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Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Extended outages at several nuclear plants led to high outage ...  

U.S. Energy Information Administration (EIA)

Outages at U.S. nuclear power plants so far in 2012 are generally higher than in recent years because of extended forced outages at four nuclear power plants.

2

Extended outages at several nuclear plants led to high outage ...  

U.S. Energy Information Administration (EIA)

Southern California Edison's San Onofre Nuclear ... and Progress's handling of the Crystal River repairs became an issue in the company's recent merger with ...

3

Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities  

Science Conference Proceedings (OSTI)

The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980’s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work tasks, may have a failure rate of 1.0E-3 or higher (Gertman, 1996). With between 10,000 and 45,000 subtasks being performed during an outage (Gomes, 1996), the opportunity for human error of some consequence is a realistic concern. Although a number of factors exist that can make these errors recoverable, reducing and effectively coordinating the sheer number of tasks to be performed, particularly those that are error prone, has the potential to enhance outage efficiency and safety. Additionally, outage management requires precise coordination of work groups that do not always share similar objectives. Outage managers are concerned with schedule and cost, union workers are concerned with performing work that is commensurate with their trade, and support functions (safety, quality assurance, and radiological controls, etc.) are concerned with performing the work within the plants controls and procedures. Approaches to outage management should be designed to increase the active participation of work groups and managers in making decisions that closed the gap between competing objectives and the potential for error and process inefficiency.

Gregory Weatherby

2012-05-01T23:59:59.000Z

4

A Study of Outage Management Practices at Selected U.S. Nuclear Plants  

SciTech Connect

This paper presents insights gained from a study of the outage management practices at a number of U.S. nuclear plants. The objective of the study was to conduct an in-depth review of the current practices of outage management at these selected plants and identify important factors that have contributed to the recent success of their outage performance. Two BWR-4, three BWR-6, and two 3-loop Westinghouse PWR plants were selected for this survey. The results of this study can be used to formulate outage improvement efforts for nuclear plants in other countries. (author)

Lin, James C. [ABSG Consulting Inc., Irvine, CA (United States)

2002-07-01T23:59:59.000Z

5

Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant  

SciTech Connect

The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

Meijing Wu; Guozhang Shen [Qinshan Nuclear power company (China)

2006-07-01T23:59:59.000Z

6

Sensitivity analysis for the outages of nuclear power plants  

E-Print Network (OSTI)

Feb 17, 2012 ... Abstract: Nuclear power plants must be regularly shut down in order to perform refueling and maintenance operations. The scheduling of the ...

7

Automatic Scheduling of Outages of Nuclear Power Plants with Time Windows  

E-Print Network (OSTI)

We report on a successful project for transference of advanced AI technology into the domain of planning of outages of nuclear power plants as part of DOD's dual-use program. ROMAN (Rome Lab Outage Manager) is the prototype system that was developed as a result of this project. ROMAN's main innovation compared to the current state of the art of outage management tools is its capability to automatically enforce safety constraints during the planning and scheduling phase. Another innovative aspect of ROMAN is the generation of more robust schedules that are feasible over time windows. In other words, ROMAN generates a family of schedules by assigning time intervals as start times to activities rather than single point start times, without afecting the overall duration of the project. ROMAN uses a constraint satisfaction paradigm combining a global search tactic with constraint propagation. The derivation of very specialized representations for the constraints to perform efficient propaga...

Carla P. Gomes

1996-01-01T23:59:59.000Z

8

Extended nuclear plant outages raise Southern California wholesale ...  

U.S. Energy Information Administration (EIA)

Tools; Glossary › All Reports ... weather; gasoline; capacity; exports; nuclear; forecast; View All Tags ...

9

Sensitivity analysis for the outages of nuclear power plants  

E-Print Network (OSTI)

Feb 17, 2012 ... voirs, fossil energy (coal, gas), atom (nuclear fission process) and to a small .... The dynamic of the stocks of fuel is clear from the differential ...

10

Nuclear power plants undergo seasonal scheduled outages - Today in ...  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors, generation, spent fuel. Total Energy. ... Privacy/Security Copyright & Reuse Accessibility. Related Sites U.S. Department of Energy

11

Key Issues for the control of refueling outage duration and costs in PWR Nuclear Power Plants  

SciTech Connect

For several years, EDF, within the framework of the CIDEM1 project and in collaboration with some German Utilities, has undertaken a detailed review of the operating experience both of its own NPP and of foreign units, in order to improve the performances of future units under design, particularly the French-German European Pressurized Reactor (EPR) project. This review made it possible to identify the key issues allowing to decrease the duration of refueling and maintenance outages. These key issues can be classified in 3 categories Design, Maintenance and Logistic Support, Outage Management. Most of the key issues in the design field and some in the logistic support field have been studied and could be integrated into the design of any future PWR unit, as for the EPR project. Some of them could also be adapted to current plants, provided they are feasible and profitable. The organization must be tailored to each country, utility or period: it widely depends on the power production environment, particularly in a deregulation context. (author)

Degrave, Claude [Electricite de France, EDF-SEPTEN, 12-14 avenue Dutrievoz 69628 Villeurbanne Cedex (France)

2002-07-01T23:59:59.000Z

12

Plant maintenance and outage management issue, 2005  

SciTech Connect

The focus of the January-February issue is on plant maintenance and outage managment. Major articles/reports in this issue include: Dawn of a new era, by Joe Colvin, Nuclear Energy Institute (NEI); Plant profile: Beloyarsk NPP, Russia, by Nikolai Oshkanov, Beloyarsk NPP, Russia; Improving economic performance, by R. Spiegelberg-Planner, John De Mella, and Marius Condu, IAEA; A model for improving performance, by Pet Karns, MRO Software; ASME codes and standards, by Shannon Burke, ASME International; and, Refurbishment programs, by Craig S. Irish, Nuclear Logistics, Inc.

Agnihotri, Newal (ed.)

2005-01-15T23:59:59.000Z

13

New tensioning equipment saves critical path time in nuclear outage  

SciTech Connect

This article examines the selection and application of new tensioning equipment for TVA`s Browns Ferry Nuclear Plant. The new device would reduce refueling outage time and radiation exposure, and require fewer personnel to operate. Results of the equipment performance during the refueling outage and problems encountered and resolved are described.

NONE

1995-10-01T23:59:59.000Z

14

Nuclear power plant outages above seasonal norm in spring of 2011 ...  

U.S. Energy Information Administration (EIA)

Like most electric generators, nuclear reactor operators typically schedule maintenance in the spring and the fall to help ensure that the reactors are available to ...

15

Outage Milestone Manual for Fossil-Fueled Power Plants  

Science Conference Proceedings (OSTI)

The efficiency of an outage program and the correctness of the outage process are important to the continuous improvement and long-term success of a utility and plant. This report--based on collective industry experience; Electric Power Research Institute (EPRI) publications; and outage conference, meeting, and workshop data--provides guidance for utility and plant management and staff involved in outage planning, execution, and post-outage operations and in restarting the planning cycle in preparation f...

2010-10-19T23:59:59.000Z

16

Outage Management Guidelines for Fossil- Fueled Power Plants  

Science Conference Proceedings (OSTI)

The efficiency of an outage program and the correctness of the outage process are important to the continuous improvement and the long-term success of a utility and plant. This report, based on collective industry experience, Electric Power Research Institute (EPRI) publications, and outage conference, meeting, and workshop data, provides guidance for utility/plant management and staff involved in outage planning, execution, and post-outage operations and in restarting the planning cycle in preparation f...

2006-12-22T23:59:59.000Z

17

Outage Management Benchmarking Guideline  

Science Conference Proceedings (OSTI)

Benchmarking of power plant outages will help plants target performance improvements to specific elements of a plant outage program in order to improve overall availability, reliability, and safety while decreasing generation costs. EPRI's "Outage Management Benchmarking Guideline" builds on the Institute's fossil and nuclear plant experience with routine maintenance and extends that to outage maintenance processes. The guideline describes the initial steps in an outage benchmarking effort and 13 key ele...

2003-03-26T23:59:59.000Z

18

Nuclear outages back within typical range since July following ...  

U.S. Energy Information Administration (EIA)

U.S. nuclear generator outages were above the levels of the previous four years in the second quarter of 2011 but have returned to more typical ...

19

Improving Outage Performance: Outage Optimization Process  

SciTech Connect

Planned outage performance is a key measure of how well an Nuclear Power Plant (NPP) is operated. Performance during planned outages strongly affects virtually all of a plant's performance metrics. In recognition of this fact, NPP operators worldwide have and continue to focus on improving their outage performance. The process of improving outage performance is commonly referred to as 'Outage Optimization' in the industry. This paper starts with a summary of the principles of Outage Optimization. It then provides an overview of a process in common use in the USA and elsewhere to manage the improvement of planned outages. The program described is comprehensive in that it involves managing improvement in both the Preparation and Execution phases of outage management. (author)

LaPlatney, Jere J. [AREVA NP (United States)

2006-07-01T23:59:59.000Z

20

Nuclear Maintenance Applications Center: Effective Refueling Outage Preparation and Execution Guidance--Revision to 1014480  

Science Conference Proceedings (OSTI)

This report provides updated, current guidance to assist outage managers and teams during preparation and execution phases of a nuclear refueling outage. Included is guidance on how the outage activities support long-range and strategic plans developed by the site or fleet of units.

2011-12-13T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Notice of Unplanned Outage at the Mirant Potomac River Plant | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Unplanned Outage at the Mirant Potomac River Plant Unplanned Outage at the Mirant Potomac River Plant Notice of Unplanned Outage at the Mirant Potomac River Plant Docket No. EO-05-01. Order No. 202-05-03: Pursuant to the United States Department of Energy ("DOE") Order No_ 202-05-3, issued December 20, 2005 ("DOE Potomac River Order"), Pepco hereby files this notice of an unplanned outage of one of the 230kV circuits serving the Potomac River Substation, and through that station, the District of Columbia. Notice of Unplanned Outage at the Mirant Potomac River Plant More Documents & Publications Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac Electric Power Company (PEPCO) Concerning Planned Outages of the 230 kV circuits Further Notice of 230kV Circuit Planned Outages

22

Fossil Power Plant Outage Scoping and Scope Control  

Science Conference Proceedings (OSTI)

This document provides detailed guidance for outage scope planning and control. It covers such topics as long-range business asset management tracking and inclusion into outage scope and contingency planning. It provides guidance on developing the outage plan, including typical criteria for the baseline budget, developing and using a monitoring plan and metrics, and developing an assessment plan for outage scope development and execution. The scope identification and approval processes are discussed as w...

2007-12-19T23:59:59.000Z

23

Synthesis of power plant outage schedules. Final technical report, April 1995-January 1996  

SciTech Connect

This document provides a report on the creation of domain theories in the power plant outage domain. These were developed in conjunction with the creation of a demonstration system of advanced scheduling technology for the outage problem. In 1994 personnel from Rome Laboratory (RL), Kaman Science (KS), Kestrel Institute, and the Electric Power Research Institute (EPRI) began a joint project to develop scheduling tools for power plant outage activities. This report describes our support for this joint effort. The project uses KIDS (Kestrel Interactive Development System) to generate schedulers from formal specifications of the power plant domain outage activities.

Smith, D.R.

1997-07-01T23:59:59.000Z

24

Nuclear outages begin to increase with the start of the ...  

U.S. Energy Information Administration (EIA)

Short-Term Energy Outlook ... Search EIA.gov. A-Z Index; ... several units began to reduce their output to enter into refueling outages, ...

25

Unit-Contingent Power Purchase Agreement and Asymmetric Information About Plant Outage  

Science Conference Proceedings (OSTI)

This paper analyzes a unit-contingent power purchase agreement between an electricity distributor and a power plant. Under such a contract the distributor pays the plant a fixed price if the plant is operational and nothing if plant outage occurs. Pricing ... Keywords: electricity industry, risk allocation, spot market, unit-contingent contract

Owen Q. Wu; Volodymyr Babich

2012-04-01T23:59:59.000Z

26

Extended nuclear plant outages raise Southern California ...  

U.S. Energy Information Administration (EIA)

Although SoCal Citygate spot natural gas prices have increased slightly ... higher wholesale power prices in Southern California more likely are attributable to ...

27

Outage Effectiveness Measurement Methodology  

Science Conference Proceedings (OSTI)

The efficiency of an outage program and the correctness of the outage process are important to the continuous improvement and long-term success of the plant. This report, based on a collective of industry experience, EPRI publications, and power conference data, is an aid to utility and plant management and staff to understanding the outage effectiveness methods and metrics relative to outage planning, execution, and post-outage operations.

2004-12-15T23:59:59.000Z

28

Outage Log  

NLE Websites -- All DOE Office Websites (Extended Search)

For Users Live Status Global Queue Look Scheduled Outages Outage Log Edison Login Node Status Hopper Login Node Status Hopper User Environment Monitoring Carver Login Node Status...

29

Application of Standard Maintenance Windows in PHWR Outage  

SciTech Connect

The concept of Standard Maintenance Windows has been widely used in the planned outage of light water reactor in the world. However, due to the specific feature of Pressurized Heavy Water Reactor (PHWR), it has not come to a consensus for the PHWR owners to adopt Standard Maintenance Windows for planned outage aiming at the optimization of outage duration. Third Qinshan Nuclear Power Company (TQNPC), with their experience gained in the previous outages and with reference to other PHWR power plants, has identified a set of Standard Maintenance Windows for planned outage. It can be applied to similar PHWR plants and with a few windows that are specific to Qinshan Phase III NPP. The use of these Standard Maintenance Windows in planned outage has been proved to be effective in control shutdown nuclear safety, minimize the unavailability of safety system, improve the efficient utilization of outage duration, and improved the flexibility of outage schedule in the case of emergency issue, which forced the revision of outage schedule. It has also formed a solid foundation for benchmarking. The identification of Standard Maintenance Windows and its application will be discussed with relevant cases for the common improvement of outage duration. (author)

Fuming Jiang [Third Qinshan Nuclear Power Company, Ltd. (China)

2006-07-01T23:59:59.000Z

30

Outage Closeout and Unit Restart Guidelines for Fossil-Fueled Power Plants  

Science Conference Proceedings (OSTI)

Outage closeout planning and execution and successful restart are as important as the efforts going into an outage. Detailed planning and execution are required to ensure that schedules are met, tests are completed in a timely fashion, training is completed, and that lessons learned are captured for use in future outages, both planned and forced. Effective closure and restart activities result in a smoother return to service and more reliable operation. This project is based upon collective industry expe...

2008-12-22T23:59:59.000Z

31

Experience Based Interview Process for Power Plant Management: With a Pilot Application to Aging of Outage Support Equipment  

Science Conference Proceedings (OSTI)

Plant managers are responsible for ensuring that their facilities meet strategic asset management goals in an increasingly competitive power generation marketplace. This report describes an experience based interview (EBI) method for capturing the knowledge of plant staff to more efficiently identify technical or operational issues and make management decisions that protect assets. Included is a demonstration of the method in a pilot application to aging of support equipment that could impact outages in ...

1999-04-05T23:59:59.000Z

32

Plant Outage Time Savings Provided by Subcritical Physics Testing at Vogtle Unit 2  

SciTech Connect

The most recent core reload design verification physics testing done at Southern Nuclear Company's (SNC) Vogtle Unit 2, performed prior to initial power operations in operating cycle 12, was successfully completed while the reactor was at least 1% {delta}K/K subcritical. The testing program used was the first application of the Subcritical Physics Testing (SPT) program developed by the Westinghouse Electric Company LLC. The SPT program centers on the application of the Westinghouse Subcritical Rod Worth Measurement (SRWM) methodology that was developed in cooperation with the Vogtle Reactor Engineering staff. The SRWM methodology received U. S. Nuclear Regulatory Commission (NRC) approval in August of 2005. The first application of the SPT program occurred at Vogtle Unit 2 in October of 2005. The results of the core design verification measurements obtained during the SPT program demonstrated excellent agreement with prediction, demonstrating that the predicted core characteristics were in excellent agreement with the actual operating characteristics of the core. This paper presents an overview of the SPT Program used at Vogtle Unit 2 during operating cycle 12, and a discussion of the critical path outage time savings the SPT program is capable of providing. (authors)

Cupp, Philip [Southern Nuclear Company (United States); Heibel, M.D. [Westinghouse Electric Company, LLC (United States)

2006-07-01T23:59:59.000Z

33

Development of Methodologies for Technology Deployment for Advanced Outage Control Centers that Improve Outage Coordination, Problem Resolution and Outage Risk Management  

SciTech Connect

This research effort is a part of the Light-Water Reactor Sustainability (LWRS) Program, which is a research and development (R&D) program sponsored by Department of Energy (DOE) and performed in close collaboration with industry R&D programs that provides the technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants. The LWRS program serves to help the U.S. nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The long term viability of existing nuclear power plants in the U.S. will depend upon maintaining high capacity factors, avoiding nuclear safety issues and reducing operating costs. The slow progress in the construction on new nuclear power plants has placed in increased importance on maintaining the output of the current fleet of nuclear power plants. Recently expanded natural gas production has placed increased economic pressure on nuclear power plants due to lower cost competition. Until recently, power uprate projects had steadily increased the total output of the U.S. nuclear fleet. Errors made during power plant upgrade projects have now removed three nuclear power plants from the U.S. fleet and economic considerations have caused the permanent shutdown of a fourth plant. Additionally, several utilities have cancelled power uprate projects citing economic concerns. For the past several years net electrical generation from U.S. nuclear power plants has been declining. One of few remaining areas where significant improvements in plant capacity factors can be made is in minimizing the duration of refueling outages. Managing nuclear power plant outages is a complex and difficult task. Due to the large number of complex tasks and the uncertainty that accompanies them, outage durations routinely exceed the planned duration. The ability to complete an outage on or near schedule depends upon the performance of the outage management organization. During an outage, the outage control center (OCC) is the temporary command center for outage managers and provides several critical functions for the successful execution of the outage schedule. Essentially, the OCC functions to facilitate information inflow, assist outage management in processing information and to facilitate the dissemination of information to stakeholders. Currently, outage management activities primarily rely on telephone communication, face to face reports of status and periodic briefings in the OCC. Much of the information displayed in OCCs is static and out of date requiring an evaluation to determine if it is still valid. Several advanced communication and collaboration technologies have shown promise for facilitating the information flow into, across and out of the OCC. Additionally, advances in the areas of mobile worker technologies, computer based procedures and electronic work packages can be leveraged to improve the availability of real time status to outage managers.

Shawn St. Germain; Ronald Farris; Heather Medeman

2013-09-01T23:59:59.000Z

34

Study, outlines why outages go long, short, or on-time  

SciTech Connect

A recent report by a nuclear industry professional, based on a survey of outage managers at US nuclear power plants, declares that [open quotes]preplanned outage schedules appear to be grossly inaccurate, and the outage management planners and schedulers do not have a grasp of the requirements and/or the resources needed to complete the actual activities on schedule.[close quotes] It declares that [open quotes]the scheduled duration of a planned outage must be realistic.[close quotes] The study identifies personnel, planning and scheduling, and equipment/hardware as [open quotes]the primary reasons why refueling outages and outage activities finished ahead of, right on, or behind schedule.[close quotes

Not Available

1993-09-01T23:59:59.000Z

35

Outage dose reduction achievements during shorter refueling outages  

SciTech Connect

Achievement of dose reduction goals has been demonstrated at the Limerick Generating Station during the past three refueling outages in 1995-96. Shorter refueling outages were accomplished by carefully selecting outage work and thoroughly planning the work. Limerick Unit 1 completed its outage in 35 d; Unit 2 in 23 d in 1995; Unit 1 completed its outage in 24 d in 1996. The four previous outages at Unit I had taken from 100 to 127 days. European plants were visited by plant supervisors to develop improved management approaches to optimizing outage performance from work planning to work implement. Cofrentes in Spain and KKL Leibstadt in Switzerland were visited in 1994 because of their similar design and outage durations consistently below 35 d. This paper describes the radiation protection practices observed at European plants and implemented at Limerick to achieve efficiency of work practices and adequacy of radiological controls. Specific radiation protection initiatives discussed include electronic dosimetry system, break areas, wash sinks, scrub suits, zone mapping and self-monitoring. Outage achievements in 1995 and 1996 has assured Limerick continued BWR industry leadership as the lowest annual person-rem BWRs in the U.S..

Harris, W.O.; Taylor, S. [Limerick Generating Station, Sanatoga, PA (United States)

1996-06-01T23:59:59.000Z

36

Outage management and health physics issue, 2009  

SciTech Connect

The focus of the May-June issue is on outage management and health physics. Major articles include the following: Planning and scheduling to minimize refueling outage, by Pat McKenna, AmerenUE; Prioritizing safety, quality and schedule, by Tom Sharkey, Dominion; Benchmarking to high standards, by Margie Jepson, Energy Nuclear; Benchmarking against U.S. standards, by Magnox North, United Kingdom; Enabling suppliers for new build activity, by Marcus Harrington, GE Hitachi Nuclear Energy; Identifying, cultivating and qualifying suppliers, by Thomas E. Silva, AREVA NP; Creating new U.S. jobs, by Francois Martineau, Areva NP. Industry innovation articles include: MSL Acoustic source load reduction, by Amir Shahkarami, Exelon Nuclear; Dual Methodology NDE of CRDM nozzles, by Michael Stark, Dominion Nuclear; and Electronic circuit board testing, by James Amundsen, FirstEnergy Nuclear Operating Company. The plant profile article is titled The future is now, by Julia Milstead, Progress Energy Service Company, LLC.

Agnihotri, Newal (ed.)

2009-05-15T23:59:59.000Z

37

Outage management and health physics issue, 2006  

SciTech Connect

The focus of the May-June issue is on outage management and health physics. Major articles/reports in this issue include: A design with experience for the U.S., by Michael J. Wallace, Constellation Generation Group; Hope to be among the first, by Randy Hutchinson, Entergy Nuclear; Plans to file COLs in 2008, by Garry Miller, Progress Energy; Evolution of ICRP's recommendations, by Lars-Erik Holm, ICRP; European network on education and training in radiological protection, by Michele Coeck, SCK-CEN, Belgium; Outage managment: an important tool for improving nuclear power plant performance, by Thomas Mazour and Jiri Mandula, IAEA, Austria; and Plant profile: Exploring new paths to excellence, by Anne Thomas, Exelon Nuclear.

Agnihotri, Newal (ed.)

2006-05-15T23:59:59.000Z

38

Technology Integration Initiative In Support of Outage Management  

SciTech Connect

Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Often, command and control during outages is maintained in the outage control center where many of the underlying technologies supporting outage control are the same as those used in the 1980’s. This research reports on the use of advanced integrating software technologies and hand held mobile devices as a means by which to reduce cycle time, improve accuracy, and enhance transparency among outage team members. This paper reports on the first phase of research supported by the DOE Light Water Reactor Sustainability (LWRS) Program that is performed in close collaboration with industry to examine the introduction of newly available technology allowing for safe and efficient outage performance. It is thought that this research will result in: improved resource management among various plant stakeholder groups, reduced paper work, and enhanced overall situation awareness for the outage control center management team. A description of field data collection methods, including personnel interview data, success factors, end-user evaluation and integration of hand held devices in achieving an integrated design are also evaluated. Finally, the necessity of obtaining operations cooperation support in field studies and technology evaluation is acknowledged.

