; two-phase flow at abrupt expansions. The code applicability to this kind of transients is investigated. Some sensitivity analyses to different code and model options are performed. Finally, the suitability of the code and some modeling guidelines are discussed

Innovative Clean Coal Technology (ICCT): 500-MW demonstration of advanced wall-fired cmbustion techniques for the reduction of nitrogen oxide (NO{sub x}) emissions from coal-fired boilers. Field chemical emissions monitoring, Overfire air and overfire air/low NO{sub x} burner operation: Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-12-31

This report summarizes data gathered by Radian Corporation at a coal-fired power plant, designated Site 16, for a program sponsored by the United States Department of Energy (DOE), Southern Company Services (SCS), and the Electric Power Research Institute (EPRI). Concentrations of selected inorganic and organic substances were measured in the process and discharge streams of the plant operating under two different types of combustion modifications: overfire air (OFA) and a combination of overfire air with low-NO{sub x} burners (OFA/LNB). Information contained in this report will allow DOE and EPRI to determine the effects of low-NO{sub x} modifications on plant emissions and discharges. Sampling was performed on an opposed wall-fired boiler burning medium-sulfur bituminous coal. Emissions were controlled by electrostatic precipitators (ESPs). The testing was conducted in two distinct sampling periods, with the OFA test performed in March of 1991 and the OFA/LNB test performed in May of 1993. Specific objectives were: to quantify emissions of target substances from the stack; to determine the efficiency of the ESPs for removing the target substances; and to determine the fate of target substances in the various plant discharge streams.

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

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

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

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

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.

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.

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.

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

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

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.)

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

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

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)

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

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)

Reporting of quantitative oxygen mapping in EPR imaging

Science.gov (United States)

Subramanian, Sankaran; Devasahayam, Nallathamby; McMillan, Alan; Matsumoto, Shingo; Munasinghe, Jeeva P.; Saito, Keita; Mitchell, James B.; Chandramouli, Gadisetti V. R.; Krishna, Murali C.

2012-01-01

Oxygen maps derived from electron paramagnetic resonance spectral-spatial imaging (EPRI) are based upon the relaxivity of molecular oxygen with paramagnetic spin probes. This technique can be combined with MRI to facilitate mapping of pO 2 values in specific anatomic locations with high precision. The co-registration procedure, which matches the physical and digital dimensions of EPR and MR images, may present the pO 2 map at the higher MRI resolution, exaggerating the spatial resolution of oxygen, making it difficult to precisely distinguish hypoxic regions from normoxic regions. The latter distinction is critical in monitoring the treatment of cancer by radiation and chemotherapy, since it is well-established that hypoxic regions are three or four times more resistant to treatment compared to normoxic regions. The aim of this article is to describe pO 2 maps based on the intrinsic resolution of EPRI. A spectral parameter that affects the intrinsic spatial resolution of EPRI is the full width at half maximum (FWHM) height of the gradient-free EPR absorption line in frequency-encoded imaging. In single point imaging too, the transverse relaxation times (T2∗) limit the resolution since the signal decays by exp(-tp/T2∗) where the delay time after excitation pulse, t p, is related to the resolution. Although the spin densities of two point objects may be resolved at this separation, it is inadequate to evaluate quantitative changes of pO 2 levels since the linewidths are proportionately affected by pO 2. A spatial separation of at least twice this resolution is necessary to correctly identify a change in pO 2 level. In addition, the pO 2 values are blurred by uncertainties arising from spectral dimensions. Blurring due to noise and low resolution modulates the pO 2 levels at the boundaries of hypoxic and normoxic regions resulting in higher apparent pO 2 levels in hypoxic regions. Therefore, specification of intrinsic resolution and pO 2 uncertainties are

Solar-Assisted Electric Vehicle Charging Station Interim Report

Energy Technology Data Exchange (ETDEWEB)

Lapsa, Melissa Voss [ORNL; Durfee, Norman [ORNL; Maxey, L Curt [ORNL; Overbey, Randall M [ORNL

2011-09-01

Oak Ridge National Laboratory (ORNL) has been awarded $6.8 million in the Department of Energy (DOE) American Recovery and Reinvestment Act (ARRA) funds as part of an overall $114.8 million ECOtality grant with matching funds from regional partners to install 125 solar-assisted Electric Vehicle (EV) charging stations across Knoxville, Nashville, Chattanooga, and Memphis. Significant progress has been made toward completing the scope with the installation of 25 solar-assisted charging stations at ORNL; six stations at Electric Power Research Institute (EPRI); and 27 stations at Nissan's Smyrna and Franklin sites, with three more stations under construction at Nissan's new lithium-ion battery plant. Additionally, the procurement process for contracting the installation of 34 stations at Knoxville, the University of Tennessee Knoxville (UTK), and Nashville sites is underway with completion of installation scheduled for early 2012. Progress is also being made on finalizing sites and beginning installations of 30 stations in Nashville, Chattanooga, and Memphis by EPRI and Tennessee Valley Authority (TVA). The solar-assisted EV charging station project has made great strides in fiscal year 2011. A total of 58 solar-assisted EV parking spaces have been commissioned in East and Middle Tennessee, and progress on installing the remaining 67 spaces is well underway. The contract for the 34 stations planned for Knoxville, UTK, and Nashville should be underway in October with completion scheduled for the end of March 2012; the remaining three Nissan stations are under construction and scheduled to be complete in November; and the EPRI/TVA stations for Chattanooga, Vanderbilt, and Memphis are underway and should be complete by the end of March 2012. As additional Nissan LEAFs are being delivered, usage of the charging stations has increased substantially. The project is on course to complete all 125 solar-assisted EV charging stations in time to collect meaningful data

Development of a Coal Quality Expert

Energy Technology Data Exchange (ETDEWEB)

None

1998-06-20

ABB Power Plant Laboratories Combustion Engineering, Inc., (ABB CE) and CQ Inc. completed a broad, comprehensive program to demonstrate the economic and environmental benefits of using higher quality U.S. coals for electrical power generation and developed state-of-the-art user-friendly software--Coal Quality Expert (CQE)-to reliably predict/estimate these benefits in a consistent manner. The program was an essential extension and integration of R and D projects performed in the past under U.S. DOE and EPRI sponsorship and it expanded the available database of coal quality and power plant performance information. This software will permit utilities to purchase the lowest cost clean coals tailored to their specific requirements. Based on common interest and mutual benefit, the subject program was cosponsored by the U.S. DOE, EPRI, and eight U.S. coal-burning utilities. In addition to cosponsoring this program, EPN contributed its background research, data, and computer models, and managed some other supporting contracts under the terms of a project agreement established between CQ Inc. and EPRI. The essential work of the proposed project was performed under separate contracts to CQ Inc. by Electric Power Technologies (El?'T), Black and Veatch (B and V), ABB Combustion Engineering, Babcock and Wilcox (B and W), and Decision Focus, Inc. Although a significant quantity of the coals tied in the United States are now cleaned to some degree before firing, for many of these coals the residual sulfur content requires users to install expensive sulfur removal systems and the residual ash causes boilers to operate inefficiently and to require frequent maintenance. Disposal of the large quantities of slag and ash at utility plant sites can also be problematic and expensive. Improved and advanced coal cleaning processes can reduce the sulfur content of many coals to levels conforming to environmental standards without requiring post-combustion desulfurization systems. Also

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

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

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)

Factors involved in the selection of limestone reagents for use in wet FGD systems

International Nuclear Information System (INIS)

Jarvis, J.B.; Roothaan, E.S.; Meserole, F.B.; Owens, D.R.