Gregory Weatherby; David Gertman

2012-07-01T23:59:59.000Z

39

NUCLEAR PLANT OPERATIONS AND  

E-Print Network (OSTI)

reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed--has been benchmarked against measurements.30 At the Ringhals nuclear power plant, this measurement is car a measurement performed at the PWR Unit 4 of the Ring hals Nuclear Power Plant was available to us

Demazière, Christophe

40

NUCLEAR PLANT OPERATIONS AND  

E-Print Network (OSTI)

reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed reactivity effects--has been benchmarked against measurements.30 At the Ringhals nuclear power plant a measurement performed at the PWR Unit 4 of the Ring- hals Nuclear Power Plant was available to us

Demazière, Christophe

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Loss of benefits resulting from mandated nuclear plant shutdowns  

SciTech Connect

This paper identifies and discusses some of the important consequences of nuclear power plant unavailability, and quantifies a number of technical measures of loss of benefits that result from regulatory actions such as licensing delays and mandated nuclear plant outages. The loss of benefits that accompany such regulatory actions include increased costs of systems generation, increased demand for nonnuclear and often scarce fuels, and reduced system reliability. This paper is based on a series of case studies, supplemented by sensitivity studies, on hypothetical nuclear plant shutdowns. These studies were developed by Argonne in cooperation with four electric utilities.

Peerenboom, J.P.; Buehring, W.A.

1982-01-01T23:59:59.000Z

42

NUCLEAR PLANT OPERATIONS AND  

E-Print Network (OSTI)

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: neutron flux, cur- rent noise, vibration diagnostics: Swedish Nuclear Power Inspectorate SE- 10658 Stockholm, Sweden. NUCLEAR TECHNOLOGY VOL. 131 AUG. 2000 239 by the Swedish Nuclear Power Inspectorate, contract 14.5-980942-98242. REFERENCES 1. A. M. WEINBERG and H. C

Pázsit, Imre

43

Use of expert systems in nuclear power plants  

SciTech Connect

The application of technologies, particularly expert systems, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, there are a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) in which expert systems can increase the efficiency and effectiveness of overall plant and corporate operations. This document presents a number of potential applications of expert systems in the nuclear power field. 36 refs., 2 tabs.

Uhrig, R.E.

1989-01-01T23:59:59.000Z

44

Above-normal outages of U.S. nuclear capacity persist at the start ...  

U.S. Energy Information Administration (EIA)

Southern California Edison's San Onofre Nuclear Generating ... Progress's handling of Crystal River repairs became an issue in the company's recent merger with Duke ...

45

Above-normal outages of U.S. nuclear capacity persist at the start ...  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors, generation, spent fuel. Total Energy. ... Privacy/Security Copyright & Reuse Accessibility. Related Sites U.S. Department of Energy

46

U.S. nuclear outages back within five-year range - Today in Energy ...  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors, generation, spent fuel. Total Energy. ... Privacy/Security Copyright & Reuse Accessibility. Related Sites U.S. Department of Energy

47

Georgia Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

48

Arkansas Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

49

Iowa Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Iowa nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

50

Ohio Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Ohio nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

51

Vermont Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

52

Florida Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Florida nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

53

Virginia Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

54

Missouri Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

55

Nebraska Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Nebraska nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

56

Tennessee Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Tennessee nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

57

Minnesota Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Minnesota nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

58

Arizona Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

59

Massachusetts Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

60

Kansas Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Kansas nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Alabama Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

62

Wisconsin Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Wisconsin nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

63

Texas Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

64

Michigan Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

65

Above-normal outages of U.S. nuclear capacity persist at the start ...  

U.S. Energy Information Administration (EIA)

... have both been offline since January 2012 as a precaution after a steam generator tube leak led to the discovery of excessive wear in the plant's new steam ...

66

Plant Engineering: Performance Diagnostic Test Program for the Nuclear Turbine Cycle at Korea Hydro & Nuclear Power Company  

Science Conference Proceedings (OSTI)

Currently, many power generating companies are challenged to reduce operating costs, and at the same time, the cost of unit unavailability can be significant in today's power markets. In the past decade, management of nuclear power plants, including Korea Hydro & Nuclear Power (KHNP), has been focused on reducing forced outage rates and nuclear-safety-related issues, with less attention paid to thermal performance. But recently, KHNP has been strongly challenged to increase unit thermal performance, as f...

2012-02-28T23:59:59.000Z

67

NUCLEAR POWER PLANT  

DOE Patents (OSTI)

A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

1963-05-14T23:59:59.000Z

68

Tracking Laser Coordinate Measurement System Application for Turbine Outage Activities  

Science Conference Proceedings (OSTI)

Tracking Laser Coordinate Measurement System Application for Turbine Outage Activities provides nuclear and fossil personnel with a faster and more accurate method for performing turbine measurement activities during an outage.

2007-12-21T23:59:59.000Z

69

Maryland Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

of State nuclear net generation (percent)","Owner" "Calvert Cliffs Nuclear Power Plant Unit 1, Unit 2","1,705","13,994",100.0,"Calvert Cliffs Nuclear PP Inc" "1 Plant 2...

70

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 5: Analysis of core damage frequency from seismic events for plant operational state 5 during a refueling outage  

SciTech Connect

In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Sandia National Laboratories studying a boiling water reactor (Grand Gulf), and the other at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1). Both the Sandia and Brookhaven projects have examined only accidents initiated by internal plant faults---so-called ``internal initiators.`` This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling outage conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Grand Gulf. All of the many systems modeling assumptions, component non-seismic failure rates, and human effort rates that were used in the internal-initiator study at Grand Gulf have been adopted here, so that the results of the study can be as comparable as possible. Both the Sandia study and this study examine only one shutdown plant operating state (POS) at Grand Gulf, namely POS 5 representing cold shutdown during a refueling outage. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POS 5. The results of the analysis are that the core-damage frequency for earthquake-initiated accidents during refueling outages in POS 5 is found to be quite low in absolute terms, less than 10{sup {minus}7}/year.

Budnitz, R.J. [Future Resources Associates, Inc., Berkeley, CA (United States); Davis, P.R. [PRD Consulting (United States); Ravindra, M.K.; Tong, W.H. [EQE International, Inc., Irvine, CA (United States)

1994-08-01T23:59:59.000Z

71

Nuclear Plant Decommissioning  

Science Conference Proceedings (OSTI)

In the 1990s several nuclear utilities proceeded with full decommissioning of their nuclear power plants based on perceived economics. This major shift to immediate decommissioning presented a significant challenge to the industry in terms of the development of a decommissioning process and a comprehensive updated regulatory framework. EPRI responded by undertaking the formation of the Decommissioning Support Program. The initial work involved conducting a series of topical workshops directed to specific...

2010-11-24T23:59:59.000Z

72

Washington Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Washington nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

73

Connecticut Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Connecticut nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

74

California Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

California nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

75

Mississippi Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Mississippi nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

76

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

OUTAGES COMPONENT NUCLEAR REACTOR General Primary CoolingAsh Disposal Trouble NUCLEAR REACTOR COMPONENT OUTAGE CAUSESconsisting of a Nuclear units use a reactor in which burner

Nero, A.V.

2010-01-01T23:59:59.000Z

77

Louisiana Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Louisiana nuclear power plants, summer capacity and net generation, 2010" "Plant NameTotal Reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

78

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

79

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

80

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Main report and appendices, Volume 6, Part 1  

SciTech Connect

Traditionally, probabilistic risk assessments (PRAS) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Recent studies and operational experience have, however, implied that accidents during low power and shutdown could be significant contributors to risk. In response to this concern, in 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The program consists of two parallel projects being performed by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). The program objectives include assessing the risks of severe accidents initiated during plant operational states other than full power operation and comparing the estimated risks with the risk associated with accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program is that of a Level-3 PRA. The subject of this report is the PRA of the Grand Gulf Nuclear Station, Unit 1. The Grand Gulf plant utilizes a 3833 MWt BUR-6 boiling water reactor housed in a Mark III containment. The Grand Gulf plant is located near Port Gibson, Mississippi. The regime of shutdown analyzed in this study was plant operational state (POS) 5 during a refueling outage, which is approximately Cold Shutdown as defined by Grand Gulf Technical Specifications. The entire PRA of POS 5 is documented in a multi-volume NUREG report (NUREG/CR-6143). The internal events accident sequence analysis (Level 1) is documented in Volume 2. The Level 1 internal fire and internal flood analyses are documented in Vols 3 and 4, respectively.

Brown, T.D.; Kmetyk, L.N.; Whitehead, D.; Miller, L. [Sandia National Labs., Albuquerque, NM (United States); Forester, J. [Science Applications International Corp., Albuquerque, NM (United States); Johnson, J. [GRAM, Inc., Albuquerque, NM (United States)

1995-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Illinois Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Illinois nuclear power plants, summer capacity and net generation, 2010" Illinois nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Braidwood Generation Station Unit 1, Unit 2","2,330","19,200",20.0,"Exelon Nuclear" "Byron Generating Station Unit 1, Unit 2","2,300","19,856",20.6,"Exelon Nuclear" "Clinton Power Station Unit 1","1,065","8,612",9.0,"Exelon Nuclear" "Dresden Generating Station Unit 2, Unit 3","1,734","14,593",15.2,"Exelon Nuclear" "LaSalle Generating Station

82

Nuclear power plant design analysis  

SciTech Connect

Information concerning the engineering aspects of the design of commercial nuclear power plants is presented. Topics discussed include: electric utility economics; nuclear plant cconomics; thermal-transport systems and core design; nuclear analysis methods; safcty requirements; fuel-system analysis; dcsign considerations; and optimization approaches. (DCC)

Sesonske, A.

1973-01-01T23:59:59.000Z

83

Maintain HCUs on-line, shorten refueling outages  

SciTech Connect

This article examines how removing maintenance of hydraulic control units from the outage scope lets the outage focus available resources on critical-path items, saving significant time and money and enhancing capacity factors. Because of their cost impact, refueling outages are a prime focus of efforts to improve the competitive operation of nuclear powerplants. An approach drawing wide interest is reducing the outage work scope by performing on-line key tasks normally consigned to refueling outages. applying this approach to maintenance of hydraulic control units (HCUs) on boiling-water reactors (BWRs) can be extremely fruitful.

Bell, T.

1996-09-01T23:59:59.000Z

84

US nuclear power plant operating cost and experience summaries  

Science Conference Proceedings (OSTI)

NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov).

Kohn, W.E.; Reid, R.L.; White, V.S.

1998-02-01T23:59:59.000Z

85

Video Camera Use at Nuclear Power Plants: Tools for Increasing Productivity and Reducing Radiation Exposure: Tools for Increasing Pr oductivity and Reducing Radiation Exposure  

Science Conference Proceedings (OSTI)

Nuclear power plants have increased the use of industrial video cameras as support tools for a variety of plant operations and outage tasks. This survey on utility use of video cameras, the equipment being used, and the benefits derived found that the video camera is an important tool for reducing radiation exposure and improving productivity through more efficient use of personnel.

1990-08-14T23:59:59.000Z

86

Outage management and health physics issue, 2007  

SciTech Connect

The focus of the May-June issue is on outage management and health physics. Major articles/reports in this issue include: India: a potential commercial opportunity, a U.S. Department of Commerce Report, by Joe Neuhoff and Justin Rathke; The changing climate for nuclear energy, by Skip Bowman, Nuclear Energy Insitute; Selecting protective clothing, by J. Mark Price, Southern California Edison; and Succssful refurbishment outage, by Sudesh K. Gambhir, Omaha Public Power District. Industry innovation articles in this issue are: Containment radiation monitoring spiking, by Michael W. Lantz and Robert Routolo, Arizona Public Service Company; Improved outage performance, by Michael Powell and Troy Wilfong, Arizona Public Service Company, Palo Verde Nuclear Generating Station; Stop repacking valves and achieve leak-free performance, by Kenneth Hart, PPL Susquehanna LLC; and Head assembly upgrade package, by Timothy Petit, Dominion Nuclear.

Agnihotri, Newal (ed.)

2007-05-15T23:59:59.000Z

87

Owners of nuclear power plants  

Science Conference Proceedings (OSTI)

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

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

1996-11-01T23:59:59.000Z

88

Pennsylvania Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Pennsylvania nuclear power plants, summer capacity and net generation, 2010" Pennsylvania nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Beaver Valley Unit 1, Unit 2","1,777","14,994",19.3,"FirstEnergy Nuclear Operating Company" "Limerick Unit 1, Unit 2","2,264","18,926",24.3,"Exelon Nuclear" "PPL Susquehanna Unit 1, Unit 2","2,450","18,516",23.8,"PPL Susquehanna LLC" "Peach Bottom Unit 2, Unit 3","2,244","18,759",24.1,"Exelon Nuclear" "Three Mile Island Unit 1",805,"6,634",8.5,"Exelon Nuclear"

89

Naval Nuclear Propulsion Plants | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Naval Nuclear Propulsion Plants In naval nuclear propulsion plants, fissioning of uranium atoms in the reactor core produces heat. Because the fission process also produces...

90

Guidelines for inservice testing at nuclear power plants  

Science Conference Proceedings (OSTI)

The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

Campbell, P.

1995-04-01T23:59:59.000Z

91

North Carolina Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

92

New Hampshire Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (nw)","Net generation (thousand mwh)","Share of State nuclear net...

93

New Jersey Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

94

Connecticut Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2ct Millstone Unit 2, Unit 3 2,103 16,750 100.0 Dominion Nuclear Conn Inc 1 Plant 2 Reactors Owner Note: Totals may not equal sum of components due to independent ...

95

Arkansas Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2ar Arkansas Nuclear One Unit 1, Unit 2 1,835 15,023 100.0 Entergy Arkansas Inc 1 Plant 2 Reactors Owner Note: Totals may not equal sum of ...

96

Outage managment and health physics issue, 2008  

SciTech Connect

The focus of the May-June issue is on outage management and health physics. Major articles include: Outage optimization initiatives, by George B. Beam, AREVA NP, Inc.; New plant based on excellent track records, by Jim Scarola, Progress Energy; Meeting customer needs and providing environmental benefits, by Peter S. Hastings, Duke Energy; Plants with 3-D design, by Jack A. Bailey, Tennessee Valley Authority; and Highest quality with exceptional planning, by Jason A. Walls, Duke Energy. Industry innovation articles include: Integrated exposure reduction plan, by Ed Wolfe, Exelon; Performance-based radiation worker training, by Joe Giuffre and Timothy Vriezerma, American Electric Power.

Agnihotri, Newal (ed.)

2008-05-15T23:59:59.000Z

97

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

U.S. Energy Information Administration (EIA)

snpt3wi4046 506 3,954 89.2 PWR 512 4,336 96.7 1,018 8,291 93.0 Point Beach Nuclear Plant Unit Type Data for 2010 PWR = Pressurized Light Water Reactor. Note: Totals ...

98

Transmission outage data collection for multiple related outage events  

SciTech Connect

This paper focuses on the information required to provide a basis for the analysis of forced multiple outage events. It recaps research as well as the bulk transmission outage collection up-rate that was performed. This paper identifies trends and addresses their impact on bulk transmission outage data collection.

Lauby, M.G. (Electric Power Research Inst., Palo Alto, CA (USA)); Maillant, G.R. (Electricite de France (EDF)

1989-01-01T23:59:59.000Z

99

ALARA at nuclear power plants  

SciTech Connect

Implementation of the As Low As Reasonably Achievable (ALARA) principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed though a variety of dose reduction techniques. It is planned that this report will include material on historical aspects, management, valuation of dose reduction, quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report. 30 refs., 1 fig., 6 tabs.

Baum, J.W.

1990-01-01T23:59:59.000Z

100

U.S. Nuclear Power Plant Operating Cost and Experience Summaries  

Science Conference Proceedings (OSTI)

The ''U.S. Nuclear Power Plant Operating Cost and Experience Summaries'' (NUREG/CR-6577, Supp. 2) report has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants during 2000-2001. Costs incurred after initial construction are characterized as annual production costs, which represent fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications, which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operations summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from operating reports submitted by the licensees, the Nuclear Regulatory Commission (NRC) database for enforcement actions, and outage reports.

Reid, RL

2003-09-18T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Nuclear Maintenance Applications Center: Nuclear Fuel Handling Equipment Application and Maintenance Guide  

Science Conference Proceedings (OSTI)

Fuel handling is a critical item during a nuclear power plant refueling outage. The proper operation of fuel handling equipment, such as fuel handling machines, fuel upending machines, fuel transfer carriages, and fuel elevators, is important to a successful refueling outage and to preparing fuel for eventual disposal.

2007-12-21T23:59:59.000Z

102

Performance of nuclear plant RTDs  

SciTech Connect

Resistance temperature detectors (RTDs) are used for safety-related measurements in nuclear power plants and must therefore be accurate and respond to temperature changes in a timely fashion. Experience has shown that RTD calibration shift and response-time degradation can occur with aging. Therefore, periodic testing is performed to ensure that acceptable performance limits are not exceeded. A new method called the loop current step response (LCSR) test is used for periodic response-time testing of nuclear plant RTDs. This method permits testing the RTD as installed in an operating plant (in situ testing). The LCSR test is based on heating the RTD sensing element with a small electric current applied remotely through the sensor lead wires.

Hashemian, H.M.; Petersen, K.M.

1987-01-01T23:59:59.000Z

103

The Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

Dr. David A. Petti

2009-01-01T23:59:59.000Z

104

Nuclear power plants: structure and function  

SciTech Connect

Topics discussed include: steam electric plants; BWR type reactors; PWR type reactors; thermal efficiency of light water reactors; other types of nuclear power plants; the fission process and nuclear fuel; fission products and reactor afterheat; and reactor safety.

Hendrie, J.M.

1983-01-01T23:59:59.000Z

105

Homeowners: Respond to Power Outages | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Power Outages Power Outages Homeowners: Respond to Power Outages Homeowners: Respond to Power Outages After a disaster, electric utilities and government officials will first work to restore power to critical infrastructure like power plants and transmission lines, water treatment facilities, and telecommunications networks, and also to hospitals, critical care facilities, and emergency response agencies. It may take several days or even weeks to restore power to individual homeowners, but here's what you can do to help prepare and recover power more quickly: Charge mobile devices-If you have power, charge your cell phones, laptops, and other mobile devices so they'll have the maximum amount of battery power stored in the event of a power outage. These devices will help you communicate with your power company, and they'll help you stay

106

Advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

107

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Analysis of core damage frequency from internal events for plant operational state 5 during a refueling outage. Internal events appendices K to M  

Science Conference Proceedings (OSTI)

This report provides supporting documentation for various tasks associated with the performance of the probabilistic risk assessment for Plant Operational State 5 (approximately Cold Shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143. The report contains the following appendices: K - HEP Locator Files; L - Supporting Information for the Plant Damage State Analysis; M - Summary of Results from the Coarse Screening Analysis - Phase 1A.

Forester, J.; Yakle, J.; Walsh, B. [Science Applications International Corp., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Whitehead, D.; Staple, B.; Brown, T. [Sandia National Labs., Albuquerque, NM (United States)

1994-07-01T23:59:59.000Z

108

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

109

Sabotage at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

Purvis, James W.

1999-07-21T23:59:59.000Z

110

New York Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

nuclear power plants, summer capacity and net generation, 2010" nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Indian Point Unit 2, Unit 3","2,063","16,321",39.0,"Entergy Nuclear Indian Point" "James A Fitzpatrick Unit 1",855,"6,361",15.2,"Entergy Nuc Fitzpatrick LLC" "Nine Mile Point Nuclear Station Unit 1, Unit 2","1,773","14,239",34.0,"Nine Mile Point Nuclear Sta LLC" "R E Ginna Nuclear Power Plant Unit 1",581,"4,948",11.8,"R.E. Ginna Nuclear Power Plant, LLC" "4 Plants

111

Cell outage management in LTE networks  

Science Conference Proceedings (OSTI)

Cell outage management is a functionality aiming to automatically detect and mitigate outages that occur in radio networks due to unexpected failures. We envisage that future radio networks autonomously detect an outage based on measurements, from e.g., ...

M. Amirijoo; L. Jorguseski; T. Kürner; R. Litjens; M. Neuland; L. C. Schmelz; U. Türke

2009-09-01T23:59:59.000Z

112

Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches  

DOE Green Energy (OSTI)

The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

Steven R. Sherman

2007-06-01T23:59:59.000Z

113

Balance of Plant Corrosion Issues in Aging Nuclear Power Plants  

Science Conference Proceedings (OSTI)

... number of times, can be used to forecast the most probable number of leaks. ... Conditions for Long Term Operation of Nuclear Power Plants in Sweden.

114

Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Calvert Cliffs Nuclear Power Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

115

New York Nuclear Profile - R E Ginna Nuclear Power Plant  

U.S. Energy Information Administration (EIA) Indexed Site

R E Ginna Nuclear Power Plant" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License...

116

Organizational learning at nuclear power plants  

E-Print Network (OSTI)

The Nuclear Power Plant Advisory Panel on Organizational Learning provides channels of communications between the management and organization research projects of the MIT International Program for Enhanced Nuclear Power ...

Carroll, John S.

1991-01-01T23:59:59.000Z

117

Nuclear power plant construction activity, 1988  

SciTech Connect

Nuclear Power Plant Construction Activity 1988 presents cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1988. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors.

1989-06-14T23:59:59.000Z

118

Materials in Nuclear Power Plant Construction - TMS  

Science Conference Proceedings (OSTI)

139th Annual Meeting & Exhibition. February 14 - 18, 2010, Washington State Convention Center, Seattle, Washington USA. Materials in Nuclear Power. Plant  ...

119

Steam Reheat in Nuclear Power Plants.  

E-Print Network (OSTI)

??In this work, reheating steam from a commercial nuclear power plant is explored in order to increase efficiency and power output. A thermal source in… (more)

Marotta, Paul John

2012-01-01T23:59:59.000Z

120

Effective Personnel Exposure Control in Shortened Refueling Outages: Final Report: Review of Remote Monitoring Systems in Radiation Protection Applications  

Science Conference Proceedings (OSTI)

Remote monitoring technology (RMT) significantly enhances worker protection and reduces worker radiation exposure, particularly during shortened refueling outages. This report provides a brief description of the hardware and features of remote monitoring systems, then focuses on nuclear plant experiences in applying such systems for enhanced radiation protection. It also discusses EPRI's RMT research program and formation of the RMT Working Group to support research in this area. Such information will gr...

2003-12-02T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

OpenEI Community - outages  

Open Energy Info (EERE)

have been preparing for an imminent threat that could lead to a substantial and prolonged power outage for utility customers not only on the East Coast, but also as far west as...

122

Definition: Reduced Sustained Outages | Open Energy Information  

Open Energy Info (EERE)

Outages Outages Jump to: navigation, search Dictionary.png Reduced Sustained Outages A sustained outage is one lasting >5 minutes, excluding major outages and wide-scale outages. The monetary benefit of reducing sustained outages is based on the value of service (VOS) of each customer class. The VOS parameter represents the total cost of a power outage per MWh. This cost includes the value of unserved energy, lost productivity, collateral damage, administrative costs, the value of penalties and performance-based rates. Functions that lead to this benefit can reduce the likelihood that there will be an outage, allow the system to be reconfigured on the fly to help restore service to as many customers as possible, enable a quicker response in the restoration effort, or mitigate the impact of an outage

123

Pantex Plant | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

Plant | National Nuclear Security Administration Plant | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our Locations > Pantex Plant Pantex Plant http://www.pantex.com/ Field Office: The NNSA Production Office is responsible for contract management and oversight of the Pantex Plant in Amarillo, Texas and the Y-12 National Security Complex in Oak Ridge, Tenn. The Pantex Plant is

124

Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The nuclear power industry has entered into a voluntary initiative to implement groundwater monitoring programs at all nuclear power plant sites. This EPRI guideline provides essential technical guidance to nuclear power utilities on the necessary elements of a sound groundwater protection program.

2008-01-10T23:59:59.000Z

125

PROPOSED AMENDMENT TO THE NUCLEAR POWER PLANT  

E-Print Network (OSTI)

NOTE TO EDITORS: The Nuclear Regulatory Commission has received two reports from its independent Advisory Committee on Reactor Safeguards. The attached reports, in the form of letters, comment on a proposed amendment to the NRC's rule on license renewal for nuclear power plants and a proposed revision to the decommissioning rule for nuclear power reactors. Attachments:

T. S. Kress

1995-01-01T23:59:59.000Z

126

Nuclear Power Plant Concrete Structures  

Science Conference Proceedings (OSTI)

A nuclear power plant (NPP) involves complex engineering structures that are significant items of the structures, systems and components (SSC) important to the safe and reliable operation of the NPP. Concrete is the commonly used civil engineering construction material in the nuclear industry because of a number of advantageous properties. The NPP concrete structures underwent a great degree of evolution, since the commissioning of first NPP in early 1960. The increasing concern with time related to safety of the public and environment, and degradation of concrete structures due to ageing related phenomena are the driving forces for such evolution. The concrete technology underwent rapid development with the advent of chemical admixtures of plasticizer/super plasticizer category as well as viscosity modifiers and mineral admixtures like fly ash and silica fume. Application of high performance concrete (HPC) developed with chemical and mineral admixtures has been witnessed in the construction of NPP structures. Along with the beneficial effect, the use of admixtures in concrete has posed a number of challenges as well in design and construction. This along with the prospect of continuing operation beyond design life, especially after 60 years, the impact of extreme natural events ( as in the case of Fukushima NPP accident) and human induced events (e.g. commercial aircraft crash like the event of September 11th 2001) has led to further development in the area of NPP concrete structures. The present paper aims at providing an account of evolution of NPP concrete structures in last two decades by summarizing the development in the areas of concrete technology, design methodology and construction techniques, maintenance and ageing management of concrete structures.

Basu, Prabir [International Atomic Energy Agency (IAEA)] [International Atomic Energy Agency (IAEA); Labbe, Pierre [Electricity of France (EDF)] [Electricity of France (EDF); Naus, Dan [Oak Ridge National Laboratory (ORNL)] [Oak Ridge National Laboratory (ORNL)

2013-01-01T23:59:59.000Z

127

Plutonium Processing Plant Deactivated | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

128

Plutonium Processing Plant Deactivated | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

129

Water Hammer Handbook for Nuclear Plant Engineers and Operators  

Science Conference Proceedings (OSTI)

Water hammer events continue to be responsible for costly equipment damage and plant outages. This Water Hammer Handbook is designed to help utility engineers prevent, mitigate, and accommodate water hammer events. The handbook provides assessment techniques, design approaches, and operating procedures. Also included are a root cause summary and an extensive overview of BWR and PWR water hammer experience on a system-by-system basis.

1996-10-04T23:59:59.000Z

130

DOE Announces Loan Guarantee Applications for Nuclear Power Plant...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis...

131

A Review of Sensor Calibration Monitoring for Calibration Interval Extension in Nuclear Power Plants  

SciTech Connect

Currently in the United States, periodic sensor recalibration is required for all safety-related sensors, typically occurring at every refueling outage, and it has emerged as a critical path item for shortening outage duration in some plants. Online monitoring can be employed to identify those sensors that require calibration, allowing for calibration of only those sensors that need it. International application of calibration monitoring, such as at the Sizewell B plant in United Kingdom, has shown that sensors may operate for eight years, or longer, within calibration tolerances. This issue is expected to also be important as the United States looks to the next generation of reactor designs (such as small modular reactors and advanced concepts), given the anticipated longer refueling cycles, proposed advanced sensors, and digital instrumentation and control systems. The U.S. Nuclear Regulatory Commission (NRC) accepted the general concept of online monitoring for sensor calibration monitoring in 2000, but no U.S. plants have been granted the necessary license amendment to apply it. This report presents a state-of-the-art assessment of online calibration monitoring in the nuclear power industry, including sensors, calibration practice, and online monitoring algorithms. This assessment identifies key research needs and gaps that prohibit integration of the NRC-approved online calibration monitoring system in the U.S. nuclear industry. Several needs are identified, including the quantification of uncertainty in online calibration assessment; accurate determination of calibration acceptance criteria and quantification of the effect of acceptance criteria variability on system performance; and assessment of the feasibility of using virtual sensor estimates to replace identified faulty sensors in order to extend operation to the next convenient maintenance opportunity. Understanding the degradation of sensors and the impact of this degradation on signals is key to developing technical basis to support acceptance criteria and set point decisions, particularly for advanced sensors which do not yet have a cumulative history of operating performance.

Coble, Jamie B.; Meyer, Ryan M.; Ramuhalli, Pradeep; Bond, Leonard J.; Hashemian, Hash; Shumaker, Brent; Cummins, Dara

2012-08-31T23:59:59.000Z

132

Guide to Optimized Nuclear Low-Pressure Turbine Rotor Inspection  

Science Conference Proceedings (OSTI)

In the past few years, the nuclear utility industry has reduced down-time for refueling outages to trim costs and improve overall unit performance. Consequently, this has also reduced the time available for other routine outage work and has often placed turbine maintenance and inspection tasks on the critical path. This report provides a review of the strategies several nuclear utilities have employed at their plants to reduce the time required to perform low-pressure turbine inspections. Included is a r...

1997-12-23T23:59:59.000Z

133

Plant Support Engineering: Elastomer Handbook for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

On a daily basis, engineers and maintenance personnel make judgments regarding the capabilities, degradation, and longevity of elastomeric material and its compatibility with other materials. Although most applications of elastomers in nuclear power plants are not unique to the industry, there is an extra emphasis in certain applications with regard to reliability, quality, and resistance to nuclear-plant-specific environments. Existing resources on elastomers are extensive, but they are not tailored to ...

2007-08-20T23:59:59.000Z

134

Nuclear Power Plant NDE Challenges — Past, Present, and Future  

Science Conference Proceedings (OSTI)

The operating fleet of U.S. nuclear power plants was built to fossil plant standards (of workmanship

S. R. Doctor

2007-01-01T23:59:59.000Z

135

New York Nuclear Profile - R E Ginna Nuclear Power Plant  

U.S. Energy Information Administration (EIA)

snpt3ny6122 581 4,948 97.2 PWR R E Ginna Nuclear Power Plant Unit Summer Capacity (MW) Net Generation (Thousand MWh) Summer Capacity Factor (Percent) Type

136

outages | OpenEI Community  

Open Energy Info (EERE)

66 66 Varnish cache server Home Groups Community Central Green Button Applications Developer Utility Rate FRED: FRee Energy Database More Public Groups Private Groups Features Groups Blog posts Content Stream Documents Discussions Polls Q & A Events Notices My stuff Energy blogs 429 Throttled (bot load) Error 429 Throttled (bot load) Throttled (bot load) Guru Meditation: XID: 2142234866 Varnish cache server outages Home Graham7781's picture Submitted by Graham7781(2002) Super contributor 29 October, 2012 - 14:46 East Coast Utilities prepare for Hurricane Sandy East Coast Hurricane Sandy OpenEI outages storm United States Utility Companies As Hurricane Sandy continues to track towards the coast of the Eastern United States, utility companies have been preparing for an imminent threat that could lead to a substantial and prolonged power outage for utility

137

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 3: Internal Events Appendices I and J  

SciTech Connect

This report provides supporting documentation for various tasks associated with the performance of the probablistic risk assessment for Plant Operational State 5 during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143.

Yakle, J. [Science Applications International Corp., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Whitehead, D.; Staple, B. [Sandia National Labs., Albuquerque, NM (United States)

1994-06-01T23:59:59.000Z

138

Kansas City Plant | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

| National Nuclear Security Administration | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our Locations > Kansas City Plant Kansas City Plant http://honeywell.com/sites/aero-kcp/Pages/Home.aspx Field Office: The Kansas City Field Office (KCFO) stewards the NNSA Kansas City Plant, the principal nonnuclear production site within the nuclear

139

Kansas City Plant | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

| National Nuclear Security Administration | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our Locations > Kansas City Plant Kansas City Plant http://honeywell.com/sites/aero-kcp/Pages/Home.aspx Field Office: The Kansas City Field Office (KCFO) stewards the NNSA Kansas City Plant, the principal nonnuclear production site within the nuclear

140

Project Prioritization for Nuclear Plant Investments  

Science Conference Proceedings (OSTI)

Evaluating investments, sometimes called project prioritization, is a central business process in a plant's or fleet's management of their nuclear assets. To date, a variety of project prioritization approaches have been used in the nuclear industry. Many nuclear utilities use an approach that can be characterized as an engineering work grading process. Project prioritization is related closely to long-range planning. Long-range plans help to avoid surprises from increased expenditures and reduced levels...

2008-12-23T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Nuclear power plant construction activity, 1986  

SciTech Connect

Cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1986, are presented. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors.

1987-07-24T23:59:59.000Z

142

The Politically Correct Nuclear Energy Plant  

E-Print Network (OSTI)

- and downstream processes Risks due to power plant emissions Coal Lignite Gas CC Nuclear PV (amorph) Wind Hydro-proliferation and waste. Then BUILD one! #12;Modular Pebble Bed Reactor Thermal Power 250 MW Core Height 10.0 m Core Product Barrier · Core Physics · Safety · Balance of Plant Design · Modularity Design · Core Power

143

Definition: Reduced Major Outages | Open Energy Information  

Open Energy Info (EERE)

Outages Outages Jump to: navigation, search Dictionary.png Reduced Major Outages A major outage is defined using the beta method, per IEEE Std 1366-2003 (IEEE Power Engineering Society 2004). The monetary benefit of reducing major outages is based on the VOS of each customer class. The VOS parameter represents the total cost of a power outage per MWh. This cost includes the value of unserved energy, lost productivity, collateral damage, the value of penalties and performance-based rates. Functions that lead to this benefit can mitigate major outages by allowing the system to be reconfigured on the fly to help restore service to as many customers as possible, enable a quicker response in the restoration effort, or mitigate the impact of an outage through islanding or alternative power supply.[1]

144

Definition: Outage Management System | Open Energy Information  

Open Energy Info (EERE)

Outage Management System Outage Management System A software application that can process outage reports from a variety of utility operational systems including SCADA, AMI, and customer phone calls, and display outage information to utility operators. The OMS can help a utility interpret outage information and determine where the likely cause of an outage may be. It can also help the utility optimize its service restoration resources.[1] Related Terms advanced metering infrastructure References ↑ https://www.smartgrid.gov/category/technology/outage_management_system [[C LikeLike UnlikeLike You like this.Sign Up to see what your friends like. ategory: Smart Grid Definitionssmart grid,smart grid, |Template:BASEPAGENAME]]smart grid,smart grid, Retrieved from "http://en.openei.org/w/index.php?title=Definition:Outage_Management_System&oldid=502507

145

Broadcast Outages for NIST Radio Station WWVB  

Science Conference Proceedings (OSTI)

... Numerous short outages while station was undergoing maintenance and testing during daylight hours. WWVB operated at reduced power during ...

146

Nuclear power plant construction activity 1987  

SciTech Connect

This annual report published by the Energy Information Administration (EIA) presents data on nuclear power plant construction activity. The previous report, Nuclear Power Plant Construction Activity 1986, included data for units that, as of December 31, 1986, were (1) in the construction pipeline, (2) canceled, or (3) commercial operation as of December 31, 1986. The data in this report, which were collected on Form EIA-254, ''Semiannual Report on Status of Reactor Construction,'' update the data in the previous report to be current as of December 31, 1987. Three types of information are included: plant characteristics and ownership; construction costs; and construction schedules and milestone dates.

1988-06-09T23:59:59.000Z

147

South Carolina Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA) Indexed Site

South Carolina nuclear power plants, summer capacity and net generation, 2010" South Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Catawba Unit 1, Unit 2","2,258","18,964",36.5,"Duke Energy Carolinas, LLC" "H B Robinson Unit 2",724,"3,594",6.9,"Progress Energy Carolinas Inc" "Oconee Unit 1, Unit 2, Unit 3","2,538","20,943",40.3,"Duke Energy Carolinas, LLC" "V C Summer Unit 1",966,"8,487",16.3,"South Carolina Electric&Gas Co" "4 Plants 7 Reactors","6,486","51,988",100.0

148

Nuclear Power Plant Design Project  

E-Print Network (OSTI)

................................................. 22 5.1.16 Decommissioning: AP600, HTGR, ALWR ............................................................................................................... 35 7.3.4 Decommissioning Cost #12;9 decommissioning. The long delayed nuclear waste disposal facility at Yucca Mountain is becoming

149

Nuclear Maintenance Applications Center: Nuclear Fuel Handling Equipment Application and Maintenance Guide: Fuel Handling Equipment Guide  

Science Conference Proceedings (OSTI)

Fuel handling is a critical task during a nuclear power plant refueling outage. The proper operation of fuel handling equipment (such as fuel handling machines, fuel upending machines, fuel transfer carriages, and fuel elevators) is important to a successful refueling outage and to preparing fuel for eventual disposal.BackgroundThe fuel handling system contains the components used to move fuel from the time that the new fuel is received until the spent fuel ...

2013-12-13T23:59:59.000Z

150

Missouri Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2mo Callaway Unit 1 1,190 8,996 100.0 Union Electric Co 1 Plant 1 Reactor Owner Note: Totals may not equal sum of components due to independent rounding.

151

Texas Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2tx Comanche Peak Unit 1, Unit 2 2,406 20,208 48.9 Luminant Generation Company LLC South Texas Project Unit 1, Unit 2 2,560 21,127 51.1 STP Nuclear Operating Co

152

Nuclear plant cancellations: causes, costs, and consequences  

Science Conference Proceedings (OSTI)

This study was commissioned in order to help quantify the effects of nuclear plant cancellations on the Nation's electricity prices. This report presents a historical overview of nuclear plant cancellations through 1982, the costs associated with those cancellations, and the reasons that the projects were terminated. A survey is presented of the precedents for regulatory treatment of the costs, the specific methods of cost recovery that were adopted, and the impacts of these decisions upon ratepayers, utility stockholders, and taxpayers. Finally, the report identifies a series of other nuclear plants that remain at risk of canellation in the future, principally as a result of similar demand, finance, or regulatory problems cited as causes of cancellation in the past. The costs associated with these potential cancellations are estimated, along with their regional distributions, and likely methods of cost recovery are suggested.

Not Available

1983-04-01T23:59:59.000Z

153

Reduce power outages  

SciTech Connect

A case history shows the cost-effectiveness of doing a reliability study on a new, grassroots refinery constructed in Venezuela. Constructing grassroots refineries in developing countries pose many challenges, especially when considering electrical power and steam supplies. Without dependable electrical and steam sources, the refinery will not operate according to design expectations. Consequently, utility systems are critical and expensive challenges that must be considered early in design. Because of tighter operating budgets, refiners are equally interested in cutting out system overdesign. Redundant backup systems are damaging in capital and operating expenditures. Using reliability analysis techniques, designers can evaluate the reliability, availability and maintainability of operating systems. In the following example, a Venezuelan operating company used a reliability analysis to: assess onstream factors for the refinery`s power plant; identify critical equipment that have the greatest impact on available electrical and steam sources; and achieve a cost-effective equipment configuration that eliminates redundant backup systems. Results from the study allowed decision-makers to initiate objective plans and created an equipment-failure database that will service the refinery for its useful life.

Goyal, R. [BAPCO, Awali (Bahrain); Ramirez, R. [Corpoven S.A., Caracas (Venezuela)

1995-06-01T23:59:59.000Z

154

Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06  

SciTech Connect

Following the highly successful ICAPP'05 meeting held in Seoul Korea, the 2006 International Congress on Advances in Nuclear Power Plants brought together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to Nuclear Power Plants. The program covers the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program covers lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design and reliability. The program by technical track deals with: - 1. Water-Cooled Reactor Programs and Issues Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting medium term utility needs; design and regulatory issues; business, political and economic challenges; infrastructure limitations and improved construction techniques including modularization. - 2. High Temperature Gas Cooled Reactors Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, hydrogen production and other industrial uses; advanced thermal and fast reactors. - 3. Long Term Reactor Programs and Strategies Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as, super critical water reactors, liquid metal reactors, gaseous and liquid fuel reactors, Gen IV, INPRO, EUR and other programs. - 4. Operation, Performance and Reliability Management Training, O and M costs, life cycle management, risk based maintenance, operational experiences, performance and reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in-service inspection, and codes and standards. - 5. Plant Safety Assessment and Regulatory Issues Transient and accident performance including LOCA and non-LOCA, severe accident analysis, impact of risk informed changes, accident management, assessment and management of aging, degradation and damage, life extension lessons from plant operations, probabilistic safety assessment, plant safety analysis, reliability engineering, operating and future plants. - 6. Thermal Hydraulic Analysis and Testing Phenomena identification and ranking, computer code scaling applicability and uncertainty, containment thermal hydraulics, component and integral system tests, improved code development and qualification, single and two phase flow; advanced computational thermal hydraulic methods. - 7. Core and Fuel Cycle Concepts and Experiments Core physics, advances in computational reactor analysis, in-core fuel management, mixed-oxide fuel, thorium fuel cycle, low moderation cores, high conversion reactor designs, particle and pebble bed fuel design, testing and reliability; fuel cycle waste minimization, recycle, storage and disposal. - 8. Materials and Structural Issues Fuel, core, RPV and internals structures, advanced materials issues and fracture mechanics, concrete and steel containments, space structures, analysis, design and monitoring for seismic, dynamic and extreme accidents; irradiation issues and materials for new plants. - 9. Nuclear Energy and Sustainability including Hydrogen, Desalination and Other Applications Environmental impact of nuclear and alternative systems, spent fuel dispositions and transmutation systems, fully integrated fuel cycle and symbiotic nuclear power systems, application of advanced designs to non-power applications such as the production of hydrogen, sea water desalination, heating and other co-generation applications. - 10. Near Term Issues (New) Applies to plants that have a significa

NONE

2006-07-01T23:59:59.000Z

155

Seismic Isolation of Nuclear Power Plants  

Science Conference Proceedings (OSTI)

With increasing public concern for seismic safety in general and research findings that indicate that seismic hazards may be larger than expected in many parts of the world, it would be prudent for the nuclear industry to consider more fully the potential benefits, costs, and impediments associated with applying seismic isolation more widely and to identify actions needed to develop practical and cost-effective guidelines for the application of seismic isolation to nuclear power plants (NPPs) and ...

2013-10-28T23:59:59.000Z

156

Virtual environments for nuclear power plant design  

SciTech Connect

In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W. [and others

1996-03-01T23:59:59.000Z

157

Holdup measurement for nuclear fuel manufacturing plants  

Science Conference Proceedings (OSTI)

The assay of nuclear material holdup in fuel manufacturing plants is a laborious but often necessary part of completing the material balance. A range of instruments, standards, and a methodology for assaying holdup has been developed. The objectives of holdup measurement are ascertaining the amount, distribution, and how firmly fixed the SNM is. The purposes are reconciliation of material unbalance during or after a manufacturing campaign or plant decommissioning, to decide security requirements, or whether further recovery efforts are justified.

Zucker, M.S.; Degen, M.; Cohen, I.; Gody, A.; Summers, R.; Bisset, P.; Shaub, E.; Holody, D.

1981-07-13T23:59:59.000Z

158

Nuclear plant construction and investment risk  

SciTech Connect

Escalated cost estimations, delays and cancellations in nuclear construction have caused a preoccupation with the risks of nuclear power plant construction that dominates utility stock investment, overshadowing increased earnings per share and recent growth in production. The issue will be resolved when increased power demand requires new construction, but the effect has so far been to erode the economic advantage of nuclear power and threaten the ability of utilities to get rate increases high enough to cover their costs. Projected delays and cost escalations and their effects must go into an economic appraisal of the investment risks.

Studness, C.M.

1984-07-05T23:59:59.000Z

159

Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant  

U.S. Energy Information Administration (EIA)

snpt3md6011 855 6,755 90.2 PWR 850 7,239 97.2 1,705 13,994 93.7 Calvert Cliffs Nuclear Power Plant Unit Type Data for 2010 PWR = Pressurized Light Water Reactor.

160

Groundwater Monitoring Guidance for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Recent experience has shown that the initial design of nuclear power plant groundwater characterization programs can have a significant impact upon the resources needed to demonstrate regulatory compliance. This document provides technical experience and lessons learned in designing an optimized groundwater investigation program.

2005-09-06T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Overview of Trends in Nuclear Power Plant Sensors and Instrumentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Trends in Nuclear Power Plant Sensors and Instrumentation SASAN BAKTIARI Nuclear Engineering Division Argonne National Laboratory Ph: (630) 252-8982 bakhtiati@anl.gov Abstract -...

162

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

... (kWh). There were 65 nuclear power plants with 104 operating nuclear reactors that generated a total of 790 billion kilowatt-hours (kWh), ...

163

Definition: Reduced Momentary Outages | Open Energy Information  

Open Energy Info (EERE)

Momentary Outages Momentary Outages Jump to: navigation, search Dictionary.png Reduced Momentary Outages By locating faults more accurately or adding electricity storage, momentary outages could be reduced or eliminated. Moreover, fewer customers on the same or adjacent distribution feeders would experience the momentary interruptions associated with reclosing. Momentary outages last <5 min in duration. The benefit to consumers is based on the value of service.[1] Related Terms electricity storage technologies, electricity generation, smart grid References ↑ SmartGrid.gov 'Description of Benefits' An in LikeLike UnlikeLike You like this.Sign Up to see what your friends like. line Glossary Definition Retrieved from "http://en.openei.org/w/index.php?title=Definition:Reduced_Momentary_Outages&oldid=493094

164

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 2, Part 1C: Analysis of core damage frequency from internal events for plant operational State 5 during a refueling outage, Main report (Sections 11--14)  

SciTech Connect

This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power analyses performed on Grand Gulf.

Whitehead, D. [Sandia National Labs., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Yakle, J. [Science Applications International Corp., Albuquerque, NM (United States)] [and others

1994-06-01T23:59:59.000Z

165

Trojan Nuclear Power Plant Reactor Vessel and Internals Removal: Trojan Nuclear Plant Decommissioning Experience  

Science Conference Proceedings (OSTI)

One goal of the EPRI Decommissioning Technology Program is to capture the growing utility experience in nuclear plant decommissioning activities for the benefit of other utilities facing similar challenges in the future. This report provides historical information on the background, scope, organization, schedule, cost, contracts, and support activities associated with the Trojan Nuclear Plant Reactor Vessel and Internals Removal (RVAIR) Project. Also discussed are problems, successes, and lessons learned...

2000-10-16T23:59:59.000Z

166

SIGNAL GROUPING FOR CONDITION MONITORING OF NUCLEAR POWER PLANT COMPONENTS  

E-Print Network (OSTI)

SIGNAL GROUPING FOR CONDITION MONITORING OF NUCLEAR POWER PLANT COMPONENTS Piero Baraldi between those used to monitor the reactor coolant pump of a Pressurized Water Reactor (PWR) is considered Monitoring, Empirical Modeling, Power Plants, Safety Critical Nuclear Instrumentation, Autoassociative models

167

Broadcast Outages for NIST Radio Station WWVB  

Science Conference Proceedings (OSTI)

... Broadcast Outages for WWVB. ... WWVB will be operating at 1/2 power (35 kW) during the daylight hours on weekdays from September 14, 2009 until ...

168

Advanced nuclear plant control room complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

169

International Cooperation on Safety of Nuclear Plants - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

170

Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant  

Energy.gov (U.S. Department of Energy (DOE))

NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

171

Engineering Fundamentals - Nuclear Power Plant Materials, Version 2.0  

Science Conference Proceedings (OSTI)

The Engineering Fundamentals - Nuclear Power Plant Materials (EF-Materials) Version 2.0 computer-based training module provides new-hire engineering personnel with an overview of the basic concepts of nuclear power plant materials. Graphics and interactive features are used to enhance learning.EF-Materials covers the basic terms and concepts related to nuclear power plant materials and provides information about the significance of material degradation issues in nuclear power plants. ...