1992-01-01

With recent activity in the design and construction of retrofit flue gas desulfurization (FGD) systems, many utilities are faced with the task of selecting limestones which will allow FGD systems to function as designed, and at the same time, provide cost-effective operation. The Electric Power Research Institute (EPRI) has sponsored research to identify factors which should be considered in the reagent selection process. A set of capabilities has been developed which is currently being employed to assist six utilities in selecting cost-effective reagent sources. The major elements in the selection package consist of an analytical characterization of candidate limestones; grindability, reactivity, and magnesium availability testing; and performance modeling utilizing EPRI's FGD PRocess Integration and Simulation Model (FGDPRISM). The results from these measurements are used to perform a site-specific economic analysis which can be used to rank the candidate limestones and quantify the impact of various limestone properties on plant operating costs. This paper includes a description of each element in the selection package along with a review of current research activities aimed at improving predictions of limestone reactivity and magnesium availability. An example is presented which illustrates how reactivity and magnesium availability affect both the performance of an FGD system and plant operating costs

USW[center dot]33M-VS wind power turbine winning a 1993 environmental department prize of Discover Magazine. 1993 nendo DISCOVER kankyo bumonsho ni USW/33M-VS furyoku turbine

Energy Technology Data Exchange (ETDEWEB)

Ushiyama, M. (Waseda University, Tokyo (Japan))

1993-12-01

This paper introduces a variable speed wind power turbine developed jointly by EPRI and US Wind Power Corporation. This wind power turbine has a wind velocity responsive construction in which generated alternating current power has the frequency vary with change in the shaft rotation speed. The specified performance calls for a cut-in of 4 m/s and cut-out of 29 m/s, wind velocity variable. The blades are made of laminated fiberglass, and the rotor has a diameter of 33 m, rotation variable. The tower height is classified to 24 m, 30 m, and 42 m. The blade pitch is controlled by a linear hydraulic cylinder, and the turbine is controlled by a microprocessor. The wind turbine has a system interconnecting control and data collecting system. Two induction three-phase generators are used. EPRI has calculated its power generation cost at 5 cents/kWh if wind blows at an annual average velocity of 16 miles per hour. This is nearly equivalent to the cost at new power plants. US Wind Power Corporation has disassembled 22 experimental models that have been in operation to investigate wear in the machines. Its economy is evaluated comparable with that for fossil fuel technologies. 1 fig.

Assessments of CHF correlations based on full-scale rod bundle experiments

International Nuclear Information System (INIS)

Sardh, K.; Becker, K.M.

1986-02-01

In the present study the Barnett, the Becker, the Biasi, the CISE-4, the XN-1, the EPRI and the Bezrukov burnout correlations have been compared with burnout measurements obtained with full scale 81, 64, 36 and 37-rod bundles. The total power as well as the local power hypothesis was employed for the comparisons. The results clearly indicated that the Biasi and the CISE-4 correlations do not predict the burnout conditions in full-scale rod bundles. Since, these correlations yield non-conservative results their use in computer programs as for instance RELAP, TRAC or NORA should be avoided. Considering that the effects of spacers were not included in the predictions, the Becker and the Bezrukov correlations were in excellent agreement with the experimental data. However, it should be pointed out that the Bezrukov correlation only covered the 70 and 90 bar data, while the Becker correlation agreed with the experimental data in the whole pressure range between 30 and 90 bar. The Barnett, the XN-1 and the EPRI correlations were also in satisfactory agreement with the experiments. We therefore conclude that for predictions of the burnout conditions in full-scale BWR rod bundles the Becker correlation should be employed. (author)

Assessment of inspectability of LMFBR designs. Final report

International Nuclear Information System (INIS)

1981-09-01

This two-volume report provides a comprehensive review of the inspectability of specific portions of loop- and pool-type LMFBR (1000-MWe) designs selected by EPRI. The designs were developed during the mid to late 1970s by three independent design teams (General Electric Co., Rockwell International, and Westinghouse) under the sponsorship of DOE (formerly ERDA) and EPRI. The requirements for normal, contingency, and post-repair inspections, addressed in this report, were established from Draft 12 of the ASME Boiler and Pressure Vessel Code, Section XI Division 3, issued in September 1979. These requirements, the intrinsic characteristics of the designs, the environmental (radiation, thermal, and atmospheric) aspects, and the available (present and near-term) inspection techniques, formed the basis for assessing the selected portions of the design or (1) accessibility, (2) feasibility, (3) practicality, and (4) costs to perform the above-specified inspections. Changes and additions fly ash has been as a concrete additive; however, extensive pilot scale development is underway to advance ash use in the TVA region in such areas as mineral and magnetite recovery, and mineral wool insulation. Recommended studies include: (1) the feasibility of converting existing wet fly d by the fuels include: residential (which includes residential and commercial), elthodology will be developed and verified in Phase II

Technology development by the U.S. industry to resolve erosion-corrosion

International Nuclear Information System (INIS)

Chexal, B.; Dietrich, N.; Horowitz, J.; Layman, W.; Randall, G.; Shevde, V.

1990-01-01

Erosion-corrosion is a flow-accelerated corrosion process that leads to wall thinning (metal loss) of steel piping exposed to flowing water or wet steam. The rate of metal loss depends on a complex interplay of several parameters. These parameters include water chemistry, material composition, and hydrodynamics. Erosion-corrosion of plant piping can lead to costly outages and repairs, and can raise concerns about plant reliability and safety. Pipe wall degradation rates as high as 1.5 mm/year have occurred, resulting in pipe ruptures at both fossil and nuclear plants. The Nuclear Management and Resource Council (NUMARC) and EPRI have developed inspection planning methods and tools to help utilities identify areas of piping that might undergo erosion-corrosion. These tools provide utilities with the ability to predict wall thinning and to assess various remedial options. This allows utilities to plan and perform inspections, and to correct problems found during inspection. The U.S. electric power industry has developed the knowledge and the tools needed to protect against erosion-corrosion, and utilities have implemented erosion-corrosion monitoring programs. This paper describes EPRI's technical developments that support the utilities in determining where to inspect for erosion-corrosion. 15 refs, 7 figs

Instrumentation and control strategies for power plants. Volume 2: Problem definition and recommendations. Final report, December 1990

International Nuclear Information System (INIS)

1990-12-01

The I and C systems now in service are largely based on process technology from the 50s and 60s. Replacement parts are becoming unavailable and the infrastructure of designers, engineers and manufacturers to support the existing obsolete I and C technology is disappearing. Without the stimulus of new plant orders, there has been little incentive to develop new nuclear plant I and C technology. State-of-the-art I and C systems can provide highly analyzed status information, can control complex functions in a more refined way, are more reliable, and more economical. Modern I and C technology takes full advantage of both analog and digital capabilities, using each to its best advantage. EPRI is expanding its efforts to bridge the gap that had developed between the U.S. power industry and state-of-the-art I and C technology. In March of 1990 EPRI sponsored an I and C workshop to solicit utility industry views as to how this effort could most productively proceed. The material of the workshop, which is described in this report (Volumes 1 and 2), covered where we are in I and C technology, where we need to go, and provided input toward defining a strategy for I and C research and development. (author)

Transmission and Distribution: AREVA takes further action to reinforce its presence in China

International Nuclear Information System (INIS)

2007-05-01

Following the recent opening of its new gas-insulated switchgear factory last month in Suzhou, China, AREVA's Transmission and Distribution (T and D) division has announced additional actions to increase its market share in the country. The division has just signed an agreement to form a 50/50 joint venture with the Chinese company, Sunten Electric Co. Ltd., a leading manufacturer of distribution transformers, whose 2006 annual sales reached circa euro 120 million. Through this joint venture, AREVA T and D will become No 1 in China for dry-type transformers, Sunten Electric Co. Ltd.'s specialization. AREVA T and D has also established a partnership with the China Electric Power Research Institute (C-EPRI), a leading Chinese organization specialized in electrical technologies. Under the agreement, C-EPRI will be the official licensee for AREVA T and D's H-400 high-voltage direct current (HVDC) Thyristor valves in China. The partnership will enable AREVA T and D to enter the fast-growing domestic HVDC market. The T and D sector in China represents 24% of the worldwide transmission and distribution market. AREVA T and D's turnover in China, where demand for T and D equipment is growing strongly, should significantly contribute to the division's objective to reach euro 5 billion in sales by 2010

Spanish approach to research and development applied to steam generator tubes structural integrity and life management

International Nuclear Information System (INIS)

Lozano, J.; Bollini, G.J.

1997-01-01

The operating experience acquired from certain Spanish Nuclear Power Plant steam generators shows that the tubes, which constitute the second barrier to release of fission products, are susceptible to mechanical damage and corrosion as a result of a variety of mechanisms, among them wastage, pitting, intergranular attack (IGA), stress-corrosion cracking (SCC), fatigue-induced cracking, fretting, erosion/corrosion, support plate denting, etc. These problems, which are common in many plants throughout the world, have required numerous investments by the plants (water treatment plants, replacement of secondary side materials such as condensers and heaters, etc.), have meant costs (operation, inspection and maintenance) and have led to the unavailability of the affected units. In identifying and implementing all these preventive and corrective measures, the Spanish utilities have moved through three successive stages: in the initial stage, the main source of information and of proposals for solutions was the Plant Vendor, whose participation in this respect was based on his own Research and Development programs; subsequently, the Spanish utilities participated jointly in the EPRI Steam Generator Owners Group, collaborating in financing; finally, the Spanish utilities set up their own Steam Generator Research and Development program, while maintaining relations with EPRI programs and those of other countries through information interchange

The use of research results for effective aging management

International Nuclear Information System (INIS)

Gunther, W.E.; Taylor, J.H.

1989-01-01

The study of the degradation of structures, components, and systems due to aging is an important ongoing area of research in the nuclear industry. Efforts by the U.S. Nuclear Regulatory Commission (NRC) and the utility industry, through organizations such as the Electric Power Research Institute (EPRI), have produced substantial research results that can be used by inspectors and operators to effectively understand and manage the aging of nuclear power plants. One of the primary objectives of the NRC's Nuclear Plant Aging Research (NPAR) Program is to determine how aging affects the safety of nuclear power plants. This program uses operating experience, testing, and engineering analysis to identify failures caused by age-related degradation. Useful information on aging has also resulted from research being performed by the industry to support plant-life extension (PLEX). The EPRI program, for instance, is directed toward the resolution of issues related to materials and components. Degradation of equipment and systems due to aging can occur which, if unmitigated, could result in reduction of the nuclear power plant safety margin as the plant ages. This paper describes how aging research results may be used by plant operating management to effectively address the aging issue and by inspectors responsible for monitoring plant activities and programs

Development of an ultrasonic flow and temperature measurement system for pressurized water reactors

International Nuclear Information System (INIS)

James, R.W.; Lubnow, T.; Baumgart, G.; Ravetti, D.

1996-01-01

In U.S. nuclear plants, primary coolant flow and reactor thermal power are calculated from a measurement of feedwater flow to the steam generator combined with knowledge of steam generator heat transfer characteristics nd measurement of hot leg temperature by resistance temperature detectors (RTDs). The calculation of plant thermal output is complicated by an indirect measurement of primary coolant mass flow rate and thermal streaming in the region where hot leg temperature is typically measured. Uncertainty in the thermal output calculation results from uncertainties in steam generator characteristics, in the hot leg temperature due to thermal streaming, and in fouling of venturi nozzles used for feedwater flow measurement. This in turn leads to operation of power plants ar lower levels of efficiency. The Electric Power Research Institute (EPRI) has on ongoing project to develop a prototype system to directly measure primary coolant flow rate and bulk average temperature using ultrasonic transducers externally mounted on the pipe. The topic of this paper is a summary of the project experience in developing this system. The technology being developed in this project is based in part upon previously existing ultrasonic feedwater flow measurement technology developed by MPR Associates and Caldon, Inc EPRI is a non-profit company performing research for U.S. and international electric power utilities. (authors)

Reactor fuel reliability constraints on power shape control

International Nuclear Information System (INIS)

Gelhaus, F.; Hallam, J.; Sauar, T.

1977-01-01

The level of reliability of fuel rods operating in commercial nuclear power plants has been less than desired for a number of reasons. Several of these causes have been successfully minimized, but pellet-clad interaction failures persist. Since power and power change are dominant parameters in this failure mode, restrictions on operational maneuvers have been recommended by all U. S. fuel suppliers. Slower-than-design allowable maneuvers decrease the plant capacity factor, which can cost a utility up to $7 million per year per plant. To assist utility engineering and operations personnel in their day-to-day decisions in this regard, the Electric Power Research Institute (EPRI) is initiating a project, designated RP895, to develop a fully computerized Power Shape Monitoring System (PSMS) for core-wide fuel rod reliability prediction. This paper describes the PSMS system and details some of the hardware/software requirements as they are now perceived. Salient results from a just-completed complementary EPRI-funded study, RP509, are described; this effort employed hand data acquisition and many man-machine interfaces that will be fully integrated and automated in the PSMS. The capabilities of the PSMS will derive from the use of modern minicomputer hardware and software and from accurate computational modules that enable near-real-time predictive capability

Tritium interactions of potential importance to fusion reactor systems: technology requirements

International Nuclear Information System (INIS)

Wilkes, W.R.