2012-11-30T23:59:59.000Z

172

Extending Sensor Calibration Intervals in Nuclear Power Plants  

SciTech Connect

Currently in the USA, sensor recalibration is required at every refueling outage, and it has emerged as a critical path item for shortening outage duration. International application of calibration monitoring, such as at the Sizewell B plant in UK, has shown that sensors may operate for eight years, or longer, within calibration tolerances. Online monitoring can be employed to identify those sensors which require calibration, allowing for calibration of only those sensors which need it. The US NRC accepted the general concept of online monitoring for sensor calibration monitoring in 2000, but no plants have been granted the necessary license amendment to apply it. This project addresses key issues in advanced recalibration methodologies and provides the science base to enable adoption of best practices for applying online monitoring, resulting in a public domain standardized methodology for sensor calibration interval extension. Research to develop this methodology will focus on three key areas: (1) quantification of uncertainty in modeling techniques used for calibration monitoring, with a particular focus on non-redundant sensor models; (2) accurate determination of acceptance criteria and quantification of the effect of acceptance criteria variability on system performance; and (3) the use of virtual sensor estimates to replace identified faulty sensors to extend operation to the next convenient maintenance opportunity.

Coble, Jamie B.; Meyer, Ryan M.; Ramuhalli, Pradeep; Bond, Leonard J.; Shumaker, Brent; Hashemian, Hash

2012-11-15T23:59:59.000Z

173

Balance of Plant Requirements for a Nuclear Hydrogen Plant  

DOE Green Energy (OSTI)

This document describes the requirements for the components and systems that support the hydrogen production portion of a 600 megawatt thermal (MWt) Next Generation Nuclear Plant (NGNP). These systems, defined as the "balance-of-plant" (BOP), are essential to operate an effective hydrogen production plant. Examples of BOP items are: heat recovery and heat rejection equipment, process material transport systems (pumps, valves, piping, etc.), control systems, safety systems, waste collection and disposal systems, maintenance and repair equipment, heating, ventilation, and air conditioning (HVAC), electrical supply and distribution, and others. The requirements in this document are applicable to the two hydrogen production processes currently under consideration in the DOE Nuclear Hydrogen Initiative. These processes are the sulfur iodide (S-I) process and the high temperature electrolysis (HTE) process. At present, the other two hydrogen production process - the hybrid sulfur-iodide electrolytic process (SE) and the calcium-bromide process (Ca-Br) -are under flow sheet development and not included in this report. While some features of the balance-of-plant requirements are common to all hydrogen production processes, some details will apply only to the specific needs of individual processes.

Bradley Ward

2006-04-01T23:59:59.000Z

174

THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM  

Science Conference Proceedings (OSTI)

Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor (HTGR) is one of the critical development activities being pursued within the Next Generation Nuclear Plant (NGNP) program. Graphite’s thermal stability (in an inert gas environment), high compressive strength, fabricability, and cost effective price make it an ideal core structural material for the HTGR reactor design. While the general characteristics necessary for producing nuclear grade graphite are understood, historical “nuclear” grades no longer exist. New grades must be fabricated, characterized, and irradiated to demonstrate that current grades of graphite exhibit acceptable non-irradiated and irradiated properties upon which the thermo-mechanical design of the structural graphite in NGNP is based. The NGNP graphite R&D program has selected a handful of commercially available types for research and development activities necessary to qualify this nuclear grade graphite for use within the NGNP reactor. These activities fall within five primary areas; 1) material property characterization, 2) irradiated material property characterization, 3) modeling, and 4) ASTM test development, and 5) ASME code development efforts. Individual research and development activities within each area are being pursued with the ultimate goal of obtaining a commercial operating license for the nuclear graphite from the US NRC.

William E. Windes; Timothy D. Burchell; Robert L. Bratton

2008-09-01T23:59:59.000Z

175

Nuclear Plant Life Cycle Management Implementation Guide  

Science Conference Proceedings (OSTI)

The day-to-day pressures of operation, limited budgets, and regulatory scrutiny of nuclear power plants focus on the present or short term, and may preempt cost-beneficial activities with long-term pay-off. This guide to implementing life-cycle management (LCM) fosters long-range thinking and decision making focused on profitability in the new competitive era of electricity production.

1998-11-19T23:59:59.000Z

176

Track NERSC Scheduled and Unscheduled Outages in Google Calendar  

NLE Websites -- All DOE Office Websites (Extended Search)

Track NERSC Outages in Google Calendar Track NERSC Outages in Google Calendar March 22, 2013 by Jack Deslippe (0 Comments) Outages are now available in Google calendar form. You...

177

North American Electric Reliability Council Outage Announcement |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Council Outage Announcement Council Outage Announcement North American Electric Reliability Council Outage Announcement Starting at about 4:11 p.m. EDT, major losses of electric load occurred in the northeastern United States and Canada in the Eastern Interconnection. Although the exact cause is not known at present, the outages are not the result of a terrorist attack. The areas most affected center around the Great Lakes: Michigan, Ohio, New York City, Ontario, Quebec, northern New Jersey, Massachusetts, and Connecticut. North American Electric Reliability Council Outage Announcement More Documents & Publications Blackout 2003: Final Report on the August 14, 2003 Blackout in the United States and Canada: Causes and Recommendations Blackout 2003: Blackout Final Implementation Report

178

Nuclear power plant performance assessment pertaining to plant aging in France and the United States  

E-Print Network (OSTI)

The effect of aging on nuclear power plant performance has come under increased scrutiny in recent years. The approaches used to make an assessment of this effect strongly influence the economics of nuclear power plant ...

Guyer, Brittany (Brittany Leigh)

2013-01-01T23:59:59.000Z

179

Analysis of nuclear power plant construction costs  

SciTech Connect

The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs.

1986-01-01T23:59:59.000Z

180

Guidelines for Reduced Seismic Loads to Assess Temporary Conditions in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities do not have uniform guidelines and criteria to treat plant temporary conditions (TCs) or planned changes to safety-related systems. Regulatory review and acceptance criteria and guidelines tend to be overly conservative, leading to costly measures. This report proposes a risk-informed procedure for evaluating TCs using reduced seismic loads and current licensing basis allowables that reduces plant operation and maintenance (O&M) costs, shortens plant outages, and reduces personnel radiation exp...

1998-09-10T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Korea Hydro & Nuclear Power Co., Ltd. Nuclear Power Plants: Construction and Technology Experience  

Science Conference Proceedings (OSTI)

The Korean nuclear power industry has grown rapidly since Kori Unit 1, the first Korean nuclear power plant (NPP), which began operation in April 1978. Following the technology developments of the nuclear power industry in 1980s, the first standard Korean nuclear plants (Ulchin Units 3 and 4) were constructed in the 1990s. At present, 20 NPP units operate in Korea16 pressurized water reactor (PWR) plants and four pressurized heavy water reactor (PHWR) plants; eight PWR units are under construction. This ...

2011-09-21T23:59:59.000Z

182

Secretary Chu Visits Vogtle Nuclear Power Plant | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Vogtle Nuclear Power Plant Vogtle Nuclear Power Plant Secretary Chu Visits Vogtle Nuclear Power Plant February 15, 2012 - 3:54pm Addthis Secretary Chu traveled to Waynesboro, Georgia, to visit the Vogtle nuclear power plant, the site of what will be the first new nuclear reactors to be built in the United States in three decades. | Image credit: Southern Company. Secretary Chu traveled to Waynesboro, Georgia, to visit the Vogtle nuclear power plant, the site of what will be the first new nuclear reactors to be built in the United States in three decades. | Image credit: Southern Company. Niketa Kumar Niketa Kumar Public Affairs Specialist, Office of Public Affairs Just over 60 years ago, scientists in Arco, Idaho, successfully used nuclear energy to power four light bulbs, laying the foundation for U.S.

183

Managing turbine-generator outages by computer  

SciTech Connect

This article describes software being developed to address the need for computerized planning and documentation programs that can help manage outages. Downsized power-utility companies and the growing demand for independent, competitive engineering and maintenance services have created a need for a computer-assisted planning and technical-direction program for turbine-generator outages. To meet this need, a software tool is now under development that can run on a desktop or laptop personal computer to assist utility personnel and technical directors in outage planning. Total Outage Planning Software (TOPS), which runs on Windows, takes advantage of the mass data storage available with compact-disc technology by archiving the complete outage documentation on CD. Previous outage records can then be indexed, searched, and viewed on a computer with the click of a mouse. Critical-path schedules, parts lists, parts order tracking, work instructions and procedures, custom data sheets, and progress reports can be generated by computer on-site during an outage.

Reinhart, E.R. [Reinhart and Associates, Inc., Austin, TX (United States)

1997-09-01T23:59:59.000Z

184

Nuclear Plant Analyzer: Installation manual. Volume 1  

SciTech Connect

This report contains the installation instructions for the Nuclear Plant Analyzer (NPA) System. The NPA System consists of the Computer Visual System (CVS) program, the NPA libraries, the associated utility programs. The NPA was developed at the Idaho National Engineering Laboratory under the sponsorship of the US Nuclear Regulatory Commission to provide a highly flexible graphical user interface for displaying the results of these analysis codes. The NPA also provides the user with a convenient means of interactively controlling the host program through user-defined pop-up menus. The NPA was designed to serve primarily as an analysis tool. After a brief introduction to the Computer Visual System and the NPA, an analyst can quickly create a simple picture or set of pictures to aide in the study of a particular phenomenon. These pictures can range from simple collections of square boxes and straight lines to complex representations of emergency response information displays.

Snider, D.M.; Wagner, K.L.; Grush, W.H.; Jones, K.R. [Idaho National Engineering Lab., Idaho Falls, ID (United States)]|[Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-01-01T23:59:59.000Z

185

Recent Progress in U.S. Nuclear Power Plant Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Recent Progress in U.S. Nuclear Power Plant Safety Speaker(s): Robert Budnitz Date: April 15, 2010 - 12:00pm Location: 90-3122 The U.S. commercial nuclear-power industry consists...

186

Definition: Sustained Outage | Open Energy Information  

Open Energy Info (EERE)

Sustained Outage Sustained Outage Jump to: navigation, search Dictionary.png Sustained Outage The deenergized condition of a transmission line resulting from a fault or disturbance following an unsuccessful automatic reclosing sequence and/or unsuccessful manual reclosing procedure.[1] View on Wikipedia Wikipedia Definition A power outage (also power cut, blackout, or power failure) is a short- or long-term loss of the electric power to an area. There are many causes of power failures in an electricity network. Examples of these causes include faults at power stations, damage to electric transmission lines, substations or other parts of the distribution system, a short circuit, or the overloading of electricity mains. Power failures are particularly critical at sites where the environment and public safety are

187

Systems and Services Outage Notification Policy  

NLE Websites -- All DOE Office Websites (Extended Search)

Job Logs & Analytics Job Logs & Analytics Training & Tutorials Software Accounts & Allocations Policies Acknowledge NERSC Allocation Eligibility Allocation Management Computer Security Computer Use Data Management Passwords Queue Scheduling Usage Charges System Outages Data Analytics & Visualization Data Management Policies Science Gateways User Surveys NERSC Users Group User Announcements Help Operations for: Passwords & Off-Hours Status 1-800-66-NERSC, option 1 or 510-486-6821 Account Support https://nim.nersc.gov accounts@nersc.gov 1-800-66-NERSC, option 2 or 510-486-8612 Consulting http://help.nersc.gov consult@nersc.gov 1-800-66-NERSC, option 3 or 510-486-8611 Home » For Users » Policies » System Outages Systems Outage Notification Policy To be considered a scheduled outage, the user community must be notified of

188

Definition: Forced Outage | Open Energy Information  

Open Energy Info (EERE)

Forced Outage Forced Outage Jump to: navigation, search Dictionary.png Forced Outage The removal from service availability of a generating unit, transmission line, or other facility for emergency reasons., The condition in which the equipment is unavailable due to unanticipated failure.[1] Related Terms transmission lines, transmission line References ↑ Glossary of Terms Used in Reliability Standards An i LikeLike UnlikeLike You like this.Sign Up to see what your friends like. nline Glossary Definition Retrieved from "http://en.openei.org/w/index.php?title=Definition:Forced_Outage&oldid=480310" Categories: Definitions ISGAN Definitions What links here Related changes Special pages Printable version Permanent link Browse properties About us Disclaimers Energy blogs Linked Data

189

August 14, 2003 Power Outages Â… Announcement  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Ellen P. Vancko Ellen P. Vancko evancko@nerc.com Power Outage Update ⎯ 8/16/2003 11 a.m. EDT The bulk electric transmission system in the United States and Canada has been restored and is operating reliably. Many of the generating units that tripped off line during the outage have returned to service and additional generating units are expected to return to service over the weekend. Virtually all customers have been returned to electric service, although some customers will continue to experience rotating outages due to generating capacity availability. Some rotating outages may also be necessary on Monday depending on the status of the generating units returning to service and the electrical demand. "NERC is conducting a thorough investigation into this event in conjunction with the regional

190

Electromagnetic Compatibility in Nuclear Power Plants  

SciTech Connect

Electromagnetic compatibility (EMC) has long been a key element of qualification for mission critical instrumentation and control (I&C) systems used by the U.S. military. The potential for disruption of safety-related I&C systems by electromagnetic interference (EMI), radio-frequency interference (RFI), or power surges is also an issue of concern for the nuclear industry. Experimental investigations of the potential vulnerability of advanced safety systems to EMI/RFI, coupled with studies of reported events at nuclear power plants (NPPs) that are attributed to EMI/RFI, confirm the safety significance of EMC for both analog and digital technology. As a result, Oak Ridge National Laboratory has been engaged in the development of the technical basis for guidance that addresses EMC for safety-related I&C systems in NPPs. This research has involved the identification of engineering practices to minimize the potential impact of EMI/RFI and power surges and an evaluation of the ambient electromagnetic environment at NPPs to tailor those practices for use by the nuclear industry. Recommendations for EMC guidance have been derived from these research findings and are summarized in this paper.

Ewing, P.D.; Kercel, S.W.; Korsah, K.; Wood, R.T.

1999-08-29T23:59:59.000Z

191

Multipurpose Outage at a Midsize, Resource-Limited Nonpower Reactor  

SciTech Connect

The University of Florida Training Reactor (UFTR) is a light water-cooled, graphite and light water-moderated, modified Argonaut-type reactor licensed to operate at steady-state power levels up to 100 kW. The UFTR was subject to a unique and lengthy voluntary outage beginning in May 1998 following several months of gradual increases in the normal critical position totaling {approx}0.002 {Delta}k/k. The Nuclear Regulatory Commission (NRC) was updated periodically on the facility status and visited the facility twice during the outage and once since restart to normal operations on August 17, 1999. Various potential causes of this reactivity anomaly were identified. After investigation, each of these causes was eliminated with no specific cause ever identified. Despite all the inherent limitations and especially because of the difficulty of core access, this entire outage was conducted with the perspective of relicensing in 2002. Areas specifically addressed included compensating efforts to preclude loss of user clientele, acquisition of data for facilitating the upcoming conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU), and development of a surveillance plan relicensing database to support the planned license renewal. In summary, this nonpower reactor facility with limited staff has been successful in all three areas.

William G. Vernetson

2000-06-04T23:59:59.000Z

192

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

How much electricity does a typical nuclear power plant generate? ... tariff, and demand charge data? How is electricity used in U.S. homes?

193

Need for process/radiochemists at nuclear power plants  

SciTech Connect

Viewgraphs are presented concerning the operating requirements for chemists at nuclear power plants. The number of positions available, job duties, and training requirements are reviewed.

Wymer, R.G.; Skrable, K.W.; Alexander, E.L.

1984-01-01T23:59:59.000Z

194

Guideline for Online Monitoring of Nuclear Power Plants: Volume 2  

Science Conference Proceedings (OSTI)

This report continues a series of guidelines that assist member utilities in developing an online monitoring (OLM) program for equipment condition assessment at nuclear power plants.

2011-12-16T23:59:59.000Z

195

MANAGING MODERNIZATION OF NUCLEAR POWER PLANT INSTRUMENTATION AND CONTROL SYSTEMS  

E-Print Network (OSTI)

Managing modernization of nuclear power plant instrumentation and control systems February 2004The originating Section of this publication in the IAEA was:

unknown authors

2003-01-01T23:59:59.000Z

196

Risk-informed incident management for nuclear power plants  

E-Print Network (OSTI)

Decision making as a part of nuclear power plant operations is a critical, but common, task. Plant management is forced to make decisions that may have safety and economic consequences. Formal decision theory offers the ...

Smith, Curtis Lee, 1966-

2002-01-01T23:59:59.000Z

197

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Supporting MELCOR calculations, Volume 6, Part 2  

SciTech Connect

To gain a better understanding of the risk significance of low power and shutdown modes of operation, the Office of Nuclear Regulatory Research at the NRC established programs to investigate the likelihood and severity of postulated accidents that could occur during low power and shutdown (LP&S) modes of operation at commercial nuclear power plants. To investigate the likelihood of severe core damage accidents during off power conditions, probabilistic risk assessments (PRAs) were performed for two nuclear plants: Unit 1 of the Grand Gulf Nuclear Station, which is a BWR-6 Mark III boiling water reactor (BWR), and Unit 1 of the Surry Power Station, which is a three-loop, subatmospheric, pressurized water reactor (PWR). The analysis of the BWR was conducted at Sandia National Laboratories while the analysis of the PWR was performed at Brookhaven National Laboratory. This multi-volume report presents and discusses the results of the BWR analysis. The subject of this part presents the deterministic code calculations, performed with the MELCOR code, that were used to support the development and quantification of the PRA models. The background for the work documented in this report is summarized, including how deterministic codes are used in PRAS, why the MELCOR code is used, what the capabilities and features of MELCOR are, and how the code has been used by others in the past. Brief descriptions of the Grand Gulf plant and its configuration during LP&S operation and of the MELCOR input model developed for the Grand Gulf plant in its LP&S configuration are given.

Kmetyk, L.N.; Brown, T.D. [Sandia National Labs., Albuquerque, NM (United States)

1995-03-01T23:59:59.000Z

198

Pantex Plant | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Locations > Pantex Plant Pantex Plant http:www.pantex.com Field Office: The NNSA Production Office is responsible for contract management and oversight of the Pantex Plant in...

199

Inspection of Nuclear Power Plant Containment Structures  

SciTech Connect

Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

Graves, H.L.; Naus, D.J.; Norris, W.E.

1998-12-01T23:59:59.000Z

200

Next Generation Nuclear Plant GAP Analysis Report  

DOE Green Energy (OSTI)

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

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

2008-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Nuclear Power Plant Fire-Modeling Applications Guide  

Science Conference Proceedings (OSTI)

This report replaces EPRI 1002981, Fire Modeling Guide for Nuclear Power Plant Applications, August 2002, as guidance for fire-modeling practitioners in nuclear power plants (NPPs). The report has benefited from insights gained since 2002 on the predictive capability of selected fire models to improve confidence in the use of fire modeling in NPP decision-making.

2009-12-22T23:59:59.000Z

202

Welding and Fabrication Critical Factors for New Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Welding and fabrication processes employed for manufacture of critical nuclear power plant components may adversely affect material performance and can potentially increase susceptibility to known degradation mechanisms. This report identifies important welding and fabrication processes for specific materials, assesses their effects on potential degradation mechanisms, and identifies process enhancements that can improve long-term asset management of new nuclear plant components.

2009-12-08T23:59:59.000Z

203

Groundwater Sampling and Analysis Sourcebook for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This sourcebook provides technical guidance and best practices for groundwater sampling and analysis at nuclear power plants. Robust sampling and analysis protocols are required to ensure accurate characterization of radionuclides in groundwater.BackgroundNuclear power plants implement groundwater protection programs to minimize contamination of on-site soil and groundwater, and to prevent the off-site migration of licensed material through groundwater ...

2012-09-25T23:59:59.000Z

204

Review of Polyimide Insulated Wire in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Because of its toughness and other desirable properties, Kapton insulated wire has been test-qualified for use in nuclear power plants; however, failures of this material in military aircraft have raised safety questions. This report identifies the conditions of proper use and handling that will ensure reliable functioning of the wire under nuclear plant operating and accident conditions.

1991-03-01T23:59:59.000Z

205

Construction or Extended Operation of Nuclear Plant (Vermont) | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Construction or Extended Operation of Nuclear Plant (Vermont) Construction or Extended Operation of Nuclear Plant (Vermont) Construction or Extended Operation of Nuclear Plant (Vermont) < Back Eligibility Investor-Owned Utility Utility Program Info State Vermont Program Type Siting and Permitting Any petition for approval of construction of a nuclear energy generating plant within the state, or any petition for approval of the operation of a nuclear energy generating plant beyond the date established in a certificate of public good issued under this title, must be submitted to the public service board no later than four years before the date upon which the approval may take effect. Upon receipt of a petition for approval of construction or operation as provided under this section, the public service board shall notify the

206

Program Change Management During Nuclear Power Plant Decommissioning  

Science Conference Proceedings (OSTI)

Decommissioning a nuclear power plant is a complex project, which involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As plants meet certain project Milestones, the evolution of such plant programs and regulations can help optimize project execution and cost. This report provides information about these Milestones and the plant departments and programs that change throughout a decommissioning project.

2009-12-11T23:59:59.000Z

207

Guidelines for Nuclear Plant Response to an Earthquake  

Science Conference Proceedings (OSTI)

Guidelines for nuclear plant response to earthquakes enable utilities to evaluate in a timely manner the need for post-earthquake plant shutdown and to provide procedures for evaluation of earthquake effects on the plant, as well as criteria for plant restart. The procedures enable the responding team of operators and engineers to identify and assess any earthquake effects and, if shutdown is necessary, to return the plant to safe operation as rapidly as possible. The guidelines presented herein ...

2013-10-15T23:59:59.000Z

208

Guidelines for Nuclear Plant Response to an Earthquake  

Science Conference Proceedings (OSTI)

Guidelines for nuclear plant response to earthquakes enable utilities to evaluate in a timely manner the need for post-earthquake plant shutdown and to provide procedures for evaluation of earthquake effects on the plant, as well as criteria for plant restart. The procedures enable the responding team of operators and engineers to identify and assess any earthquake effects and, if shutdown is necessary, to return the plant to safe operation as rapidly as possible. The guidelines presented herein ...

2012-10-11T23:59:59.000Z

209

Contingency Analysis of Cascading Line Outage Events  

SciTech Connect

As the US power systems continue to increase in size and complexity, including the growth of smart grids, larger blackouts due to cascading outages become more likely. Grid congestion is often associated with a cascading collapse leading to a major blackout. Such a collapse is characterized by a self-sustaining sequence of line outages followed by a topology breakup of the network. This paper addresses the implementation and testing of a process for N-k contingency analysis and sequential cascading outage simulation in order to identify potential cascading modes. A modeling approach described in this paper offers a unique capability to identify initiating events that may lead to cascading outages. It predicts the development of cascading events by identifying and visualizing potential cascading tiers. The proposed approach was implemented using a 328-bus simplified SERC power system network. The results of the study indicate that initiating events and possible cascading chains may be identified, ranked and visualized. This approach may be used to improve the reliability of a transmission grid and reduce its vulnerability to cascading outages.

Thomas L Baldwin; Magdy S Tawfik; Miles McQueen

2011-03-01T23:59:59.000Z

210

Some aspects of the decommissioning of nuclear power plants  

SciTech Connect

The major factors influencing the choice of a national concept for the decommissioning of nuclear power plants are examined. The operating lifetimes of power generating units with nuclear reactors of various types (VVER-1000, VVER-440, RBMK-1000, EGP-6, and BN-600) are analyzed. The basic approaches to decommissioning Russian nuclear power plants and the treatment of radioactive waste and spent nuclear fuel are discussed. Major aspects of the ecological and radiation safety of personnel, surrounding populations, and the environment during decommissioning of nuclear installations are identified.