1976-01-01

The tritium technology requirements created by the controlled thermonuclear research program to develop a demonstration fusion power reactor by the year 2000 are reviewed. It is found that the majority of the technological advances which are needed to ensure adequate tritium containment in a tritium breeding power reactor need to be demonstrated on a pilot scale by approximately 1983, so that they may be incorporated into EPR-II, the second of two planned experimental power reactors. The most important advances include development of containment materials with permeabilities to tritium well below measured values for stainless steel; large scale, low inventory deuterium-tritium separation systems; and improved monitoring and assay systems. There are less critical requirements for information about the effects of tritium and helium on the mechanical properties of materials, the effects of tritium on biological systems, and data on physical and chemical properties of tritium. Substantial progress needs to be made on these problems early enough to permit possible solutions to be tested on EPR-I. In addition, major improvements in tritium handling equipment are required for EPR-I. Those technological problems for which solutions have not yet been demonstrated by EPR-II must be solved by 1989 if they are to be assured successful application in the demonstration reactor

Outage Risk Assessment and Management (ORAM) technology to improve outage safety and economics

International Nuclear Information System (INIS)

Kalra, S.P.

2004-01-01

The Electric Power Research Institute (EPRI) has undertaken an aggressive program, called ORAM (Outage Risk Assessment and Management), to provide utilities with tools and technology to assist in managing risk during the planning and conduct of outages. The ORAM program consists of the following 6 steps: i) Perform utility surveys and visits on shutdown risk management needs, ii) Perform probabilistic shutdown safety assessments (PSSAs) to identify generic insights that can be incorporated into risk management guidelines and identify selected areas for the development of contingency actions, iii) Develop risk management guidelines (RMG's) that provide a systematic approach to the planning and conduct of outages from a safety perspective. Incorporate insights from the shutdown safety assessments and other operating experience into the RMG's. iv) Develop selected contingency actions including a thermalhydraulic tool kit to address higher risk time periods and activities identified in the shutdown safety assessments, v) Develop computer software that integrates all of the above capability into an easy to use tool for effective shutdown operation management for utilities, vi) Provide assistance in the transfer of this technology and the application of these tools. This paper briefly describes the technical approach and tools developed under EPRI's ORAM program and its applications for improving outage safety and economics. (author)

A demonstration of strobe lights to repel fish

International Nuclear Information System (INIS)

Martin, P.; Downing, J.; Taft, N.; Sullivan, C.

1991-01-01

This paper reports is an EPRI review of fish protection systems for hydroelectric facilities which identified strobe lights as a potential behavioral system to minimize fish entrainment. In 1988, EPRI initiated an evaluation of juvenile American shad response to strobe lights at Metropolitan Edison's York Haven Power Station on the Susquehanna River. During their fall migration, juvenile shad accumulate in the forebay. In 1988, using a raft mounted with four strobe lights, it was clearly demonstrated that shad could be excluded from the area in front of the trash racks, and bypassed through a sluiceway into the tailrace. Hydroacoustics were used to monitor the effectiveness of the strobe lights. In 1989, six rafts supporting 22 strobe light were moored in front of the trash racks. Unit outages and river flooding limited a full evaluation of the strobe system. Under limited test conditions, it was possible to confirm shad avoidance of strobe lights similar to that observed in 1988. In 1990, testing was performed with a fully operational strobe system under normal flow conditions and hydraulics. Testing showed that shad could be effectively passed around the York Haven Station. The results of the 1990 studies were more extensive than those of 1989, however, flood waters again limited complete testing of the system

Generation of plastic influence functions for J-integral and crack opening displacement of thin-walled pipes with a short circumferential through-wall crack

International Nuclear Information System (INIS)

Park, Jeong Soon; Choi, Young Hwan; Im, Seyoung

2014-01-01

Fracture mechanics parameters such as the J-integral and crack opening displacement (COD), are necessary for Leak-Before-Break (LBB) evaluation. The famous two estimation methods, the GE/EPRI and the Reference Stress Method (RSM), have their applicability limit with regard to the ratio of a pipe mean radius to thickness (R m /t). In order to extend their applicability limit to a thin walled pipe, several finite element analyses are performed for the J-integral and COD, and then new plastic influence functions are developed for thin-walled pipes with a short circumferential through-wall crack. With the newly generated plastic influence functions, the GE/EPRI and the RSM give closer results with those obtained from detailed finite element analyses. In addition, C*-integral and COD rate are estimated by using the new plastic influence functions and they are well matched with elastic–creep finite element analysis results under the power-law creep condition. Since the LBB concept can be applied to a piping system in a Korean Sodium-cooled Fast Reactor (SFR) which is designed to have thin-walled pipes and to operate in high temperature enough to cause creep, this paper can be applied for the LBB assessment of thin-walled pipes with a short through-wall crack in the SFR

Qualification of NDE personnel in the nuclear industry

International Nuclear Information System (INIS)

Epps, T.N.

1984-01-01

There has been evidence of ineffective programs for certifying nondestructive examination (NDE) personnel who conduct periodic inservice examinations in nuclear power plants under ASME Section XI Code requirements. This was brought to the attention of a group from the electric utility industry, the Electric Power Research Institute (EPRI), some NDE consultants and representatives from the American Society of Mechanical Engineers (ASME) by the Nuclear Regulatory Commission (NRC) in a May, 1982 meeting in Bethesda, Maryland. One problem pointed out by the NRC was the lack of a clear definition of qualification requirements for certification of NDE personnel who conduct ASME Section XI Inservice Inspection work in nuclear power plants. The NRC requested that the nuclear industry resolve this problem by formulating definitive qualification requirements for personnel certification that could be made an industry requirement. In June, 1982 the EPRI NDE Subcommittee held a general meeting for utility representatives to discuss the results of the May, 1982 meeting to develop a plan for industry response to the issue. The consensus was that an Ad Hoc Committee of utility representatives be convened to develop a document outlining qualification requirements for vertification of NDE personnel. The Ad Hoc Committee was formally convened on September 29, 1982

A study of toxic emissions from a coal-fired gasification plant. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

Under the Fine Particulate Control/Air Toxics Program, the US Department of Energy (DOE) has been performing comprehensive assessments of toxic substance emissions from coal-fired electric utility units. An objective of this program is to provide information to the US Environmental Protection Agency (EPA) for use in evaluating hazardous air pollutant emissions as required by the Clean Air Act Amendments (CAAA) of 1990. The Electric Power Research Institute (EPRI) has also performed comprehensive assessments of emissions from many power plants and provided the information to the EPA. The DOE program was implemented in two. Phase 1 involved the characterization of eight utility units, with options to sample additional units in Phase 2. Radian was one of five contractors selected to perform these toxic emission assessments.Radian`s Phase 1 test site was at southern Company Service`s Plant Yates, Unit 1, which, as part of the DOE`s Clean Coal Technology Program, was demonstrating the CT-121 flue gas desulfurization technology. A commercial-scale prototype integrated gasification-combined cycle (IGCC) power plant was selected by DOE for Phase 2 testing. Funding for the Phase 2 effort was provided by DOE, with assistance from EPRI and the host site, the Louisiana Gasification Technology, Inc. (LGTI) project This document presents the results of that effort.