Khvostova, M. S., E-mail: marinakhvostova@list.ru [St. Petersburg State Maritime Technical University (Sevmashvtuz), Severodvinsk Branch (Russian Federation)

2012-03-15T23:59:59.000Z

211

Financial and ratepayer impacts of nuclear power plant regulatory reform  

SciTech Connect

Three reports - ''The Future Market for Electric Generating Capacity,'' ''Quantitative Analysis of Nuclear Power Plant Licensing Reform,'' and ''Nuclear Rate Increase Study'' are recent studies performed by the Los Alamos National Laboratory that deal with nuclear power. This presents a short summary of these three studies. More detail is given in the reports.

Turpin, A.G.

1985-01-01T23:59:59.000Z

212

Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Feasibility Study of Hydrogen Production at Existing Nuclear Power Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants A funding opportunity announcement of the cost shared feasibility studies of nuclear energy based production of hydrogen using available technology. The objective of this activity is to select and conduct project(s) that will utilize hydrogen production equipment and nuclear energy as necessary to produce data and analysis on the economics of hydrogen production with nuclear energy. Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants More Documents & Publications https://e-center.doe.gov/iips/faopor.nsf/UNID/E67E46185A67EBE68 Microsoft Word - FOA cover sheet.doc Microsoft Word - hDE-FOA-0000092.rtf

213

A Dynamical Systems Model for Nuclear Power Plant Risk Management  

Science Conference Proceedings (OSTI)

This report provides a mathematical dynamical systems model of the effect of plant processes and programs on nuclear plant safety. That is, it models the safety risk management process. Responses of this model to postulated changes in performance and coupling parameters were verified to be in accordance with experience from years of commercial nuclear power plant operation. A preliminary analysis of the model was performed using the techniques of dynamical systems theory to determine regions of operation...

2003-10-31T23:59:59.000Z

214

Tenth Nuclear Plant Performance Improvement (NPPI) Seminar Proceedings  

Science Conference Proceedings (OSTI)

This report contains information presented at the Tenth Nuclear Plant Performance Improvement (NPPI) Seminar held July 15-16, 2002, in Saratoga Springs, New York. The biannual seminar -- sponsored by EPRI Plant Support Engineering (PSE), EPRI Plant Performance Enhancement Program (P2EP), and Rochester Gas and Electric -- provided an opportunity for participants to exchange technical information and experience regarding the achievement of the highest possible megawatt electric (MWe) output from nuclear po...

2002-08-15T23:59:59.000Z

215

Nuclear Power Plant Emergency Diesel Generator Tanks 1  

E-Print Network (OSTI)

Nuclear power provides about 20 % of the total electricity generated in the United States. In 2005, this was about 782 Billion kWh of the total electricity generation (EIA 2006). 2 As with fossil-fueled electricity generating plants, electricity in a nuclear power plant is produced by heated steam that drives a turbine generator. In a nuclear power plant, however, nuclear fission reactions in the core produce heat that is absorbed by a liquid that flows through the system and is converted to steam. Nuclear power plants are highly efficient and have become more so over the last 25 years. Operational efficiency (also referred to as plant performance or electricity production) can be measured by the capacity factor. The capacity factor is the ratio of the actual amount of electricity generated to the maximum possible amount that could be generated in a given period of time – usually a year. Today, nuclear power plants operate at an average 90 % capacity factor (compared to 56 % in 1980) (EIA 2006a). Thus, although nuclear generating capacity has remained roughly constant since 1990, at about 99 gigawatts (or about 10 % of the total U.S. electric generating capacity), the amount of electricity produced has increased 33 % since that time because of increased capacity utilization. Nuclear plants have the highest capacity factors of

unknown authors

2006-01-01T23:59:59.000Z

216

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plants: Industry Recommendations for Design  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries. Good initial and continued performance is vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

217

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

Science Conference Proceedings (OSTI)

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

L.E. Demick

2011-10-01T23:59:59.000Z

218

Definition: Cascading Outage | Open Energy Information  

Open Energy Info (EERE)

Cascading Outage Cascading Outage Jump to: navigation, search Dictionary.png Cascading Outage The uncontrolled successive loss of system elements triggered by an incident at any location. Cascading results in widespread electric service interruption that cannot be restrained from sequentially spreading beyond an area predetermined by studies.[1] View on Wikipedia Wikipedia Definition A cascading failure is a failure in a system of interconnected parts in which the failure of a part can trigger the failure of successive parts. Such a failure may happen in many types of systems, including power transmission, computer networking, finance and bridges. Cascading failures usually begin when one part of the system fails. When this happens, nearby nodes must then take up the slack for the failed component. This overloads

219

Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents  

Science Conference Proceedings (OSTI)

Nuclear power plants report the amount of radioactivity released through permitted effluent pathways in their plant annual reports. This report provides users with a method for calculating the amount of carbon-14 (14C) generated in a light water reactor (LWR) core and released through plant gaseous effluent pathways.

2010-12-21T23:59:59.000Z

220

Plant Engineering: Advanced Nuclear Plant Cable System Design and Installation Concepts to Assure Longevity  

Science Conference Proceedings (OSTI)

Although the electrical cable systems for existing nuclear power plants have functioned well for up to 40 years, the desired service life for new plants is 60 or more years. Experience with existing plants indicates that relatively small changes during the design and construction of nuclear plants will lead to longer cable system lives and greater ease of testing and assessment of cables to verify their remaining service life. This report describes those changes and provides recommendations for their imp...

2012-04-16T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Groundwater Protection Guidelines for Nuclear Power Plants: Revision 1  

Science Conference Proceedings (OSTI)

The United States nuclear power industry has undertaken a Groundwater Protection Initiative [NEI 07-07] at the direction of the Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC). International nuclear power plants implement groundwater protection programs to ensure appropriate management of on-site groundwater and protection of the public and environment. This Electric Power Research Institute (EPRI) guideline provides essential technical guidance to utilities on the ...

2013-10-29T23:59:59.000Z

222

Lesson 7 - Waste from Nuclear Power Plants | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7 - Waste from Nuclear Power Plants 7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing Decommissioning Lesson 7 - Waste.pptx More Documents & Publications National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

223

DOE Announces Loan Guarantee Applications for Nuclear Power Plant  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Announces Loan Guarantee Applications for Nuclear Power Plant DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it has received 19 Part I applications from 17 electric power companies for federal loan guarantees to support the construction of 14 nuclear power plants in response to its June 30, 2008 solicitation. The applications reflect the intentions of those companies to build 21 new reactors, with some applications covering two reactors at the same site. All five reactor designs that have been certified, or are currently under review for possible certification, by the Nuclear Regulatory Commission (NRC) are

224

Guidance for Deployment of Mobile Technologies for Nuclear Power Plant  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Guidance for Deployment of Mobile Technologies for Nuclear Power Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers This report is a guidance document prepared for the benefit of commercial nuclear power plants' (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel. This information is not intended to replace basic project management practices or reiterate these processes, but is to support decision-making,

225

DOE Announces Loan Guarantee Applications for Nuclear Power Plant  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Loan Guarantee Applications for Nuclear Power Plant Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it has received 19 Part I applications from 17 electric power companies for federal loan guarantees to support the construction of 14 nuclear power plants in response to its June 30, 2008 solicitation. The applications reflect the intentions of those companies to build 21 new reactors, with some applications covering two reactors at the same site. All five reactor designs that have been certified, or are currently under review for possible certification, by the Nuclear Regulatory Commission (NRC) are represented in the Part I applications. DOE also has received Part I

226

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  

E-Print Network (OSTI)

Generating Plant. The enclosed report documents the inspection findings which were discussed on February 22, 2001, with you and other members of your staff. This inspection examined activities conducted under your license as they relate to safety and compliance with the Commission’s rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, the inspectors identified two issues of very low safety significance (Green). One of these issues was determined to involve a violation of NRC requirements. However, because of its very low safety significance and because it has been entered into your corrective action program, the NRC is treating the issue as a non-cited violation, in accordance with Section VI.A.1 of the NRC’s Enforcement Policy. If you deny the non-cited violation, you should provide a response with the basis for your denial, within 30 days of the date of this inspection report, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator,

Dear Mr. Sorensen; Roger D. Lanksbury

2001-01-01T23:59:59.000Z

227

Mesoscale to plant-scale models of nuclear waste reprocessing.  

Science Conference Proceedings (OSTI)

Imported oil exacerabates our trade deficit and funds anti-American regimes. Nuclear Energy (NE) is a demonstrated technology with high efficiency. NE's two biggest political detriments are possible accidents and nuclear waste disposal. For NE policy, proliferation is the biggest obstacle. Nuclear waste can be reduced through reprocessing, where fuel rods are separated into various streams, some of which can be reused in reactors. Current process developed in the 1950s is dirty and expensive, U/Pu separation is the most critical. Fuel rods are sheared and dissolved in acid to extract fissile material in a centrifugal contactor. Plants have many contacts in series with other separations. We have taken a science and simulation-based approach to develop a modern reprocessing plant. Models of reprocessing plants are needed to support nuclear materials accountancy, nonproliferation, plant design, and plant scale-up.

Noble, David Frederick; O'Hern, Timothy John; Moffat, Harry K.; Nemer, Martin B.; Domino, Stefan Paul; Rao, Rekha Ranjana; Cipiti, Benjamin B.; Brotherton, Christopher M.; Jove-Colon, Carlos F.; Pawlowski, Roger Patrick

2010-09-01T23:59:59.000Z

228

Industry Participation Sought for Design of Next Generation Nuclear Plant |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Industry Participation Sought for Design of Next Generation Nuclear Industry Participation Sought for Design of Next Generation Nuclear Plant Industry Participation Sought for Design of Next Generation Nuclear Plant June 29, 2006 - 2:41pm Addthis Gen IV Reactor Capable of Producing Electricity and/or Hydrogen WASHINGTON, DC - The U.S. Department of Energy (DOE) is seeking expressions of interest from prospective industry teams interested in participating in the development and conceptual design for the Next Generation Nuclear Plant (NGNP), a very high temperature gas-cooled nuclear reactor prototype with the capability to produce process heat, electricity and/or hydrogen. The very high temperature reactor is based on research and development activities supported by DOE's Generation IV nuclear energy systems initiative.

229

New Jersey Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2nj Oyster Creek Unit 1 615 4,601 14.0 Exelon Nuclear PSEG Hope Creek Generating Station Unit 1 1,161 9,439 28.8 PSEG Nuclear LLC PSEG Salem Generating Station

230

Advanced Pipe Replacement Procedure for a Defective CRDM Housing Nozzle Enables Continued Normal Operation of a Nuclear Power Plant  

SciTech Connect

During the 2003 outage at the Ringhals Nuclear Plant in Sweden, a leak was found in the vicinity of a Control Rod Drive Mechanism (CRDM) housing nozzle at Unit 1. Based on the ALARA principle for radioactive contamination, a unique repair process was developed. The repair system includes utilization of custom, remotely controlled GTAW-robots, a CNC cutting and finishing machine, snake-arm robots and NDE equipment. The success of the repair solution was based on performing the machining and welding operations from the inside of the SCRAM pipe through the CRDM housing since accessibility from the outside was extremely limited. Before the actual pipe replacement procedure was performed, comprehensive training programs were conducted. Training was followed by certification of equipment, staff and procedures during qualification tests in a full scale mock-up of the housing nozzle. Due to the ingenuity of the overall repair solution and training programs, the actual pipe replacement procedure was completed in less than half the anticipated time. As a result of the successful pipe replacement, the nuclear power plant was returned to normal operation. (authors)

Gilmore, Geoff; Becker, Andrew [Climax Portable Machine Tools, Inc., 2712 East Second Street, Newberg, OR 97132 (United States)

2006-07-01T23:59:59.000Z

231

Potomac River Project Outage Schedule Clarification | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Potomac River Project Outage Schedule Clarification Potomac River Project Outage Schedule Clarification Potomac River Project Outage Schedule Clarification Docket No. EO-05-01. Order No. 202-07-02: Based on the most current information we have for both circuits, the new outage dates are listed below: Outage Duration Feeder Out April 30, 2007 - June 1, 2007 Circuit 1 June 2, 2007 - July 1, 2007 Circuit 2 Potomac River Project Outage Schedule Clarification More Documents & Publications Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac Electric Power Company (PEPCO) evised plan for transmission outages for the 230 kV circuits Notification of Planned 230kV Outage at Potomac River Generating Station PEPCO Comments on Special Environmental Analysis For Actions Taken Under U.S. Department of Energy Emergency Orders Regarding Operation of the

232

Market Assessment of Refinery Outages Planned for October 2009 ...  

U.S. Energy Information Administration (EIA)

January fuel demand with availability of the refinery process units for distillate and gasoline production net of outages.

233

A CCA-compliant nuclear power plant simulator kernel  

Science Conference Proceedings (OSTI)

This paper presents a parallel, component-oriented nuclear power plant simulator kernel. It is based on the high-performance computing oriented Common Component Architecture. The approach takes advantage of both the component paradigm and the parallel ...

Manuel Díaz; Daniel Garrido; Sergio Romero; Bartolomé Rubio; Enrique Soler; José M. Troya

2005-05-01T23:59:59.000Z

234

Mapping complexity sources in nuclear power plant domains  

E-Print Network (OSTI)

Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their effects on human reliability is critical for ensuring safe performance of both operators and the entire system. New ...

Sasangohar, Farzan

235

Indication of Potential Cascading Outages Using Measurement Data  

Science Conference Proceedings (OSTI)

Many efforts have been made to avoid blackouts in North America since 1965. However, cascading outages leading to catastrophic blackouts continued to happen. This project focused on investigating a comprehensive monitoring and control framework for prediction, analysis, and mitigation of cascading outages and conducting research on the early indication of potential cascading outages using real-time measurement data.

2010-12-21T23:59:59.000Z

236

A Preliminary Analysis of Network Outages During Hurricane Sandy  

E-Print Network (OSTI)

.2.3.*). To evaluate outages, we require that, historically, at least 10% of the addresses in the block reply to pingsA Preliminary Analysis of Network Outages During Hurricane Sandy USC/ISI Technical Report ISI, linquan, yuri}@isi.edu ABSTRACT This document describes our analysis of Internet outages during

Heidemann, John

237

Secretary Bodman Announces Federal Risk Insurance for Nuclear Power Plants  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Federal Risk Insurance for Nuclear Power Federal Risk Insurance for Nuclear Power Plants & Touts Robust Economy Secretary Bodman Announces Federal Risk Insurance for Nuclear Power Plants & Touts Robust Economy August 4, 2006 - 8:42am Addthis ATLANTA, GA - After touring Georgia Power and speaking to its employees, U.S. Department of Energy (DOE) Secretary Samuel W. Bodman today announced completion of the final rule that establishes the process for utility companies building the next six new nuclear power plants in the United States to qualify for a portion of $2 billion in federal risk insurance. The rule will be available on DOE's web site soon. "Providing federal risk insurance is an important step in speeding the nuclear renaissance in this country," Secretary Bodman said. "Companies

238

Training Module for Cyber Security in Nuclear Plant Digital Modifications  

Science Conference Proceedings (OSTI)

Nuclear power plants face increasing regulatory requirements from the U.S. Nuclear Regulatory Commission (NRC) and the Federal Energy Regulatory Commission (FERC) for cyber security of digital devices, components, and systems. The focus of these cyber security requirements is to protect plant digital computer systems, communications systems, and networks from cyber attacks that would affect reactor safety or generation reliability. This Electric Power Research Institute (EPRI) computer-based training mod...

2011-04-28T23:59:59.000Z

239

Advanced Sensor Diagnostics in Nuclear Power Plant Applications  

NLE Websites -- All DOE Office Websites (Extended Search)

Sensor Diagnostics in Nuclear Power Plant Applications Sensor Diagnostics in Nuclear Power Plant Applications R.B. Vilim Argonne National Laboratory Sensor degradation occurs routinely during nuclear power plant operation and can contribute to reduced power production and less efficient plant operation. Mechanisms include drift of sensor electronics and mechanical components, fouling and erosion of flow meter orifice plates, and general degradation of thermocouples. One solution to this problem is the use of higher quality instrumentation and of physical redundancy. This, however, increases plant cost and does not address the degradation problem in a fundamental way. An alternative approach is to use signal processing algorithms to detect a degraded sensor and to construct a replacement value using an

240

Pepco Update on Current Construction Work and Mirant Generation Needs for Pepco's Planned June Line Outage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

May 25, 2007 May 25, 2007 Kevin Kolevar Director of the Office of Electricity Deliverability and Energy Reliability Department of Energy 1000 Independence Ave., SW Washington, DC 20585 Dear Mr. Kolevar, DOE has requested that Pepco provide an update on the current work to install two new 230 kilovolt circuits into Potomac River substation and to evaluate the need for generation from the Potomac River plant to support the anticipated line outage during June, 2007. An outage on one of the 230 kV circuits is currently underway and is currently scheduled to be completed by June 2, 2007. Mirant has supported this outage with generation required to match the Potomac River area load from the substation. This has required the operation of all 5 generating units located at

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Y-12 PLANT NUCLEAR SAFETY HANDBOOK  

SciTech Connect

Information needed to solve nuclear safety problems is condensed into a reference book for use by persons familiar with the field. Included are a glossary of terms; useful tables; nuclear constants; criticality calculations; basic nuclear safety limits; solution geometries and critical values; metal critical values; criticality values for intermediate, heterogeneous, and interacting systems; miscellaneous and related information; and report number, author, and subject indexes. (C.H.)

Wachter, J.W. ed.; Bailey, M.L.; Cagle, T.J.; Mee, W.T.; Pletz, R.H.; Welfare, F.G.; Youngblood, B.J. comps

1963-03-27T23:59:59.000Z

242

Assessment of Electromagnetic Interference Events in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report presents a study and analysis of reported electromagnetic interference (EMI-) related incidents in nuclear power plants. These incidents were gathered primarily from the total body of incidents reported to the Institute of Nuclear Power Operations (INPO) database, with a few incidents coming from U.S. Nuclear Regulatory Commission (NRC) reports. This report analyzes trends and common factors in these events. The analysis is intended to inform the estimation of risk from EMI and offer suggesti...

2011-12-23T23:59:59.000Z

243

Qinshan: China`s first nuclear power plant  

SciTech Connect

Plant design, startup, and operation of the Qinshan-1 nuclear power plant in China are outlined in this article. Qinshan-1 is a 300 MW(e) pressurized water reactor designed and constructed in China. Approximately 70 percent of the equipment was also made in China. Findings of a preoperational safety inspection by the International Atomic Energy Agency are summarized.

NONE

1992-08-01T23:59:59.000Z

244

Life Expectancy of Motors in Mild Nuclear Plant Environments  

Science Conference Proceedings (OSTI)

Predicted life expectancies of commercial-grade motors used in the milder environments of nuclear power plants indicate that those motors can last for the life of the plant if properly maintained. This report details methods by which utilities can make such predictions and supplies the extensive data on which the analytic techniques are based.

1985-02-21T23:59:59.000Z

245

Data Mining for Monitoring Loose Parts in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Monitoring the mechanical impact of a loose (detached or drifting) part in the reactor coolant system of a nuclear power plant is one of the essential functions for operation and maintenance of the plant.Large data tables are generated during this monitoring ...

J. W. Guan; David A. Bell

2000-10-01T23:59:59.000Z

246

Atmospheric Deposition of Tritium at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Tritium source terms at nuclear power plants consist of several sources that include plant vents and cooling impoundments, cooling towers, and treatment ponds. Cooling lakes and reservoirs can be sources of airborne tritium. Methods are presented for estimating these source terms and predicting resulting deposition of tritium using metrological models and for estimating infiltration of tritium using hydrogeological models.

2010-12-16T23:59:59.000Z

247

Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The nuclear power industry has undertaken a Groundwater Protection Initiative at the Direction of the NEI Nuclear Strategic Issues Advisory Committee (NSIAC). This EPRI guideline provides essential technical guidance to utilities on the necessary elements of a sound groundwater protection program.

2007-11-27T23:59:59.000Z

248

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

U. S. Conunercial Nuclear Power Plants", Report WASH-1400 (for Light-Water Cooled Nuclear Power Plants to Assess PlantStandards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

249

Calibration of Radiation Monitors at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Radiation monitors are installed in nuclear power plants to indicate to operators the levels of radioactivity in various processes and at specific plant locations. Plant personnel depend on radiation monitors for accurate and precise data in order to make informed decisions and take appropriate actions during normal, abnormal, and design basis events. As with all electronic measurement systems, error can be introduced by changing environmental conditions, aging components, and replaced parts. The radiati...

2005-12-22T23:59:59.000Z

250

Potomac River Project Outage Schedule Clarification | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

River Project Outage Schedule Clarification River Project Outage Schedule Clarification Potomac River Project Outage Schedule Clarification Docket No. EO-05-01. Order No. 202-07-02: Based on the most current information we have for both circuits, the new outage dates are listed below: Outage Duration Feeder Out April 30, 2007 - June 1, 2007 Circuit 1 June 2, 2007 - July 1, 2007 Circuit 2 Potomac River Project Outage Schedule Clarification More Documents & Publications Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac Electric Power Company (PEPCO) evised plan for transmission outages for the 230 kV circuits PEPCO Comments on Special Environmental Analysis For Actions Taken Under U.S. Department of Energy Emergency Orders Regarding Operation of the Potomac River Generating Station in Alexandria, Virginia

251

North American Electric Reliability Council Power Outage Update |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Power Outage Update Power Outage Update North American Electric Reliability Council Power Outage Update The bulk electric transmission system in the United States and Canada has been restored and is operating reliably. Many of the generating units that tripped off line during the outage have returned to service and additional generating units are expected to return to service over the weekend. Virtually all customers have been returned to electric service, although some customers will continue to experience rotating outages due to generating capacity availability. North American Electric Reliability Council Power Outage Update More Documents & Publications Electric System Update: Sunday August 17, 2003 North American Electric Reliability Council Outage Announcement NORTH AMERICAN ELECTRIC RELIABILITY COUNCIL: Preliminary Disturbance Report

252

Nuclear plant owners move closer to life extension  

Science Conference Proceedings (OSTI)

A major debate is now underway about the safety of 40-year-old nuclear power plants. Under the Atomic Energy Act of 1954 a nuclear power plant's license is limited to a maximum of 40 years. Although the act permits the renewal of an operating license, it does not outline any standards or procedures for determining when or under what conditions a plant's operating license should be renewed. This paper reports that the Electric Power Research Institute (EPRI) and the U.S. Department of Energy (DOE) are co-sponsors of a program to demonstrate the license renewal process for two nuclear power plants - Yankee Atomic Electric's 175-MW Yankee PWR plant and Northern States Power's 536-MW Monticello BWR plant. The demonstration is known as the lead plant project. Yankee Atomic has already analyzed the plant's condition and evaluated aging using computer-based expert systems and the plant's operating experience. During these tests Yankee Atomic found embrittlement of the reactor vessel.

Smith, D.J.

1991-10-01T23:59:59.000Z

253

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts associated with the U.S. Department of Energy proposed action to conduct a lead test assembly program to confirm the viability of using a commercial light water reactor to produce tritium. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 22, 1997 EA-1210: Finding of No Significant Impact Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington July 22, 1997 EA-1210: Final Environmental Assessment

254

How many nuclear power plants are in the U.S. and where are they ...  

U.S. Energy Information Administration (EIA)

How many nuclear power plants are in the U.S. and where are they located? There are currently 65 commercially operating nuclear power plants with 104 nuclear reactors ...