Integral transport computation of gamma detector response with the CPM2 code

International Nuclear Information System (INIS)

Jones, D.B.

1989-12-01

CPM-2 Version 3 is an enhanced version of the CPM-2 lattice physics computer code which supports the capabilities to (1) perform a two-dimensional gamma flux calculation and (2) perform Restart/Data file maintenance operations. The Gamma Calculation Module implemented in CPM-2 was first developed for EPRI in the CASMO-1 computer code by Studsvik Energiteknik under EPRI Agreement RP2352-01. The gamma transport calculation uses the CPM-HET code module to calculate the transport of gamma rays in two dimensions in a mixed cylindrical-rectangular geometry, where the basic fuel assembly and component regions are maintained in a rectangular geometry, but the fuel pins are represented as cylinders within a square pin cell mesh. Such a capability is needed to represent gamma transport in an essentially transparent medium containing spatially distributed ''black'' cylindrical pins. Under a subcontract to RP2352-01, RPI developed the gamma production and gamma interaction library used for gamma calculation. The CPM-2 gamma calculation was verified against reference results generated by Studsvik using the CASMO-1 program. The CPM-2 Restart/Data file maintenance capabilities provide the user with options to copy files between Restart/Data tapes and to purge files from the Restart/Data tapes

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)

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

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

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

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

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

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

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

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

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

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

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.

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

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

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

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

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.

Fukushima Daiichi Unit 1 power plant containment analysis using GOTHIC

International Nuclear Information System (INIS)

Ozdemir, Ozkan Emre; George, Thomas L.; Marshall, Mervin D.

2015-01-01

Highlights: • The inclusion of vent heat transfer had a significant impact on the overall containment response. • The vent heat transfer and condensation results in lower containment pressure. • The reduced gas transfer to the wetwell via the vents results in higher hydrogen concentration in the drywell. - Abstract: This paper is a part of Fukushima Technical Evaluation Project (EPRI, 2013a, 2014a, 2015) which investigates various aspects of the Fukushima Daiichi event using the GOTHIC code. The analysis takes advantage of the capability of GOTHIC to model certain aspects of the system geometry and behavior in more detail than typically considered in containment performance analysis. GOTHIC is a general purpose thermal hydraulics code that is used extensively in the nuclear industry for system design support, licensing support and safety analysis. It has the capability to model 3-dimensional flow behavior including the effects of turbulence, diffusion and buoyancy (EPRI, 2014b). This allows GOTHIC to be used in cases where mixing effects and stratification are important. The analysis presented here considers the events at Fukushima Daiichi Unit 1 (1F1) following the tsunami and leading up to the time of the hydrogen detonation in the 1F1 Reactor Building. The 1F1 MAAP5 Baseline Scenario (EPRI, 2013b) is used to define the steam, hydrogen and carbon-monoxide source terms from the primary system and the core concrete interaction. The model incorporates three dimensional modeling of the drywell, wetwell and connecting vent system that can predict the 3-dimensional flow patterns and the temperature and gas distributions. The model also includes leakage to the surrounding reactor building and the wetwell vent to the stack. The 3D containment model includes models for the heat transfer from the steam and gas in the drywell vent system to the torus room, wetwell gas space and pool. Inclusion of vent heat transfer had a significant impact on the overall containment

SRS BEDROCK PROBABILISTIC SEISMIC HAZARD ANALYSIS (PSHA) DESIGN BASIS JUSTIFICATION (U)

Energy Technology Data Exchange (ETDEWEB)

(NOEMAIL), R

2005-12-14

This represents an assessment of the available Savannah River Site (SRS) hard-rock probabilistic seismic hazard assessments (PSHAs), including PSHAs recently completed, for incorporation in the SRS seismic hazard update. The prior assessment of the SRS seismic design basis (WSRC, 1997) incorporated the results from two PSHAs that were published in 1988 and 1993. Because of the vintage of these studies, an assessment is necessary to establish the value of these PSHAs considering more recently collected data affecting seismic hazards and the availability of more recent PSHAs. This task is consistent with the Department of Energy (DOE) order, DOE O 420.1B and DOE guidance document DOE G 420.1-2. Following DOE guidance, the National Map Hazard was reviewed and incorporated in this assessment. In addition to the National Map hazard, alternative ground motion attenuation models (GMAMs) are used with the National Map source model to produce alternate hazard assessments for the SRS. These hazard assessments are the basis for the updated hard-rock hazard recommendation made in this report. The development and comparison of hazard based on the National Map models and PSHAs completed using alternate GMAMs provides increased confidence in this hazard recommendation. The alternate GMAMs are the EPRI (2004), USGS (2002) and a regional specific model (Silva et al., 2004). Weights of 0.6, 0.3 and 0.1 are recommended for EPRI (2004), USGS (2002) and Silva et al. (2004) respectively. This weighting gives cluster weights of .39, .29, .15, .17 for the 1-corner, 2-corner, hybrid, and Greens-function models, respectively. This assessment is judged to be conservative as compared to WSRC (1997) and incorporates the range of prevailing expert opinion pertinent to the development of seismic hazard at the SRS. The corresponding SRS hard-rock uniform hazard spectra are greater than the design spectra developed in WSRC (1997) that were based on the LLNL (1993) and EPRI (1988) PSHAs. The

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

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.

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

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)

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)

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

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.

Department of Energy interest and involvement in nuclear plant license renewal activities

International Nuclear Information System (INIS)

Bustard, L.D.; Harrison, D.L.

1991-01-01

Recognizing the importance of nuclear license renewal to the nation's energy strategy, the Department of Energy (DOE) initiated a plant lifetime improvement program during 1985 to determine the feasibility of the license renewal option for US nuclear plants. Initial activities of the DOE program focused on determining whether there were technical and economic obstacles that might preclude or limit the successful implementation of the license renewal option. To make this determination, DOE cosponsored with the Electric Power Research Institute (EPRI) pilot-plant efforts by Virginia Electric Power and Northern States Power. Both pilot-plant efforts concluded that life extension is technically and economically feasible. In parallel with the pilot-plant activities, DOE performed national economic studies that demonstrated the economic desirability of life extension. Having demonstrated the feasibility of life extension, DOE, in conjunction with EPRI, selected two lead plants to demonstrate the license renewal process. These lead plants are Yankee Atomic's Yankee Rowe facility and Northern States Power's Monticello facility. DOE also initiated activities to develop the technical and regulatory bases to support the license renewal process in the United States. DOE has recently identified nuclear plant license renewal to be an important element of its National Energy Strategy. This paper summarizes the significant results, conclusions, and ongoing activities of the DOE effort. 18 refs

Review of earthquake hazard assessments of plant sites at Paducah, Kentucky and Portsmouth, Ohio

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

Members of the US Geological Survey staff in Golden, Colorado, have reviewed the submissions of Lawrence Livermore National Laboratory (LLNL) staff and of Risk Engineering, Inc. (REI) (Golden, Colorado) for seismic hazard estimates for Department of Energy facilities at Portsmouth, Ohio, and Paducah, Kentucky. We reviewed the historical seismicity and seismotectonics near the two sites, and general features of the LLNL and EPRI/SOG methodologies used by LLNL and Risk Engineering respectively, and also the separate Risk Engineering methodology used at Paducah. We discussed generic issues that affect the modeling of both sites, and performed alternative calculations to determine sensitivities of seismic hazard results to various assumptions and models in an attempt to assign reasonable bounding values of the hazard. In our studies we find that peak acceleration values of 0.08 g for Portsmouth and 0.32 g for Paducah represent central values of the, ground motions obtained at 1000-year return periods. Peak accelerations obtained in the LLNL and Risk Engineering studies have medians near these values (results obtained using the EPRI/SOG methodology appear low at both sites), and we believe that these medians are appropriate values for use in the evaluation of systems, structures, and components for seismic structural integrity and for the seismic design of new and improved systems, structures, and components at Portsmouth and Paducah.