255

RESOLVED: Projectb filesystem outage July 9, 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

RESOLVED: Projectb filesystem outage July 9, 2012 RESOLVED: Projectb filesystem outage July 9, 2012 RESOLVED: Projectb filesystem outage July 9, 2012 July 9, 2012 (0 Comments) The projectb filesystem had a hardware failure that potentially generated I/O errors. The filesystem logs indicate that the earliest abnormal event on the filesystem occurred at 9:19AM and the filesystem was taken down for maintenance at 10:42AM. The filesystem returned to service at 11:20AM. Jobs running on the cluster would not have been able to read from or write to the projectb filesystem between 10:42AM and 11:20AM. Between 9:19AM and 10:42AM one out of the 20 GPFS controllers on projectb was down, and didn't failover (as it should have). This means: 1/20 file I/O operations could have failed between 9:19AM and 10:42AM If your job was performing a large number of short reads and writes, then

256

The Next Generation Nuclear Plant (NGNP) Project  

DOE Green Energy (OSTI)

The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOE’s project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10 CFR 52, for the purpose of demonstrating the suitability of high-temperature gas-cooled reactors for commercial electric power and hydrogen production. Products that will support the licensing of the NGNP include the environmental impact statement, the preliminary safety analysis report, the NRC construction permit, the final safety analysis report, and the NRC operating license. The fuel development and qualification program consists of five elements: development of improved fuel manufacturing technologies, fuel and materials irradiations, safety testing and post-irradiation examinations, fuel performance modeling, and fission product transport and source term modeling. Two basic approaches will be explored for using the heat from the high-temperature helium coolant to produce hydrogen. The first technology of interest is the thermochemical splitting of water into hydrogen and oxygen. The most promising processes for thermochemical splitting of water are sulfur-based and include the sulfur-iodine, hybrid sulfur-electrolysis, and sulfur-bromine processes. The second technology of interest is thermally assisted electrolysis of water. The efficiency of this process can be substantially improved by heating the water to high-temperature steam before applying electrolysis.

F. H. Southworth; P. E. MacDonald

2003-11-01T23:59:59.000Z

257

Nuclear dual-purpose plants for industrial energy  

SciTech Connect

One of the major obstacles to extensive application of nuclear power to industrial heat is the difference between the relatively small energy requirements of individual industrial plants and the large thermal capacity of current power reactors. A practical way of overcoming this obstacle would be to operate a centrally located dual-purpose power plant that would furnish process steam to a cluster of industrial plants, in addition to generating electrical power. The present study indicates that even relatively remote industrial plants could be served by the power plant, since it might be possible to convey steam economically as much as ten miles or more. A survey of five major industries indicates a major potential market for industrial steam from large nuclear power stations.

Klepper, O.H.

1976-01-01T23:59:59.000Z

258

Advanced Cooling Options for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Alternative power plant cooling systems exist that offer significant opportunity for reducing the amount of water used in power plant cooling. These systems include direct dry cooling using air-cooled condensers, indirect dry cooling using air-cooled heat exchangers paired with water-cooled surface condensers, and a variety of hybrid systems incorporating both dry and wet cooling elements. The water savings afforded by the use of these systems, however, comes at a price in the form of more expensive ...

2013-11-27T23:59:59.000Z

259

Summary of Market Assessment of Upcoming Planned Refinery Outages  

Gasoline and Diesel Fuel Update (EIA)

Summary of Market Assessment of Upcoming Planned Refinery Outages Summary of Market Assessment of Upcoming Planned Refinery Outages Summary of Market Assessment of Upcoming Planned Refinery Outages Market Assessment of Upcoming Planned Refinery Outages, December 2008 - March 2009 reviews planned U.S. refinery outages from December 2008 though March 2009 in order to identify any regions where outages might create enough supply pressure to impact prices significantly. As required under Section 804 of the Energy Independence and Security Act of 2007 (Pub. L. 110-140), this report reviews the supply implications of planned refinery outages for December 2008 through March 2009, which covers the winter period when demand for distillate fuels (diesel and heating oil) is high. As a result, emphasis in this report is on distillate rather than gasoline. Refinery outages are the result of planned maintenance and unplanned outages. Maintenance is usually scheduled during the times when demand is lowest - in the first quarter and again in the fall. Unplanned outages, which occur for many reasons including mechanical failures, fires, and flooding, can occur at any time.

260

Nuclear safety surveillance and control of National Nuclear Safety Administration of PRC during commissioning and operation of nuclear power plants  

Science Conference Proceedings (OSTI)

This article describes the method of nuclear safety surveillance and control of National Nuclear Safety Administration (NNSA) of PRC during commissioning and operation of nuclear power plants (NPPs) and the practice for Qinshan NPP and for Guangdong Daya Bay NPP (GNPS). The results of the practice show that the surveillance models set up for Qinshan NPP and for GNPS commissioning were effective and the surveillance has played an important role for ensuring the quality and safety of the commissioning testing and consequently the nuclear safety of these two plants.

Feng, W.; Zhang, C.

1994-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Plant layup and equipment preservation sourcebook: Interim report  

Science Conference Proceedings (OSTI)

US nuclear generating plant systems and equipment have received very sophisticated chemistry and environmental controls during operation, but very little during construction and outages. As plant construction times became longer, and operating plants experienced outages of significant length, the component damage and system contamination occurring during this idle time has become greater, to the extent that plant startup schedules or the ability to keep the plant operational are sometimes affected. This has led to limited efforts in the industry to control component internal chemistry and environment by planned lay-up procedures. These efforts have been thwarted by a lack of information on how to do equipment lay-ups, and a lack of data base to quantify the value of various lay-up techniques. EPRI authorized the preparation of this sourcebook as part of a research program, RP2815-1, with the goal of providing a convenient and unified source of plant lay-up information.

Mentink, H.W.; Hagan, K.A.; Lovett, C.G.

1987-03-01T23:59:59.000Z

262

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plant Projects: Industry Recommendations for Storage, Construction, and Testing  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries and vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

263

Nuclear Power Plant Containment Pressure Boundary Research  

SciTech Connect

Research to address aging of the containment pressure boundary in light-water reactor plants is summarized. This research is aimed at understanding the significant factors relating occurrence of corrosion, efficacy of inspection, and structural capacity reduction of steel containment and liners of concrete containment. This understanding will lead to improvements in risk-informed regulatory decision making. Containment pressure boundary components are described and potential aging factors identified. Quantitative tools for condition assessments of aging structures to maintain an acceptable level of reliability over the service life of the plant are discussed. Finally, the impact of aging (i.e., loss of shell thickness due to corrosion) on steel containment fragility for a pressurized water reactor ice-condenser plant is presented.

Cherry, J.L.; Chokshi, N.C.; Costello, J.F.; Ellingwood, B.R.; Naus, D.J.

1999-09-15T23:59:59.000Z

264

Effect of Nuclear Power Plant Decommissioning Costs on Plant Life Cycle Decisions  

Science Conference Proceedings (OSTI)

Nuclear utilities implementing Life Cycle Management (LCM) Programs and facing run-relicense-retire decisions need to evaluate the financial cost/benefit of such decisions. Decommissioning costs are one element of these evaluations. This report includes a decommissioning cost estimate for Calvert Cliffs Nuclear Power Plant (CCNPP) that can be used as a reference source by nuclear utilities involved in LCM and license renewal (LR) decisions.

1995-07-01T23:59:59.000Z

265

Plant Engineering: Predicting Nuclear Plant Output from Performance Losses and Gains  

Science Conference Proceedings (OSTI)

The marginal costs of generating electricity, together with the strong emphasis on maximizing production at today's nuclear power generating units, have increased the need for nuclear plant thermal performance engineers (TPEs) to determine the gap between the station's actual performance and its ultimate capability. This report from the Electric Power Research Institute (EPRI) outlines the various items that influence the performance of a nuclear unit and gives the TPE methods to employ in estimating the...

2011-12-15T23:59:59.000Z

266

Program on Technology Innovation: The Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This Technology Update documents the Next Generation Nuclear Plant (NGNP) project, which will demonstrate the design, licensing, construction, and operation of a new nuclear energy source using high-temperature gas-cooled reactor (HTGR) technology. This new non-emitting energy source is applicable to a broad range of uses, from generating electricity to providing high-temperature industrial process heat to producing hydrogen. The NGNP project is sponsored as part of the Energy Policy Act of 2005 and envi...

2008-12-15T23:59:59.000Z

267

Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG)  

Science Conference Proceedings (OSTI)

There is a movement to introduce risk-informed and performance-based (RI/PB) analyses into fire protection engineering practice, both domestically and worldwide.  This movement exists in both the general fire protection and the nuclear power plant (NPP) fire protection communities.  The U.S. Nuclear Regulatory Commission (NRC) has used risk-informed insights as a part of its regulatory decision making since the 1990s.In 2001, the National Fire Protection Association (NFPA) ...

2012-11-30T23:59:59.000Z

268

Materials Handbook for Nuclear Plant Pressure Boundary Applications (2013)  

Science Conference Proceedings (OSTI)

Utility engineers require accurate structural materials properties and performance data to make decisions regarding the adequacy of materials for nuclear power applications. To meet this need, the Electric Power Research Institute (EPRI) publishes the Materials Handbook for Nuclear Plant Pressure Boundary Applications, which has been updated and revised since its initial publication in 1998. The primary focus of the handbook is on pressure boundary materials such as those used for piping ...

2013-03-28T23:59:59.000Z

269

Toshiba's developments on construction techniques of nuclear power plants  

SciTech Connect

Reliable and economic energy supplies are fundamental requirements of energy policies in Japan. To accomplish these needs, nuclear power plants are being increased in Japan. In recent years, construction cost increases and schedule extensions have affected the capital cost of nuclear energy, compared with fossil power plants, due to lower costs of oil and coal. On the other hand, several severe regulations have been applied to nuclear power plant designs. High-quality and cooperative engineering and harmonized design of equipment and parts are strongly required. Therefore, reduced construction costs and scheduling, as well as higher quality and reliability, are the most important items for nuclear industry. Toshiba has developed new construction techniques, as well as design and engineering tools for control and management, that demonstrate the positive results achieved in the shorter construction period of 1100-MW(electric) nuclear power plants. The normal construction period so far is 64 months, whereas the current construction period is 52 months. (New construction techniques are partially applied). In future years, the construction period will be lowered to 48 months. (New construction techniques are fully applied). A construction period is defined as time from the start of rock inspection to the start of commercial operation.

Hayashi, Y.; Itoh, N.

1987-01-01T23:59:59.000Z

270

Report on aging of nuclear power plant reinforced concrete structures  

Science Conference Proceedings (OSTI)

The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

Naus, D.J.; Oland, C.B. [Oak Ridge National Lab., TN (United States); Ellingwood, B.R. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

1996-03-01T23:59:59.000Z

271

Fire models for assessment of nuclear power plant fires  

SciTech Connect

This paper reviews the state-of-the-art in available fire models for the assessment of nuclear power plants fires. The advantages and disadvantages of three basic types of fire models (zone, field, and control volume) and Sandia's experience with these models will be discussed. It is shown that the type of fire model selected to solve a particular problem should be based on the information that is required. Areas of concern which relate to all nuclear power plant fire models are identified. 17 refs., 6 figs.

Nicolette, V.F.; Nowlen, S.P.

1989-01-01T23:59:59.000Z

272

A methodology for evaluating ``new`` technologies in nuclear power plants  

SciTech Connect

As obsolescence and spare parts issues drive nuclear power plants to upgrade with new technology (such as optical fiber communication systems), the ability of the new technology to withstand stressors present where it is installed needs to be determined. In particular, new standards may be required to address qualification criteria and their application to the nuclear power plants of tomorrow. This paper discusses the failure modes and age-related degradation mechanisms of fiber optic communication systems, and suggests a methodology for identifying when accelerated aging should be performed during qualification testing.

Korsah, K.; Clark, R.L.; Holcomb, D.E.

1994-06-01T23:59:59.000Z

273

Next Generation Nuclear Plant Materials Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

G. O. Hayner; E.L. Shaber

2004-09-01T23:59:59.000Z

274

MIMO ARQ with Multi-bit Feedback: Outage Analysis  

E-Print Network (OSTI)

We study the asymptotic outage performance of incremental redundancy automatic repeat request (INR-ARQ) transmission over the multiple-input multiple-output (MIMO) block-fading channels with discrete input constellations. We first show that transmission with random codes using a discrete signal constellation across all transmit antennas achieves the optimal outage diversity given by the Singleton bound. We then analyze the optimal SNR-exponent and outage diversity of INR-ARQ transmission over the MIMO block-fading channel. We show that a significant gain in outage diversity is obtained by providing more than one bit feedback at each ARQ round. Thus, the outage performance of INR-ARQ transmission can be remarkably improved with minimal additional overhead. A suboptimal feedback and power adaptation rule, which achieves the optimal outage diversity, is proposed for MIMO INR-ARQ, demonstrating the benefits provided by multi-bit feedback.

Nguyen, Khoa D; Fabregas, Albert Guillen i; Letzepis, Nick

2010-01-01T23:59:59.000Z

275

Definition: Outage Detection/Reporting | Open Energy Information  

Open Energy Info (EERE)

Outage Detection/Reporting Outage Detection/Reporting Jump to: navigation, search Dictionary.png Outage Detection/Reporting A system utilizing smart meters and AMI that can notify a utility of customer power outages when the power to meters is interrupted. Generally speaking, this can be done by utilizing meters that can send a "last gasp" signal to the head-end system upon losing power, or by periodically polling meters to check status.[1] Related Terms power, advanced metering infrastructure, system References ↑ https://www.smartgrid.gov/category/technology/outage_detectionreporting [[Cat Like Like You like this.Sign Up to see what your friends like. egory: Smart Grid Definitionssmart grid,smart grid, |Template:BASEPAGENAME]]smart grid,smart grid, Retrieved from "http://en.openei.org/w/index.php?title=Definition:Outage_Detection/Reporting&oldid=502576

276

Liquid metal cooled nuclear reactor plant system  

DOE Patents (OSTI)

A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting for fuel decay during reactor shutdown, or heat produced during a mishap. The reactor system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the reactor vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.

Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

1993-01-01T23:59:59.000Z

277

Radiation Protection Program Resource Optimization Project; Brunswick Nuclear Plant  

Science Conference Proceedings (OSTI)

Radiation protection (RP) managers face challenges in providing a necessary service that complies with stringent regulations, while simultaneously reducing operations and maintenance (O&M) costs. The results of this pilot project, hosted by Brunswick Nuclear Plant (BNP), will assist utilities in targeting resource commitments and cost effectiveness while optimizing overall performance. This report identifies specific program cost reduction and process performance enhancements for the host plant, and esta...

2002-11-18T23:59:59.000Z

278

Optimization of Auxiliaries Consumption in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Operators of nuclear power plants face significant challenges to produce power more cost-effectively. One approach to producing power more cost-effectively is to reduce power consumption by auxiliary systems in the plant, leading to more power available for the grid. This report provides guidance for assessing auxiliary system performance and recommends approaches to reduce their power consumption. The report also presents results from questionnaires on auxiliary system consumption and, in some cases, ac...

2005-02-08T23:59:59.000Z

279

Plant Support Engineering: Guidance for Replacing Feedwater Heaters at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities continue to pursue license renewal applications and power uprates, and these initiatives are being undertaken in an aging fleet of nuclear plants. Many plants are facing the necessity of replacing feedwater heaters to support these initiatives. However, industry expertise to support such activities has diminished since the days of plant construction8212there are fewer qualified vendors and equipment manufacturers, materials might have changed, and licensees are typically not staffed for these m...

2007-07-26T23:59:59.000Z

280

Plant Support Engineering: Guidance for Replacing Inverters and Battery Chargers at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities are continuing to pursue license renewal applications and power uprates, and these initiatives are being undertaken on an aging fleet of nuclear plants. Many plants must replace inverters and battery chargers to support these initiatives. However, industry expertise to support such activities has diminished since the days of plant constructionthere are fewer qualified vendors and equipment manufacturers, materials have changed in many cases, and licensees are typically not currently staffed for...

2008-10-29T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Plant Support Engineering: Guidance for Planned Replacement of Large Power Transformers at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities continue to pursue license renewal applications and power uprates, and these initiatives are being undertaken on an aging fleet of nuclear plants. Many plants are facing the necessity of replacing large power transformers to support these initiatives. However, industry expertise to support such activities has diminished since the days of plant construction8212there are fewer qualified vendors and equipment manufacturers, materials and standards might have changed, and licensees are typically no...

2007-11-02T23:59:59.000Z

282

Aging assessment of large electric motors in nuclear power plants  

Science Conference Proceedings (OSTI)

Large electric motors serve as the prime movers to drive high capacity pumps, fans, compressors, and generators in a variety of nuclear plant systems. This study examined the stressors that cause degradation and aging in large electric motors operating in various plant locations and environments. The operating history of these machines in nuclear plant service was studied by review and analysis of failure reports in the NPRDS and LER databases. This was supplemented by a review of motor designs, and their nuclear and balance of plant applications, in order to characterize the failure mechanisms that cause degradation, aging, and failure in large electric motors. A generic failure modes and effects analysis for large squirrel cage induction motors was performed to identify the degradation and aging mechanisms affecting various components of these large motors, the failure modes that result, and their effects upon the function of the motor. The effects of large motor failures upon the systems in which they are operating, and on the plant as a whole, were analyzed from failure reports in the databases. The effectiveness of the industry`s large motor maintenance programs was assessed based upon the failure reports in the databases and reviews of plant maintenance procedures and programs.

Villaran, M.; Subudhi, M. [Brookhaven National Lab., Upton, NY (United States)

1996-03-01T23:59:59.000Z

283

Enhancing Cross-Correlation Analysis with Artificial Neural Networks for Nuclear Power Plant Feedwater Flow Measurement  

Science Conference Proceedings (OSTI)

One of the primary cost-saving objectives of the power plant industry, including the nuclear industry, has long been the efficient operation of plant systems. Since the maximum operating thermal power of any nuclear plant is bounded by the specific licensing ... Keywords: flow measurement, neural networks, nuclear power plant

Davide Roverso; Da Ruan

2004-05-01T23:59:59.000Z

284

Carbon-14 Dose Calculation Methods at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Carbon-14 (C-14) is a naturally occurring isotope of carbon produced by cosmic radiation interactions in the upper atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. C-14 is released through permitted effluent pathways of a nuclear power plant. This report provides the current industry best...

2012-04-26T23:59:59.000Z

285

Peach Bottom and Vermont Yankee Nuclear Power Plants  

Science Conference Proceedings (OSTI)

A dramatic and extraordinary instance of state and local government control of nuclear power, the purchase by New York of the Shoreham plant is nonetheless indicative of the political demands that some states confront for additional involvement in the regulation of the radiological hazards associated with commercial nuclear power plants. Although the Supreme Court has appeared to expand, in the eight years since PG&E and Silkwood, the acceptable extent of state regulation, some states, in addition to New York, have acquired, with the acquiescence of the NRC, a degree of involvement that exceeds the role for state and local governments provided by the Court. For example, the Commonwealth of Pennsylvania concluded with the Philadelphia Electric Company (PECO) in June 1989 an agreement that commits PECO to various initiatives, not otherwise required under NRC regulations, for the safe operation of the Peach Bottom nuclear power plant in Pennsylvania. In July 1991 the State of Vermont and Vermont Yankee Nuclear Power Corporation (Vermont Yankee) concluded an agreement similar to that concluded between Pennsylvania and PECO. The agreement also commits Vermont Yankee to certain initiatives, not otherwise required under NRC regulations, related to its operation of the Vermont Yankee nuclear power plant in Vermont. The agreement was precipitated by a challenge to an application, submitted to the NRC by Vermont Yankee in April 1989, to amend the Vermont Yankee plant license to extend its expiration date from December 11, 2007 to March 21, 2012. The amendment would allow the Vermont Yankee plant to operate for forty full years.

NONE

1992-12-31T23:59:59.000Z

286

Market Assessment of Refinery Outages Planned for October 2010 ...  

U.S. Energy Information Administration (EIA)

distillation and FCC unit outages are projected to be at typical to above typical levels in the second half of 2010, with some months significantly above average in ...

287

Market Assessment of Refinery Outages Planned for March 2010 ...  

U.S. Energy Information Administration (EIA)

DOE/EIA-0641(2010)/1 Market Assessment of Refinery Outages Planned for March 2010 through June 2010 March 2010 Energy Information Administration

288

Power outages often spur questions around burying power lines ...  

U.S. Energy Information Administration (EIA)

Smart grid technology, which would allow a utility to pinpoint problems, divert power through other circuits to minimize outages, and optimize crew deployments is ...

289

Application of Nuclear Energy for Seawater Desalination: Design Concepts of Nuclear Desalination Plants  

SciTech Connect

Nuclear energy is playing an important role in electricity generation, producing 16% of the world's electricity. However, most of the world's energy consumption is in the form of heat, in which case nuclear energy could also play an important role. In particular, process heat for seawater desalination using nuclear energy has been of growing interest to some Member States of the International Atomic Energy Agency over the past two decades. This growing interest stems from increasingly acute freshwater shortages in many arid and semi-arid zones around the world. Indeed, several national and international nuclear desalination demonstration programs are already under way or being planned. Of particular interest are projects for seawater nuclear desalination plants in coastal regions, where saline feed water can serve the dual purpose of cooling water for the nuclear reactor and as feed water for the desalination plant. In principle any nuclear reactor can provide energy (low-grade heat and/or electricity), as required by desalination processes. However, there are some additional requirements to be met under specific conditions in order to introduce nuclear desalination. Technical issues include meeting more stringent safety requirements (nuclear reactors themselves and nuclear-desalination integrated complexes in particular), and performance improvement of the integrated systems. Economic competitiveness is another important factor to be considered for a broader deployment of nuclear desalination. For technical robustness and economic competitiveness a number of design variants of coupling configurations of nuclear desalination integrated plant concepts are being evaluated. This paper identifies and discusses various factors, which support the attractiveness of nuclear desalination. It further summarizes some of the key approaches recommended for nuclear desalination complex design and gives an overview of various design concepts of nuclear desalination plants, which are experienced, being implemented or evaluated by several IAEA Member States. Operating experience with nuclear desalination using a liquid-metal reactor BN-350 in Kazakhstan and several Pressurized Water Reactor units in Japan is discussed. Results of economic analyses of nuclear desalination are also presented in order to illustrate the competitiveness of this technology with other conventional desalination operations. (authors)

Faibish, R.S.; Konishi, T.; Gasparini, M. [International Atomic Energy Agency - IAEA, P.O. Box 100, Wagramer Strasse 5, A-1400 Vienna (Austria)

2002-07-01T23:59:59.000Z

290

PM-1 NUCLEAR POWER PLANT PROGRAM PARAMETRIC STUDY REPORT  

SciTech Connect

The study deals with narrowing the range of parameters prior to preliminary design of the PM-1, a factory prepackaged, air-transportable, pressurized water nuclear power plant. The plant is to produce 1000 kw of net electrical power and 7 x 10/sup 6/ Btu/hr of space heat that is suitable for use with a central heating system. The data and conclusions resulting from the parametric study will provide the basis for the preliminary design of the PM-1 power plant. (W.D.M.)

Sieg, J.S.

1959-09-01T23:59:59.000Z

291

Radioactive Effluents from Nuclear Power Plants Annual Report 2008  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

292

Radioactive Effluents from Nuclear Power Plants Annual Report 2007  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

293

Is natural background or radiation from nuclear power plants leukemogenic  

SciTech Connect

The objective in this review is to provide some facts about normal hemopoietic cell proliferation relevant to leukemogenesis, physical, chemical, and biological facts about radiation effects with the hope that each person will be able to decide for themselves whether background radiation or emissions from nuclear power plants and facilities significantly add to the spontaneous leukemia incidence. 23 refs., 1 tab.

Cronkite, E.P.

1989-01-01T23:59:59.000Z

294

Delays in nuclear power plant construction. Volume II. Final report  

SciTech Connect

The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity.

Mason, G.E.; Larew, R.E.; Borcherding, J.D.; Okes, S.R. Jr.; Rad, P.F.

1977-12-14T23:59:59.000Z

295

Radiation Data for Design and Qualification of Nuclear Plant Equipment  

Science Conference Proceedings (OSTI)

Graphic summaries in this report represent the most comprehensive collection to date of data on the degrading effects of radiation on organic materials used in nuclear plant equipment. The data, which can help designers in selecting radiation-resistant materials, can also help in qualifying equipment at minimum cost.

1985-08-01T23:59:59.000Z

296

Nuclear Plant Reliability: Data Collection and Usage Guide  

Science Conference Proceedings (OSTI)

Most nuclear utility programs and regulatory compliance actions involve several organizations within a utility and often have overlapping elements. Nearly all of these programs need extensive data. This report discusses some issues associated with the identification, collection, and effective use of plant data in support of such utility programs.

1992-07-14T23:59:59.000Z

297

Online Monitoring of Plant Assets in the Nuclear Industry  

SciTech Connect

Today’s online monitoring technologies provide opportunities to perform predictive and proactive health management of assets within many different industries, in particular the defense and aerospace industries. The nuclear industry can leverage these technologies to enhance safety, productivity, and reliability of the aging fleet of existing nuclear power plants. The U.S. Department of Energy’s Light Water Reactor Sustainability Program is collaborating with the Electric Power Research Institute’s (EPRI’s) Long-Term Operations program to implement online monitoring in existing nuclear power plants. Proactive online monitoring in the nuclear industry is being explored using EPRI’s Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software, a set of web-based diagnostic and prognostic tools and databases that serves as an integrated health monitoring architecture. This paper focuses on development of asset fault signatures used to assess the health status of generator step-up transformers and emergency diesel generators in nuclear power plants. Asset fault signatures describe the distinctive features based on technical examinations that can be used to detect a specific fault type. Fault signatures are developed based on the results of detailed technical research and on the knowledge and experience of technical experts. The Diagnostic Advisor of the FW-PHM Suite software matches developed fault signatures with operational data to provide early identification of critical faults and troubleshooting advice that could be used to distinguish between faults with similar symptoms. This research is important as it will support the automation of predictive online monitoring techniques in nuclear power plants to diagnose incipient faults, perform proactive maintenance, and estimate the remaining useful life of assets.

Nancy Lybeck; Vivek Agarwal; Binh Pham; Richard Rusaw; Randy Bickford

2013-10-01T23:59:59.000Z

298

Reprocessing of nuclear fuels at the Savannah River Plant  

Science Conference Proceedings (OSTI)

For more than 30 years, the Savannah River Plant (SRP) has been a major supplier of nuclear materials such as plutonium-239 and tritium-3 for nuclear and thermonuclear weapons, plutonium-238 for space exploration, and isotopes of americium, curium, and californium for use in the nuclear research community. SRP is a complete nuclear park, providing most of the processes in the nuclear fuel cycle. Key processes involve fabrication and cladding of the nuclear fuel, target, and control assemblies; rework of heavy water for use as reactor moderator; reactor loading, operation, and unloading; chemical recovery of the reactor transmutation products and spent fuels; and management of the gaseous, liquid, and solid nuclear and chemical wastes; plus a host of support operations. The site's history and the key processes from fabrication of reactor fuels and targets to finishing of virgin plutonium for use in the nuclear weapons complex are reviewed. Emphasis has been given to the chemistry of the recovery and purification of weapons grade plutonium from irradiated reactor targets.

Gray, L.W.

1986-10-04T23:59:59.000Z

299

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

~ ties Surrounding Nuclear Power Plants. LBlr5921, Lawrencein U. S. Commercial Nuclear Power Plants. WASH-1400. Octoberand Content of for Nuclear Power Plants. Regulatory Guide

Yen, W.W.S.

2010-01-01T23:59:59.000Z

300

Minimum-outage broadcast in wireless networks with fading channels  

Science Conference Proceedings (OSTI)

We consider the problem of cooperative broadcasting for minimum outage in wireless networks. We consider wireless multihop broadcast as a set of transmitters that transmit in a certain order. The receiving nodes are able to combine all the previous transmissions ... Keywords: broadcast, multicast, outage, wireless networks

Tolga Girici; Gulizar Duygu Kurt

2010-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.  

SciTech Connect

This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits.

Palmiotti, G.; Cahalan, J.; Pfeiffer, P.; Sofu, T.; Taiwo, T.; Wei,T.; Yacout, A.; Yang, W.; Siegel, A.; Insepov, Z.; Anitescu, M.; Hovland,P.; Pereira, C.; Regalbuto, M.; Copple, J.; Willamson, M.

2006-12-11T23:59:59.000Z

302

Survey of nuclear power plant construction costs, 1983  

SciTech Connect

This report presents cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in the construction pipeline, collected on Form EIA-254. The information on US nuclear power plants in the construction pipeline is reported voluntarily each quarter by the electric utilities. This report presents the data collected in the first quarter of 1983 on the 71 nuclear units in the construction pipeline. Historical data on 73 units, totalling 57,287 net megawatts (MWe) of design capacity, in commercial operation as of March 31, 1983, are also given. Three types of information are included: plant characteristics and ownership, construction costs, and construction schedule or chronology. Summary statistics are presented on direct component costs and construction leadtimes for a sample of operating units and units in the construction pipeline. The reactor-specific cost data included in Chapter 4 are the estimated final nuclear production plant costs and, for units in the construction pipeline, the disbursed and sunk costs as of March 31, 1983. 7 figures, 5 tables.

1983-12-01T23:59:59.000Z

303

Indicator system for advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

304

Plant Support Engineering: Aging Management Program Guidance for Medium- Voltage Cable Systems for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Regulatory and management concern regarding the reliability of medium-voltage cable systems at nuclear plants has been increasing for 5–10 years. The staff of the U.S. Nuclear Regulatory Commission (NRC) are concerned that wetted (up to and including submergence) medium-voltage cable circuits may be degrading to the point at which multiple cable circuits may fail when called on to perform functions affecting safety. Utility managers are concerned that cables may fail, causing adverse safety consequences ...

2010-06-02T23:59:59.000Z

305

DOE Releases Filing Instructions for Federal Risk Insurance for New Nuclear Power Plants  

Energy.gov (U.S. Department of Energy (DOE))

Outlines Five Steps for New Nuclear Plant Sponsors to Enter Into a Conditional Agreement for Risk Insurance

306

Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants  

SciTech Connect

OAK-B135 Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants

O' Connell, J. Michael

2002-01-01T23:59:59.000Z

307

INFORMATION INTEGRATION IN CONTROL ROOMS AND TECHNICAL OFFICES IN NUCLEAR POWER PLANTS  

E-Print Network (OSTI)

Information integration in control rooms and technical offices in nuclear power plants Report prepared within the framework of the

unknown authors

2001-01-01T23:59:59.000Z

308

A stochastic model for the measurement of electricity outage costs  

SciTech Connect

The measurement of customer outage costs has recently become an important subject of research for electric utilities. This paper uses a stochastic dynamic model as the starting point in developing a market-based method for the evaluation of outage costs. Specifically, the model postulates that once an electricity outage occurs, all production activity stops. Full production is resumed once the electricity outage is over. This process repeats itself indefinitely. The business customer maximizes his expected discounted profits (the expected value of the firm), taking into account his limited ability to respond to repeated random electricity outages. The model is applied to 11 industrial branches in Israel. The estimates exhibit a large variation across branches. 34 refs., 3 tabs.

Grosfeld-Nir, A.; Tishler, A. (Tel Aviv Univ. (Israel))

1993-01-01T23:59:59.000Z

309

Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

When assessing cable degradation or failure assessment, using the correct test and assessment methodology is critical to obtaining the correct answer. Many in-plant and laboratory tests exist. Some apply to the cable types used in nuclear plants. Some apply only to distribution cables. Most have pertinence to only one issue or even one cable design. This report provides a correlation between specific cable problems and the appropriate tests that may be used to resolve the issue. The report starts with su...

2011-12-23T23:59:59.000Z

310

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect

The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

311

Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants  

E-Print Network (OSTI)

Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 by G. Palmiotti, J. Cahalan, P. Pfeiffer, T;2 ANL-AFCI-168 Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants G

Anitescu, Mihai

312

Vulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices  

E-Print Network (OSTI)

Vulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices Marko threats to a nuclear power plant in the year 1991 and after the 9/11 events in 2001. The methodology which strength and injuries of human beings with nuclear power plant models used in probabilistic safety

Cizelj, Leon

313

U.S. Nuclear Power Plants: Continued Life or Replacement After 60? (released in AEO2010)  

Reports and Publications (EIA)

Nuclear power plants generate approximately 20 percent of U.S. electricity, and the plants in operation today are often seen as attractive assets in the current environment of uncertainty about future fossil fuel prices, high construction costs for new power plants (particularly nuclear plants), and the potential enactment of GHG regulations. Existing nuclear power plants have low fuel costs and relatively high power output. However, there is uncertainty about how long they will be allowed to continue operating.

Information Center

2010-05-11T23:59:59.000Z

314

Advanced Nuclear Technology: Supplier Quality Management for New Nuclear Plant Construction Projects  

Science Conference Proceedings (OSTI)

This report provides guidance for new nuclear power plant construction projects on supplier quality-related risks associated with the procurement of materials, equipment, and services intended for use in a safety-related plant application. This guidance takes an in-depth look into the procurement-related challenges that new construction projects face and at measures for overcoming these challenges. A methodology is provided for identifying, managing, evaluating, and mitigating quality-related risks ...

2013-06-26T23:59:59.000Z

315

Nuclear Maintenance Applications Center: Passive Component Maintenance Guide for Nuclear Power Plant Personnel  

Science Conference Proceedings (OSTI)

The information contained in this report represents a significant collection of technical and human performance information, including techniques and good practices, related to the design, maintenance, and operation of passive components common at most domestic nuclear power plants. Assemblage of this information provides a single point of reference for plant engineering and maintenance personnel, both in the present and in the future. Through the use of this guideline, in close conjunction with the indu...

2011-11-16T23:59:59.000Z

316

Design and construction of the Qinshan nuclear power plant  

Science Conference Proceedings (OSTI)

The construction work of China's first prototype nuclear power plant Qinshan NPP has already begun. This plant is located on the northern shore of Hangzhou Bay. It is designed to have a capacity of 300 MW electricity. The thermal power of the reactor is 966 MW. The primary circuit consists of 2 coolant loops and 16 auxiliary systems for normal operation. Safety is always the priority in design consideration. Preliminary safety analyses have been done and satisfactory results have been obtained. Excavation and clean out work has been finished.

Yu, O.

1985-01-01T23:59:59.000Z

317

Effects of delaying the operation of a nuclear power plant  

Science Conference Proceedings (OSTI)

This report documents a study of an actual 24-month nuclear power plant licensing delay. A representative utility was chosen for examination. The research was oriented toward determination of the licensing delay's impact on the utility's operating results, ratepayers, and security issues. The methodology utilized to estimate those impacts involved the recursive interaction of a generation costing program to estimate replacement fuel costs and a financial regulatory model to concomitantly determine the impact on the utility, its ratepayers and security issues. The latter model was executed under six alternate scenarios: (1) no delay in the plant's operation; (2) a 24-month delay; (3) a 24-month delay but further assuming all replacement power was generated by coal-fired plants; (4) a 24-month delay assuming all replacement power from oil-fired plants; (5) no delay but assuming the capital cost of the plant was twice as large; and (6) a 24-month delay with the capital cost of the plant twice as large. Three primary conclusions were made. First, under all scenarios, a 24-month delay in operation of the plant has an adverse impact on the utility's internal generation of funds. Second, although electricity rates are not appreciably affected by the delay, the direction of electricity price changes is contingent on the source of fuel used for replacement power. Finally, a 24-month delay has an adverse impact on the indicators used to evaluate the financial soundness of the utility in all cases under consideration.

Hill, L.J.; Rainey, J.A.; Tepel, R.C.; Van Dyke, J.W.

1983-12-01T23:59:59.000Z

318

U.S. - Canada Power System Outage Task Force: Final Report on...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

- Canada Power System Outage Task Force: Final Report on the Implementation of Task Force Recommendations U.S. - Canada Power System Outage Task Force: Final Report on the...

319

Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.  

Science Conference Proceedings (OSTI)

This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant licensing.

OHara,J.; Higgins, J.; Brown, W.; Fink, R.

2008-02-14T23:59:59.000Z

320

Optimization of Fire Protection Impairments at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

In recent years, risk-informed and performance-based (RI/PB) fire protection is gaining further acceptance by the Nuclear Regulatory Commission (NRC) and the industry. In addition, fire risk assessment methods are gaining some level of maturity since the first industrywide experience with individual plant examination for external events (IPEEE). RI/PB methods can reduce the cost of operating fire protection programs and maintaining fire safety.

2006-08-07T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Predictive Maintenance Self-Assessment Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

There is a need at nuclear power plants for optimization and continuous improvement in the predictive maintenance (PdM) process. This need is based upon increased reliance on PdM to contribute to low unplanned capability loss factors, prevent significant equipment failures, reduce resources for maintenance, manage assets in support of license renewal and aging control, incorporate new technologies and advanced information management, and manage the risk associated with maintenance activities. This docume...

2000-11-28T23:59:59.000Z

322

Introduction to Nuclear Plant Steam Turbine Control Systems  

Science Conference Proceedings (OSTI)

Since Nuclear Power Plants produce their power through the use of Steam Turbine Generators, any problems associated with the Turbine Control System has a direct effect on power generation. Although considerable effort has been expended in improving control system reliability, failures resulting in lost generation and high maintenance cost still plague the industry. On an individual basis, improvements have been made through maintenance techniques, modifications and upgrades. Unfortunately, this informati...

1995-03-02T23:59:59.000Z

323

Understanding seismic design criteria for Japanese nuclear power plants  

SciTech Connect

This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non-nuclear structures have been reviewed and summarized. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with US criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

Park, Y.J.; Hofmayer, C.H. [Brookhaven National Lab., Upton, NY (United States); Costello, J.F. [US Nuclear Regulatory Commission, Washington, DC (United States)

1994-12-31T23:59:59.000Z

324

Hydrogen Production from the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) is a high temperature gas-cooled reactor that will be capable of producing hydrogen, electricity and/or high temperature process heat for industrial use. The project has initiated the conceptual design phase and when completed will demonstrate the viability of hydrogen generation using nuclear produced process heat. This paper explains how industry and the U.S. Government are cooperating to advance nuclear hydrogen technology. It also describes the issues being explored and the results of recent R&D including materials development and testing, thermal-fluids research, and systems analysis. The paper also describes the hydrogen production technologies being considered (including various thermochemical processes and high-temperature electrolysis).

M. Patterson; C. Park

2008-03-01T23:59:59.000Z

325

The Acceptance Strategy for Nuclear Power Plant In Indonesia  

SciTech Connect

Indonesia has planned to build nuclear power plants. Some feasibility studies have been conducted intensively. However, the processes of NPP introduction are still uncertain. National Energy Plan in Indonesia, which has been made by some governmental agencies, does not yet give positive impact to the government decision to construct the nuclear power plant (NPP). This paper discusses the process of NPP introduction in Indonesia, which has been colored with debate of stakeholder and has delayed decision for go-nuclear. The technology paradigm is used to promote NPP as an alternative of reliable energy resources. This paradigm should be complemented with international politic-economic point of view. The international politic-economic point of view shows that structural powers, consisting of security, production, finance, and knowledge structures, within which the NPP is introduced, have dynamic characteristics. The process of NPP introduction in Indonesia contains some infrastructure development (R and D, legislation, regulation, energy planning, site study, public acceptance efforts, etc), but they need a better coherent NPP implementation program and NPP Acceptance Program. Strategic patterns for NPP acceptance described in this paper are made by considering nuclear regulation development and the interest of basic domestic participation. The first NPP program in Indonesia having proven technology and basic domestic participation is and important milestone toward and optimal national energy-mix.

Suhaemi, Tjipta [Centre for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency of Indonesia (Indonesia); Syaukat, Achmad [Centre for Nuclear Technology Business, National Nuclear Energy Agency of Indonesia, Kawasan PUSPIPTEK, Serpong-Tangerang Selatan (Indonesia)

2010-06-22T23:59:59.000Z

326

Conceivable new recycling of nuclear waste by nuclear power companies in their plants  

E-Print Network (OSTI)

We outline the basic principles and the needed experiments for a conceivable new recycling of nuclear waste by the power plants themselves to avoid its transportation and storage to a (yet unknown) dumping area. Details are provided in an adjoining paper and in patents pending.

Ruggero Maria Santilli

1997-04-09T23:59:59.000Z

327

AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT  

SciTech Connect

An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. Most of the components of the plant are within the capability of current technology. The major exception is the fuel material, uranium carbide. Preliminary results of the development work now in progress indicate that uranium carbide would be an excellent fuel for high-temperature reactors, but temperature and burnup limitation have yet to be firmly established. Additional development work is also required on the steam generators. These are the single-barrier type similar to those which will be used in the Enrico Fernri Fast Breeder Reactor plant but produce steam at higher pressure and temperature. Questions also remain regarding the use of nitrogen as a cover gas over sodium at 1200 deg F and compatibility of the materials used in the primary neutron shield. All of these questions are currently under investigation. (auth)

Churchill, J.R.; Renard, J.

1960-03-15T23:59:59.000Z

328

Validation of seismic probabilistic risk assessments of nuclear power plants  

SciTech Connect

A seismic probabilistic risk assessment (PRA) of a nuclear plant requires identification and information regarding the seismic hazard at the plant site, dominant accident sequences leading to core damage, and structure and equipment fragilities. Uncertainties are associated with each of these ingredients of a PRA. Sources of uncertainty due to seismic hazard and assumptions underlying the component fragility modeling may be significant contributors to uncertainty in estimates of core damage probability. Design and construction errors also may be important in some instances. When these uncertainties are propagated through the PRA, the frequency distribution of core damage probability may span three orders of magnitude or more. This large variability brings into question the credibility of PRA methods and the usefulness of insights to be gained from a PRA. The sensitivity of accident sequence probabilities and high-confidence, low probability of failure (HCLPF) plant fragilities to seismic hazard and fragility modeling assumptions was examined for three nuclear power plants. Mean accident sequence probabilities were found to be relatively insensitive (by a factor of two or less) to: uncertainty in the coefficient of variation (logarithmic standard deviation) describing inherent randomness in component fragility; truncation of lower tail of fragility; uncertainty in random (non-seismic) equipment failures (e.g., diesel generators); correlation between component capacities; and functional form of fragility family. On the other hand, the accident sequence probabilities, expressed in the form of a frequency distribution, are affected significantly by the seismic hazard modeling, including slopes of seismic hazard curves and likelihoods assigned to those curves.

Ellingwood, B. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

1994-01-01T23:59:59.000Z

329

NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER  

SciTech Connect

The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.

Mark Holbrook

2010-09-01T23:59:59.000Z

330

Guide for monitoring equipment environments during nuclear plant operation  

Science Conference Proceedings (OSTI)

This guide is intended to assist utilities in formulating and implementing improved monitoring programs by providing guidance on why, where and how to track environmental conditions such as temperature, radiation, and humidity for equipment in nuclear power plants during operation. The guide describes steps for implementing programs. It also gives advantages, disadvantages and costs for a variety of monitoring methods and devices such as sensors with recording devices, thermographic surveys, and passive thermal and radiation integrating devices. The guide also contains twenty technical papers presented at an environmental monitoring workshop covering the subjects of plant experience with elevated temperatures, plant environmental monitoring programs, and techniques for monitoring temperature and radiation. These individual papers have been cataloged separately.

Danahy, J.W.; Evans, R.W. (Grove Engineering, Inc., Rockville, MD (United States))

1991-06-01T23:59:59.000Z

331

Aging management guideline for commercial nuclear power plants-pumps  

SciTech Connect

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

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

1994-03-01T23:59:59.000Z

332

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

population growth surrounding a nuclear power plant once thegrowth by requiring that certification of nuclear power plant

Yen, W.W.S.

2010-01-01T23:59:59.000Z

333

Incentive regulation of nuclear power plants by state regulators  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission (NRC) monitors incentive programs established by state regulators in order to obtain current information and to consider the potential safety effects of the incentive programs as applied to nuclear units. The current report is an update of NUREG/CR-5509, Incentive Regulation of Nuclear Power Plants by State Public Utility Commissions, published in December 1989. The information in this report was obtained from interviews conducted with each state regulator and each utility with a minimum entitlement of 10%. The agreements, orders, and settlements from which each incentive program was implemented were reviewed as required. The interviews and supporting documentation form the basis for the individual state reports describing the structure and financial impact of each incentive program. The programs currently in effect represent the adoption of an existing nuclear performance incentive program proposal and one new program. In addition, since 1989 a number of nuclear units have been included in one existing program; while one program was discontinued and another one concluded. 6 refs., 27 tabs.

Martin, R.L.; Baker, K.; Olson, J. (Battelle Human Affairs Research Center, Seattle, WA (USA))

1991-02-01T23:59:59.000Z

334

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

335

Economic Benefits of Increasing Electric Grid Resilience to Weather Outages  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Economic Benefits of Increasing Electric Grid Resilience to Weather Economic Benefits of Increasing Electric Grid Resilience to Weather Outages Economic Benefits of Increasing Electric Grid Resilience to Weather Outages In June 2011, President Obama released A Policy Framework for the 21st Century Grid which set out a four-pillared strategy for modernizing the electric grid. The initiative directed billions of dollars toward investments in 21st century smart grid technologies focused at increasing the grid's efficiency, reliability, and resilience, and making it less vulnerable to weather-related outages and reducing the time it takes to restore power after an outage occurs. Grid resilience is increasingly important as climate change increases the frequency and intensity of severe weather. Greenhouse gas emissions are elevating air and water temperatures around the world. Scientific research

336

A statistical model for risk management of electric outage forecasts  

Science Conference Proceedings (OSTI)

Risk management of power outages caused by severe weather events, such as hurricanes, tornadoes, and thunderstorms, plays an important role in electric utility distribution operations. Damage prediction based on weather forecasts on an appropriate spatial ...

H. Li; L. A. Treinish; J. R. M. Hosking

2010-05-01T23:59:59.000Z

337

Abstract--Integration of asset management and outage management tasks for distribution system is proposed and  

E-Print Network (OSTI)

and evaluation of the influence of optimization on the cost of system outage is elaborated. Potential benefit as the maximum tolerable value. #12;7 V. OPTIMIZED OUTAGE COST THROUGH RISK-BASED ASSESSMENT 1. Optimized outage cost through risk-based assessment Risk-based analysis is used to estimate outage cost in this paper

Kezunovic, Mladen

338

(Safety and reliability of nuclear power plant technology)  

SciTech Connect

The traveler attended the 16th MPA Seminar on the Safety and Reliability of Plant Technology with Special Emphasis on Nuclear Technology. The objective of the trip was to gather information and data that could prove useful to the US Nuclear Regulatory Commission (USNRC) sponsored Heavy-Section Steel Irradiation (HSSI) and Heavy-Section Steel Technology (HSST) Programs and to present a paper entitled, Effects of Irradiation on Initiation and Crack-Arrest Toughness of Two High-Copper Welds and on Stainless Steel Cladding. This paper summarizes results from the 5th, 6th, and 7th Irradiation Series of experiments performed within the HSSI Program by the Metals and Ceramics Division at Oak Ridge National Laboratory (ORNL).