Insulation coordination workstation for AC and DC substations

International Nuclear Information System (INIS)

Booth, R.R.; Hileman, A.R.

1990-01-01

The Insulation Coordination Workstation was designed to aid the substation design engineer in the insulation coordination process. The workstation utilizes state of the art computer technology to present a set of tools necessary for substation insulation coordination, and to support the decision making process for all aspects of insulation coordination. The workstation is currently being developed for personal computers supporting OS/2 Presentation Manager. Modern Computer-Aided Software Engineering (CASE) technology was utilized to create an easily expandable framework which currently consists of four modules, each accessing a central application database. The heart of the workstation is a library of user-friendly application programs for the calculation of important voltage stresses used for the evaluation of insulation coordination. The Oneline Diagram is a graphic interface for data entry into the EPRI distributed EMTP program, which allows the creation of complex systems on the CRT screen using simple mouse clicks and keyboard entries. Station shielding is graphically represented in the Geographic Viewport using a three-dimensional substation model, and the interactive plotting package allows plotting of EPRI EMTP output results on the CRT screen, printer, or pen plotter. The Insulation Coordination Workstation was designed by Advanced Systems Technology (AST), a division of ABB Power Systems, Inc., and sponsored by the Electric Power Research Institute under RP 2323-5, AC/DC Insulation Coordination Workstation

Zero plastics and the radiologically protected area low level waste lockout program. Final report

International Nuclear Information System (INIS)

Kelly, J.

1995-11-01

In 1993, EPRI initiated its Integrated LLW Cost and Volume Reduction Program. One key component of the project was the identification of unique or uncommon techniques and approaches to LLW management which could be transported with or without modification to other members of EPRI's Nuclear Power Business Group. Included among these unique approaches were: some nuclear stations had aggressively eliminated most of the plastic materials commonly used in radiologically protected areas (RPA), these included plastic bags, plastic sheeting and plastic sleeving; a few nuclear stations had completely eliminated from the RPA some of the disposable items routinely considered by most nuclear stations as absolutely essential, these included masking tape, duct tape and wood; a couple of leading edge plants were implementing RPA LLW lockout programs in an effort to control absolutely all materials entering or exiting the RPA and making the worker 100% responsible for managing her/his work environment. The above three approaches were so significant in their actual or potential impact that it was decided to initiate an independent research project to evaluate and demonstrate whether all three concepts could be implemented by a single nuclear station and with significant, positive results. This project reports on that research and demonstration project which was implemented at LaSalle and Zion nuclear stations, both of which are operated by Commonwealth Edison Company

An overview of the NDE Center - The first decade

International Nuclear Information System (INIS)

Dau, G.J.

1990-01-01

The EPRI NDE Center was established in 1979 to provide the electrical utility industry with a dedicated NDE capability. The Center's role was defined as providing a bridge to transfer the research and development results generated by EPRI R and D programs (as well as other funding agencies) into qualified equipment and procedures in the shortest possible time. The mission is pursued through three distinct thrusts: technology transfer, training, and resource development. Technology transfer is usually accomplished by a combination of equipment and procedure evaluations and demonstrations. Specific training programs are developed to meet the specific needs of the utility industry. One feature of these programs is the reliance on realistic samples during the training programs. Resource development is oriented toward encouraging more people to pursue NDE as a career. This thrust is implemented by working with interested educational institutions to develop appropriate materials. Work in this project divides naturally into technology and training areas. NDE technology work is focused on improving the inspections applied to heat exchangers, piping, steam turbines, and heavy-section components such as the reactor pressure vessel. Training activities involve the provision of formal courses when a large number of people must become proficient in an improved technology. More details on each of these areas are given in sections that immediately follow

Use of 2.5-D and 3-D technology to evaluate control room upgrades

International Nuclear Information System (INIS)

Hanes, L. F.; Naser, J.

2006-01-01

This paper describes an Electric Power Research Inst. (EPRI) study in which 2.5-D and 3-D visualization technology was applied to evaluate the design of a nuclear power plant control room upgrade. The study involved converting 3-D CAD flies of a planned upgrade into a photo-realistic appearing virtual model, and evaluating the value and usefulness of the model. Nuclear utility and EPRI evaluators viewed and interacted with the control room virtual model with both 2.5-D and 3-D representations. They identified how control room and similar virtual models may be used by utilities for design and evaluation purposes; assessed potential economic and other benefits; and identified limitations, potential problems, and other issues regarding use of visualization technology for this and similar applications. In addition, the Halden CREATE (Control Room Engineering Advanced Tool-kit Environment) Verification Tool was applied to evaluate features of the virtual model against US NRC NUREG 0700 Revision 2 human factors engineering guidelines (NUREG 0700) [1]. The study results are very favorable for applying 2.5-D visualization technology to support upgrading nuclear power plant control rooms and other plant facilities. Results, however, show that today's 3-D immersive viewing systems are difficult to justify based on cost, availability and value of information provided for this application. (authors)

Organ specific mapping of in vivo redox state in control and cigarette smoke-exposed mice using EPR/NMR co-imaging

Science.gov (United States)

Caia, George L.; Efimova, Olga V.; Velayutham, Murugesan; El-Mahdy, Mohamed A.; Abdelghany, Tamer M.; Kesselring, Eric; Petryakov, Sergey; Sun, Ziqi; Samouilov, Alexandre; Zweier, Jay L.

2014-01-01

In vivo mapping of alterations in redox status is important for understanding organ specific pathology and disease. While electron paramagnetic resonance imaging (EPRI) enables spatial mapping of free radicals, it does not provide anatomic visualization of the body. Proton MRI is well suited to provide anatomical visualization. We applied EPR/NMR co-imaging instrumentation to map and monitor the redox state of living mice under normal or oxidative stress conditions induced by secondhand cigarette smoke (SHS) exposure. A hybrid co-imaging instrument, EPRI (1.2 GHz) / proton MRI (16.18 MHz), suitable for whole-body co-imaging of mice was utilized with common magnet and gradients along with dual EPR/NMR resonators that enable co-imaging without sample movement. The metabolism of the nitroxide probe, 3–carbamoyl–proxyl (3-CP), was used to map the redox state of control and SHS-exposed mice. Co-imaging allowed precise 3D mapping of radical distribution and reduction in major organs such as the heart, lungs, liver, bladder and kidneys. Reductive metabolism was markedly decreased in SHS-exposed mice and EPR/NMR co-imaging allowed quantitative assessment of this throughout the body. Thus, in vivo EPR/NMR co-imaging enables in vivo organ specific mapping of free radical metabolism and redox stress and the alterations that occur in the pathogenesis of disease. PMID:22296801

Final Report Report: Smart Grid Ready PV Inverters with Utility Communication

Energy Technology Data Exchange (ETDEWEB)

Seal, Brian [Electric Power Research Inst. (EPRI), Knovville, TN (United States); Huque, Aminul [Electric Power Research Inst. (EPRI), Knovville, TN (United States); Rogers, Lindsey [Electric Power Research Inst. (EPRI), Knovville, TN (United States); Key, Tom [Electric Power Research Inst. (EPRI), Knovville, TN (United States); Riley, Cameron [Electric Power Research Inst. (EPRI), Knovville, TN (United States); Li, Huijuan [Electric Power Research Inst. (EPRI), Knovville, TN (United States); York, Ben [Electric Power Research Inst. (EPRI), Knovville, TN (United States); Purcell, Chris [BPL Global, Inc., Canonsburg, PA (United States); Pacific, Oliver [Spirae, Inc., Fort Collins, CO (United States); Ropp, Michael [Northern Plains Power Technologies, Brookings, SD (United States); Tran, Teresa [DTE Energy, Detroit, MI (United States); Asgeirsson, Hawk [DTE Energy, Detroit, MI (United States); Woodard, Justin [National Grid, Warwick (United Kingdom); Steffel, Steve [Pepco Holdings, Inc., Washington, DC (United States)

2016-03-30

In 2011, EPRI began a four-year effort under the Department of Energy (DOE) SunShot Initiative Solar Energy Grid Integration Systems - Advanced Concepts (SEGIS-AC) to demonstrate smart grid ready inverters with utility communication. The objective of the project was to successfully implement and demonstrate effective utilization of inverters with grid support functionality to capture the full value of distributed photovoltaic (PV). The project leveraged ongoing investments and expanded PV inverter capabilities, to enable grid operators to better utilize these grid assets. Developing and implementing key elements of PV inverter grid support capabilities will increase the distribution system’s capacity for higher penetration levels of PV, while reducing the cost. The project team included EPRI, Yaskawa-Solectria Solar, Spirae, BPL Global, DTE Energy, National Grid, Pepco, EDD, NPPT and NREL. The project was divided into three phases: development, deployment, and demonstration. Within each phase, the key areas included: head-end communications for Distributed Energy Resources (DER) at the utility operations center; methods for coordinating DER with existing distribution equipment; back-end PV plant master controller; and inverters with smart-grid functionality. Four demonstration sites were chosen in three regions of the United States with different types of utility operating systems and implementations of utility-scale PV inverters. This report summarizes the project and findings from field demonstration at three utility sites.

Proceedings: 1993 fuel oil utilization workshop

International Nuclear Information System (INIS)

1994-08-01

The primary objective of the Workshop was to utilize the experiences of utility personnel and continue the interchange of information related to fuel oil issues. Participants also identified technical problem areas in which EPRI might best direct its efforts in research and development of fuel oil utilization and to improve oil-fired steam generating systems' performance. Speakers presented specific fuel projects conducted at their particular utilities, important issues in the utilization of fuel oil, studies conducted or currently in the process of being completed, and information on current and future regulations for fuel utilization. Among the major topics addressed at the 1993 Fuel Oil Utilization Workshop were burner and ESP improvements for the reduction of particulate and NO x emissions, practical experience in utilization of low API gravity residual fuel oils, the use of models to predict the spread of oil spills on land, implementing OPA 90 preparedness and response strategies planning, a report on the annual Utility Oil Buyers Conference, ASTM D-396 specification for No. 6 fuel oil, the utilization of Orimulsion reg-sign in utility boilers, recent progress on research addressing unburned carbon and opacity from oil-fired utility boilers, EPRI's hazardous air pollutant monitoring and implications for residual fuel oil, and the feasibility of toxic metals removal from residual fuel oils. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

Third annual Walker Branch Watershed research symposium. Program and abstracts

Energy Technology Data Exchange (ETDEWEB)

1992-03-01

The methods and concepts of watershed research, originally applied in an experimental or monitoring mode to relatively small catchments, are increasingly being used at larger scales and for specific applied problems. Research at Oak Ridge National Laboratory, the Tennessee Valley Authority, the US Forest Service, and other agencies and institutions participating in this symposium reflects research over a broad range of spatial scales that is being integrated through large-scale experiments along with computer modeling and graphical interfaces. These research projects address the basic atmospheric, geophysical, biogeochemical, and biological processes that regulate the responses of forested ecosystems to natural environmental variation and anthropogenic stresses. Regional and global issues addressed by presentations include emissions of carbon dioxide, methane, and other hydrocarbons; deposition of sulfate, nitrate, and mercury; land-use changes; biological diversity; droughts; and water quality. The reports presented in this symposium illustrate a wide range of methods and approaches and focus more on concepts and techniques than on a specific physical site. Sites and projects that have contributed research results to this symposium include Walker Branch Watershed (DOE), the Coweeta Hydrologic Laboratory and LTER site (USFS and NSF), Great Smoky Mountains National Park (research funded by NPS, TVA, and EPRI), Imnavait Creek, Alaska (DOE), the TVA-Norris Whole-tree Facility (TVA and EPRI), and DOE`s Biomass Program.

Review of earthquake hazard assessments of plant sites at Paducah, Kentucky, and Portsmouth, Ohio

International Nuclear Information System (INIS)

1992-03-01

Members of the US Geological Survey staff in Golden, Colorado, have reviewed the submissions of Lawrence Livermore National Laboratory (LLNL) staff and of Risk Engineering, Inc. (REI) (Golden, Colorado) for seismic hazard estimates for Department of Energy facilities at Portsmouth, Ohio, and Paducah, Kentucky. We reviewed the historical seismicity and seismotectonics near the two sites, and general features of the LLNL and EPRI/SOG methodologies used by LLNL and Risk Engineering respectively, and also the separate Risk Engineering methodology used at Paducah. We discussed generic issues that affect the modeling of both sites, and performed alternative calculations to determine sensitivities of seismic hazard results to various assumptions and models in an attempt to assign reasonable bounding values of the hazard. In our studies we find that peak acceleration values of 0.08 g for Portsmouth and 0.32 g for Paducah represent central values of the ground motions obtained at 1000-year return periods. Peak accelerations obtained in the LLNL and Risk Engineering studies have medians near these values (results obtained using the EPRI/SOG methodology appear low at both sites), and we believe that these medians are appropriate values for use in the evaluation of systems, structures, and components for seismic structural integrity and for the seismic design of new and improved systems, structures, and components at Portsmouth and Paducah

Advanced digital computers, controls, and automation technologies for power plants: Proceedings

International Nuclear Information System (INIS)

Bhatt, S.C.

1992-08-01

This document is a compilation of the papers that were presented at an EPRI workshop on Advances in Computers, Controls, and Automation Technologies for Power Plants. The workshop, sponsored by EPRI's Nuclear Power Division, took place February 1992. It was attended by 157 representatives from electric utilities, equipment manufacturers, engineering consulting organizations, universities, national laboratories, government agencies and international utilities. More than 40% of the attendees were from utilities representing the majority group. There were 30% attendees from equipment manufacturers and the engineering consulting organizations. The participants from government agencies, universities, and national laboratories were about 10% each. The workshop included a keynote address, 35 technical papers, and vendor's equipment demonstrations. The technical papers described the state-of-the-art in the areas of recent utility digital upgrades such as digital feedwater controllers, steam generator level controllers, integrated plant computer systems, computer aided diagnostics, automated testing and surveillance and other applications. A group of technical papers presented the ongoing B ampersand W PWR integrated plant control system prototype developments with the triple redundant advanced digital control system. Several international papers from France, Japan and U.K. presented their programs on advance power plant design and applications. Significant advances in the control and automation technologies such as adaptive controls, self-tuning methods, neural networks and expert systems were presented by developers, universities, and national laboratories. Individual papers are indexed separately

Sparing analysis for FGD systems

International Nuclear Information System (INIS)

Dene, C.E.; Weiss, J.; Twombly, M.A.; Witt, J.

1992-01-01

With the passage of federal clean air legislation, utilities will be evaluating the capability of various flue gas desulfurization (FGD) system design configurations and operating scenarios to meet sulfur dioxide (SO 2 ) removal goals. The primary goal in reviewing these alternatives will be to optimize SO 2 removal capability in relation to power production costs. The Electric Power Research institute (EPRI) and its contractor, ARINC Research Corporation, have developed an automated FGD Analysis System that can evaluate competing FGD design alternatives in terms of their SO 2 removal capability and operating costs. The FGD Analysis System can be used to evaluate different design configurations for new systems or to calculate the effect of changes in component reliability for existing FGD systems. The system is based on the EPRI UNIRAM methodology and evaluates the impact of alternative FGD component configurations on the expected unit emission rates. The user interactively enters FGD design data, unit SO 2 generation-level data, and FGD chemical additive-level data for the design configuration to be evaluated. The system then calculates expected SO 2 removal capability and operating cost data for operation of the design configuration over a user specified time period. This paper provides a brief description of the FGD Analysis System and presents sample results for three typical design configurations with different redundancy levels

Regulatory Drivers of Multimedia Reactive Nitrogen Research (Invited)

Science.gov (United States)

Shaw, S. L.; Knipping, E.; Kumar, N.

2010-12-01

The presence of nitrogenous compounds can impact biogeochemical processes in the atmosphere, oceans and freshwater, and land surfaces. As a result, a number of regulations exist that are intended to control the amount and forms of nitrogen present in the environment. These range from the newly proposed Transport Rule, both the primary and secondary National Ambient Air Quality Standards (NAAQS) for nitrogen oxide targeted at ozone and particulate matter formation and nitrogen deposition, and waterbody requirements such as the Total Maximum Daily Load. This talk will cover a subset of research activities at EPRI that inform environmental nitrogen concerns. A multimedia modeling framework has facilitated effect studies of atmospheric loadings on ecosystems. Improvements in emissions estimates, such as for mobile sources, suggest large current underestimates that will substantially impact air quality modeling of nitrogen oxides. Analyses of wintertime nitrate formation in the northern U.S. are demonstrating the roles of NH3 and NOx in particle formation there. Novel measurements of power plant stack emissions suggest operating configurations can influence the isotopic composition of emitted NOx. Novel instruments for ambient measurements of nitrogen, and suggestions for improved deposition estimates, are being developed. EPRI results suggest that multimedia solutions across multiple economic sectors, such as electrification of a wide variety of engines and water quality treatment and trading, have the potential to improve environmental quality effectively.

Review of earthquake hazard assessments of plant sites at Paducah, Kentucky and Portsmouth, Ohio

International Nuclear Information System (INIS)

1997-01-01

Members of the US Geological Survey staff in Golden, Colorado, have reviewed the submissions of Lawrence Livermore National Laboratory (LLNL) staff and of Risk Engineering, Inc. (REI) (Golden, Colorado) for seismic hazard estimates for Department of Energy facilities at Portsmouth, Ohio, and Paducah, Kentucky. We reviewed the historical seismicity and seismotectonics near the two sites, and general features of the LLNL and EPRI/SOG methodologies used by LLNL and Risk Engineering respectively, and also the separate Risk Engineering methodology used at Paducah. We discussed generic issues that affect the modeling of both sites, and performed alternative calculations to determine sensitivities of seismic hazard results to various assumptions and models in an attempt to assign reasonable bounding values of the hazard. In our studies we find that peak acceleration values of 0.08 g for Portsmouth and 0.32 g for Paducah represent central values of the, ground motions obtained at 1000-year return periods. Peak accelerations obtained in the LLNL and Risk Engineering studies have medians near these values (results obtained using the EPRI/SOG methodology appear low at both sites), and we believe that these medians are appropriate values for use in the evaluation of systems, structures, and components for seismic structural integrity and for the seismic design of new and improved systems, structures, and components at Portsmouth and Paducah

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)

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

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)

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.

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

Crystal River 3 Cable Materials for Thermal and Gamma Radiation Aging

Energy Technology Data Exchange (ETDEWEB)

Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Correa, Miguel [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zwoster, Andy [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-09-07

The Expanded Materials Degradation Assessment Volume 5: Aging of Cables and Cable Systems (EMDA) summarizes the state of knowledge of materials, constructions, operating environments, and aging behavior of low voltage and medium cables in nuclear power plants (NPPs) and identifies potential knowledge gaps with regard to cable operation beyond 60 years. The greatest area of uncertainty relates to how well the accelerated aging used in the original equipment qualification (EQ) processes predicts the performance of cable materials in extended operation. General opinion and utility experience have indicated that actual operating environments of in-plant cables are not as severe, however, as the operating and design basis environments used in the qualification process. Better understanding of the long term aging behavior of cable insulation materials in service conditions and the analysis of actual cable operating environments are the objectives of ongoing research to support subsequent license renewal activities in particular and long term cable aging management in general. A key component of the effort to better understand cable material aging behavior is the availability of representative samples of cables that have been installed in operating light water reactors and have experienced long term service. Unique access to long term service cables, including relatively rich information on cable identity and history, occurred in 2016 through the assistance of the Electric Power Research Institute (EPRI). EPRI facilitated DOE receipt of harvested cables from the decommissioned Crystal River Unit 3 (CR3) pressurized water reactor representing six of the nine most common low voltage cable manufacturers (EPRI 103841R1): Rockbestos, Anaconda Wire and Cable Company (Anaconda), Boston Insulated Wire (BIW), Brand-Rex, Kerite and Okonite. Cable samples received had been installed in the operating plant for durations ranging from 10 years to 36 years. These cables provide the

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

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

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

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)

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

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

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