Dickson, T.L.

1990-10-22T23:59:59.000Z

339

COMMERCIAL UTILITY PERSPECTIVES ON NUCLEAR POWER PLANT CONTROL ROOM MODERNIZATION  

SciTech Connect

Commercial nuclear power plants (NPPs) in the United States need to modernize their main control rooms (MCR). Many NPPs have done partial upgrades with some success and with some challenges. The Department of Energy’s (DOE) Light Water Reactor Sustainability (LWRS) Program, and in particular the Advanced Instrumentation and Controls (I&C) and Information Systems Technologies Research and Development (R&D) Pathway within LWRS, is designed to assist commercial nuclear power industry with their MCR modernization efforts. As part of this framework, a survey was issued to utility representatives of the LWRS Program Advanced Instrumentation, Information, and Control Systems/Technologies (II&C) Utility Working Group to obtain their views on a range of issues related to MCR modernization, including: drivers, barriers, and technology options, and the effects these aspects will have on concepts of operations, modernization strategies, and staffing. This paper summarizes the key survey results and discusses their implications.

Jeffrey C. Joe; Ronald L. Boring; Julius J. Persensky

2012-07-01T23:59:59.000Z

340

The Need for Near-Term Deployment of New Nuclear Power Plants Position Statement  

E-Print Network (OSTI)

The American Nuclear Society (ANS) supports and encourages the near-term deployment of new nuclear power plants. Nuclear energy, the second-largest power source, contributes 20 % of the electricity production in the United States. 1 Nuclear power can be competitive with gas and coal plants. Like solar, wind, and hydropower, nuclear energy has near-zero emissions of greenhouse gases and air pollutants. The more than one hundred nuclear power plants currently operating in the United States have an excellent safety record and are proven reliable sources of power.

unknown authors

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures.

Powell, J.G.

1993-11-16T23:59:59.000Z

342

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

Powell, James G. (Clifton Park, NY)

1993-01-01T23:59:59.000Z

343

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect

Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

Lynne M. Stevens

2010-07-01T23:59:59.000Z

344

Seismic Margin Assessment of the Edwin I. Hatch Nuclear Plant, Unit 1  

Science Conference Proceedings (OSTI)

A seismic margin assessment of the Georgia Power Company Edwin I. Hatch, unit 1 nuclear power plant showed the practicality of an EPRI methodology for assessing the ability of nuclear plants to withstand large earthquakes. The assessment, performed by the utility, established that the plant can withstand an earthquake at least twice the magnitude for which it was designed.

1991-08-01T23:59:59.000Z

345

Comparison of Options for a Pilot Plant Fusion Nuclear Mission  

Science Conference Proceedings (OSTI)

A fusion pilot plant study was initiated to clarify the development needs in moving from ITER to a first of a kind fusion power plant, following a path similar to the approach adopted for the commercialization of fission. The pilot plant mission encompassed component test and fusion nuclear science missions plus the requirement to produce net electricity with high availability in a device designed to be prototypical of the commercial device. Three magnetic configuration options were developed around this mission: the advanced tokamak (AT), spherical tokamak (ST) and compact stellarator (CS). With the completion of the study and separate documentation of each design option a question can now be posed; how do the different designs compare with each other as candidates for meeting the pilot plant mission? In a pro/con format this paper will examine the key arguments for and against the AT, ST and CS magnetic configurations. Key topics addressed include: plasma parameters, device configurations, size and weight comparisons, diagnostic issues, maintenance schemes, availability influences and possible test cell arrangement schemes.

Brown, T; Goldston, R J; El-Guebaly, L; Kessel, C; Neilson, G H; Malang, S; Menard, J E; Prager, S; Waganer, L; Titus, P

2012-08-27T23:59:59.000Z

346

Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1  

Science Conference Proceedings (OSTI)

This reference manual compiles information on technology, requirements, and experience pertaining to the qualification of safety-related equipment for use in nuclear power plants under normal operating conditions and under adverse environments such as steam line breaks and earthquakes. The manual covers both environmental and seismic qualification of all safety-related electrical and mechanical equipment, but places emphasis on environmental qualification of Class 1E electrical equipment subject to harsh...

2010-09-16T23:59:59.000Z

347

Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine Nuclear Fuel Qualification Program  

Energy.gov (U.S. Department of Energy (DOE))

fficials from the U.S. Department of Energy’s (DOE) Office of Nuclear Energy today (April 8, 2010) participated in a ceremony in Ukraine to mark the insertion of Westinghouse-produced nuclear fuel into a nuclear power plant in Ukraine.

348

Nuclear Maintenance Applications Center: Considerations for Developing a Critical Parts Program at a Nuclear Power Plant  

Science Conference Proceedings (OSTI)

In 2003, Plant Support Engineering (PSE) of the Electric Power Research Institute (EPRI) published the report Critical Component Identification Process8212Licensee Examples: Scoping and Identification of Critical Components in Support of INPO AP-913 (1007935). That report was the initial output from a project to assist utilities that were implementing Institute of Nuclear Power Operations (INPO) AP-913, Equipment Reliability Process Description. Two of the key aspects of INPO AP-913 are the accurate scop...

2007-11-30T23:59:59.000Z

349

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESSPlanning for Nuclear Power Plants Determination of Accidentnuclear power plants . . . . . . . . . • . . . . .2.2.4.3.

Yen, W.W.S.

2010-01-01T23:59:59.000Z

350

Nuclear power plant Generic Aging Lessons Learned (GALL). Appendix B  

SciTech Connect

The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This report consists of Volume 2, which consists of the GALL literature review tables for the NUMARC Industry Reports reviewed for the report.

Kasza, K.E.; Diercks, D.R.; Holland, J.W.; Choi, S.U. [and others

1996-12-01T23:59:59.000Z

351

Cognitive skill training for nuclear power plant operational decision making  

SciTech Connect

Training for operator and other technical positions in the commercial nuclear power industry traditionally has focused on mastery of the formal procedures used to control plant systems and processes. However, decisionmaking tasks required of nuclear power plant operators involve cognitive skills (e.g., situation assessment, planning). Cognitive skills are needed in situations where formal procedures may not exist or may not be as prescriptive, as is the case in severe accident management (SAM). The Westinghouse research team investigated the potential cognitive demands of SAM on the control room operators and Technical Support Center staff who would be most involved in the selection and execution of severe accident control actions. A model of decision making, organized around six general cognitive processes, was developed to identify the types of cognitive skills that may be needed for effective performance. Also, twelve SAM scenarios were developed to reveal specific decision-making difficulties. Following the identification of relevant cognitive skills, 19 approaches for training individual and team cognitive skills were identified. A review of these approaches resulted in the identification of general characteristics that are important in effective training of cognitive skills.

Mumaw, R.J.; Swatzler, D.; Roth, E.M. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Thomas, W.A. [Quantum Technologies, Inc., Oak Brook, IL (United States)

1994-06-01T23:59:59.000Z

352

Advanced design nuclear power plants: Competitive, economical electricity. An analysis of the cost of electricity from coal, gas and nuclear power plants  

SciTech Connect

This report presents an updated analysis of the projected cost of electricity from new baseload power plants beginning operation around the year 2000. Included in the study are: (1) advanced-design, standardized nuclear power plants; (2) low emissions coal-fired power plants; (3) gasified coal-fired power plants; and (4) natural gas-fired power plants. This analysis shows that electricity from advanced-design, standardized nuclear power plants will be economically competitive with all other baseload electric generating system alternatives. This does not mean that any one source of electric power is always preferable to another. Rather, what this analysis indicates is that, as utilities and others begin planning for future baseload power plants, advanced-design nuclear plants should be considered an economically viable option to be included in their detailed studies of alternatives. Even with aggressive and successful conservation, efficiency and demand-side management programs, some new baseload electric supply will be needed during the 1990s and into the future. The baseload generating plants required in the 1990s are currently being designed and constructed. For those required shortly after 2000, the planning and alternatives assessment process must start now. It takes up to ten years to plan, design, license and construct a new coal-fired or nuclear fueled baseload electric generating plant and about six years for a natural gas-fired plant. This study indicates that for 600-megawatt blocks of capacity, advanced-design nuclear plants could supply electricity at an average of 4.5 cents per kilowatt-hour versus 4.8 cents per kilowatt-hour for an advanced pulverized-coal plant, 5.0 cents per kilowatt-hour for a gasified-coal combined cycle plant, and 4.3 cents per kilowatt-hour for a gas-fired combined cycle combustion turbine plant.

1992-06-01T23:59:59.000Z

353

Identification of good practices in the operation of nuclear power plants  

E-Print Network (OSTI)

This work developed an approach to diagnose problems and identify good practices in the operation of nuclear power plants using the system dynamics technique. The research began with construction of the ORSIM (Nuclear Power ...

Chen, Haibo, 1975-

2005-01-01T23:59:59.000Z

354

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Nuclear power plants in the United States currently produce about 20 percent of the nation's electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit greenhouse gases. Continued and expanded reliance on nuclear energy is one key to meeting future demand for electricity in the U.S. and is called for in the National Energy Policy. Nevertheless, no new nuclear plants have been built in the U.S. in many years, and none are currently slated for construction. The U.S. Department of Energy (DOE) has been working with the nuclear

355

An examination of the pursuit of nuclear power plant construction projects in the United States  

E-Print Network (OSTI)

The recent serious reconsideration of nuclear power as a means for U.S. electric utilities to increase their generation capacity provokes many questions regarding the achievable success of future nuclear power plant ...

Guyer, Brittany (Brittany Leigh)

2011-01-01T23:59:59.000Z

356

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Nuclear power plants in the United States currently produce about 20 percent of the nation's electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit greenhouse gases. Continued and expanded reliance on nuclear energy is one key to meeting future demand for electricity in the U.S. and is called for in the National Energy Policy. Nevertheless, no new nuclear plants have been built in the U.S. in many years, and none are currently slated for construction. The U.S. Department of Energy (DOE) has been working with the nuclear

357

Fire Events Database and Generic Ignition Frequency Model for U.S. Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report contains a revision of the EPRI Fire Events Database for U.S. Nuclear Power Plants last published in EPRI Report 1000894 in October 2000. This report also contains a revision of the generic fire ignition frequency models that were published in NSAC-178L, "Fire Events Database of U.S. Nuclear Power Plants" (January 1993) and EPRI TR-105929, "Fire Ignition Frequency Model at Shutdown for U.S. Nuclear Power Plants" (December 1995).

2001-11-09T23:59:59.000Z

358

Reactor Vessel Head Disposal Campaign for Nuclear Management Company  

SciTech Connect

After establishing a goal to replace as many reactor vessel heads as possible - in the shortest time and at the lowest cost as possible - Nuclear Management Company (NMC) initiated an ambitious program to replace the heads on all six of its pressurized water reactors. Currently, four heads have been replaced; and four old heads have been disposed of. In 2002, NMC began fabricating the first of its replacement reactor vessel heads for the Kewaunee Nuclear Plant. During its fall 2004 refueling outage, Kewaunee's head was replaced and the old head was prepared for disposal. Kewaunee's disposal project included: - Down-ending, - Draining, - Decontamination, - Packaging, - Removal from containment, - On-Site handling, - Temporary storage, - Transportation, - Disposal. The next two replacements took place in the spring of 2005. Point Beach Nuclear Plant (PBNP) Unit 2 and Prairie Island Nuclear Generating Plant (PINGP) Unit 2 completed their head replacements during their scheduled refueling outages. Since these two outages were scheduled so close to each other, their removal and disposal posed some unique challenges. In addition, changes to the handling and disposal programs were made as a result of lessons learned from Kewaunee. A fourth head replacement took place during PBNP Unit 1's refueling outage during the fall of 2005. A number of additional changes took place. All of these changes and challenges are discussed in the paper. NMC's future schedule includes PINGP Unit 1's installation in Spring 2006 and Palisades' installation during 2007. NMC plans to dispose of these two remaining heads in a similar manner. This paper presents a summary of these activities, plus a discussion of lessons learned. (authors)

Hoelscher, H.L.; Closs, J.W. [Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 (United States); Johnson, S.A. [Duratek, Inc., 140 Stoneridge Drive, Columbia, SC 29210 (United States)

2006-07-01T23:59:59.000Z

359

Success of the first nuclear power plant built on China`s self-reliance  

Science Conference Proceedings (OSTI)

Having overcome a series of difficulties and hard points, the first Chinese indigenous nuclear power plant, Qinshan Nuclear Power Plant of PWR type with the capacity of 300MW(e) is now in steady operation. Through tremendous works done for this project great achievements and experience as well as lessons learned have been obtained for systematic acquisition of nuclear power technology. The sound fact has demonstrated that China has the ability to develop nuclear power mainly depending on self-reliance.

Yu, O.

1994-12-31T23:59:59.000Z

360

Compilation of Results and Feedback Regarding Turbine Upgrades at Nuclear and Fossil Power Plants  

Science Conference Proceedings (OSTI)

This report compiles results and feedback and draws a number of conclusions and lessons learned regarding steam turbine generator upgrades at nuclear and fossil power plants.

2008-11-24T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Analysis of Nuclear Power Plant Operating Costs: A 1995 Update, An  

Reports and Publications (EIA)

This report provides an analysis of nuclear power plant operating costs. EIA published three reports on this subject during the period 1988-1995.

James G. Hewlett

1995-04-01T23:59:59.000Z

362

Guideline for On-Line Monitoring of Nuclear Power Plant Instrument Channel Performance  

Science Conference Proceedings (OSTI)

This report provides a guideline for a utility to develop an on-line monitoring (OLM) program for evaluating instrument channel performance at nuclear power plants (NPPs).

2011-11-08T23:59:59.000Z

363

Survey on the Use of Configuration Risk and Safety Management Tools at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

A joint project of Electricite de France (EDF) and EPRI, this project analyzed use of configuration safety and risk management tools at nuclear power plants.

1998-09-24T23:59:59.000Z

364

Bayesian Analysis for the Site-Specific Dose Modeling in Nuclear Power Plant Decommissioning.  

E-Print Network (OSTI)

??Decommissioning is the process of closing down a facility. In nuclear power plant decommissioning, it must be determined that that any remaining radioactivity at a… (more)

Ling, Xianbing

2001-01-01T23:59:59.000Z

365

A review of the methods of economic analysis of nuclear power plants.  

E-Print Network (OSTI)

??Nuclear power plants across the United States are reaching the end of their current operating licenses, forcing decision makers to think about the way forward.… (more)

Cavender, Brittainy Anne

2011-01-01T23:59:59.000Z

366

Long term control of 3D engineering data for nuclear power plants  

Science Conference Proceedings (OSTI)

The engineering of the next generation of nuclear power plants requires to take into account the whole plant lifecycle: engineering, building, operating, maintaining and decommissioning. Satisfying stronger and stronger safety regulations requires the ...

Thomas Paviot; Christophe Mouton; Samir Lamouri

2013-06-01T23:59:59.000Z

367

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

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

2005-09-01T23:59:59.000Z

368

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network (OSTI)

Uncertainty can be either an opportunity or a risk. Every construction project begins with the expectation of project performance. To meet the expectation, construction projects need to be managed through sound risk assessment and management beginning with the front-end of the project life cycle to check the feasibility of a project. The Construction Industry Institute’s (CII) International Project Risk Assessment (IPRA) tool has been developed, successfully used for a variety of heavy industry sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks associated with NPP projects, the goal of this thesis is to develop tailored risk framework for NPP projects that leverages and modifies the existing IPRA process. The IPRA has 82 elements to assess the risks associated with international construction projects. The modified IPRA adds five major issues (elements) to consider the unique risk factors of typical NPP projects based upon a review of the literature and an evaluation of the performance of previous nuclear-related facilities. The modified IPRA considers the sequence of NPP design that ultimately impacts the risks associated with plant safety and operations. Historically, financial risks have been a major chronic problem with the construction of NPPs. This research suggests that unstable regulations and the lack of design controls and oversight are significant risk issues. This thesis includes a consistency test to initially validate whether the asserted risks exist in actual conditions. Also, an overall risk assessment is performed based on the proposed risk framework for NPP and the list of assessed risk is proposed through a possible scenario. After the assessment, possible mitigation strategies are also provided against the major risks as a part of this thesis. This study reports on the preliminary findings for developing a new risk framework for constructing nuclear power plants. Future research is needed for advanced verification of the proposed elements. Follow-on efforts should include verification and validation of the proposed framework by industry experts and methods to quantify and evaluate the performance and risks associated with the multitude of previous NPP projects.

Yeon, Jaeheum 1981-

2012-12-01T23:59:59.000Z

369

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

None

2005-01-01T23:59:59.000Z

370

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

Nuclear Reactor Operational Status Tables (Information and data on nuclear power reactors Generation: by State and Reactor. Annual Energy Review, ...

371

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

372

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

373

Prognostics and Life Beyond 60 for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Safe, secure, reliable and sustainable energy supply is vital for advanced and industrialized life styles. To meet growing energy demand there is interest in longer term operation (LTO) for the existing nuclear power plant fleet and enhancing capabilities in new build. There is increasing use of condition based maintenance (CBM) for active components and periodic in service inspection (ISI) for passive systems: there is growing interest in deploying on-line monitoring. Opportunities exist to move beyond monitoring and diagnosis based on pattern recognition and anomaly detection to and prognostics with the ability to provide an estimate of remaining useful life (RUL). The adoption of digital I&C systems provides a framework within which added functionality including on-line monitoring can be deployed, and used to maintain and even potentially enhance safety, while at the same time improving planning and reducing both operations and maintenance costs.

Leonard J. Bond; Pradeep Ramuhalli; Magdy S. Tawfik; Nancy J. Lybeck

2011-06-01T23:59:59.000Z

374

Capturing Historical Knowledge for Decommissioning of Nuclear Power Plants: Summary of Historical Site Assessments at Eight Decommis sioning Plants  

Science Conference Proceedings (OSTI)

This report describes approaches utilized and experience gained in the development of early characterization activities by a number of nuclear power plants undergoing decommissioning. In particular, the report provides experience and lessons of performing the Historical Site Assessment, or HSA.

2004-04-01T23:59:59.000Z

375

Overview of Common Mode Outages in Power Systems  

SciTech Connect

This paper is a result of ongoing activity carried out by Probability Applications for Common Mode Events (PACME) Task Force under the Reliability Risk and Probability Applications (RRPA) Subcommittee. The paper is intended to constitute a valid source of information and references about dealing with common-mode outages in power systems reliability analysis. This effort involves reviewing published literature and presenting state-of-the-art research and practical applications in the area of common-mode outages. Evaluation of available outage statistics show that there is a definite need for collective effort from academia and industry to not only recommended procedures for data collection and monitoring but also to provide appropriate mathematical models to assess such events.

Papic, Milorad; Awodele , Kehinde; Billinton, Roy; Dent, Chris; Eager, Dan; Hamoud, Gomaa; Jirutitijaroen, Panida; Kumbale, Murali; Mitra, Joydeep; Samaan, Nader A.; Schneider, Alex; Singh, Chanan

2012-11-10T23:59:59.000Z

376

Lassoing Line Outages in the Smart Power Grid  

E-Print Network (OSTI)

Fast and accurate unveiling of power line outages is of paramount importance not only for preventing faults that may lead to blackouts, but also for routine monitoring and control tasks of the smart grid, including state estimation and optimal power flow. Existing approaches are either challenged by the \\emph{combinatorial complexity} issues involved, and are thus limited to identifying single- and double-line outages; or, they invoke less pragmatic assumptions such as \\emph{conditionally independent} phasor angle measurements available across the grid. Using only a subset of voltage phasor angle data, the present paper develops a near real-time algorithm for identifying multiple line outages at the affordable complexity of solving a quadratic program via block coordinate descent iterations. The novel approach relies on reformulating the DC linear power flow model as a \\emph{sparse} overcomplete expansion, and leveraging contemporary advances in compressive sampling and variable selection using the least-abso...

Zhu, Hao

2011-01-01T23:59:59.000Z

377

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

SciTech Connect

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

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01T23:59:59.000Z

378

License Stewardship Approach to Commercial Nuclear Power Plant Decommissioning  

SciTech Connect

The paper explores both the conceptual approach to decommissioning commercial nuclear facilities using a license stewardship approach as well as the first commercial application of this approach. The license stewardship approach involves a decommissioning company taking control of a site and the 10 CFR 50 License in order to complete the work utilizing the established trust fund. In conclusion: The license stewardship approach is a novel way to approach the decommissioning of a retired nuclear power plant that offers several key advantages to all parties. For the owner and regulators, it provides assurance that the station will be decommissioned in a safe, timely manner. Ratepayers are assured that the work will be completed for the price they already have paid, with the decommissioning contractor assuming the financial risk of decommissioning. The contractor gains control of the assets and liabilities, the license, and the decommissioning fund. This enables the decommissioning contractor to control their work and eliminates redundant layers of management, while bringing more focus on achieving the desired end state - a restored site. (authors)

Daly, P.T.; Hlopak, W.J. [Commercial Services Group, EnergySolutions 1009 Commerce Park, Oak Ridge, TN (United States)

2008-07-01T23:59:59.000Z

379

EIA - AEO2010 - U.S. nuclear power plants: Continued life or replacement  

Gasoline and Diesel Fuel Update (EIA)

U.S. nuclear power plants: continued life or replacement after 60? U.S. nuclear power plants: continued life or replacement after 60? Annual Energy Outlook 2010 with Projections to 2035 U.S. nuclear power plants: Continued life or replacement after 60? Background Nuclear power plants generate approximately 20 percent of U.S. electricity, and the plants in operation today are often seen as attractive assets in the current environment of uncertainty about future fossil fuel prices, high construction costs for new power plants (particularly nuclear plants), and the potential enactment of GHG regulations. Existing nuclear power plants have low fuel costs and relatively high power output. However, there is uncertainty about how long they will be allowed to continue operating. The nuclear industry has expressed strong interest in continuing the operation of existing nuclear facilities, and no particular technical issues have been identified that would impede their continued operation. Recent AEOs had assumed that existing nuclear units would be retired after 60 years of operation (the initial 40-year license plus one 20-year license renewal). Maintaining the same assumption in AEO2010, with the projection horizon extended to 2035, would result in the retirement of more than one-third of existing U.S. nuclear capacity between 2029 and 2035. Given the uncertainty about when existing nuclear capacity actually will be retired, EIA revisited the assumption for the development of AEO2010 and modified it to allow the continued operation of all existing U.S. nuclear power plants through 2035 in the Reference case.

380

The Decommissioning of the Trino Nuclear Power Plant  

Science Conference Proceedings (OSTI)

Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise utilizes the full range of BNFL decommissioning experience and knowledge to develop a strategy, methodology and cost for the decommissioning of NPPs. Over the past year, a prompt decommissioning strategy for Trino has been developed. The strategy has been based on the principles of minimizing waste products that require long term storage, maximizing 'free release' materials and utilizing existing and regulatory approved technologies.

Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

2002-02-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
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381

Advisory system for the diagnosis of lost electric output in nuclear power plants  

Science Conference Proceedings (OSTI)

The enhancement of efficiency is world-wide trend to survive under intense competition. In recent years, the efficiency in the power industry is also one of the important topics. In case of nuclear power plants(NPPs), the period and quality of maintenance ... Keywords: Advisory system, Bayesian network, Diagnosis, Nuclear power plant, Regression, Turbine cycle

Gyunyoung Heo; Soon Heung Chang; Seong Soo Choi; Gwang Hee Choi; Moon Hak Jee

2005-11-01T23:59:59.000Z

382

Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants  

DOE Green Energy (OSTI)

Cooperative Agreement DE-FC07-06ID14788 was executed between the U.S. Department of Energy, Electric Transportation Applications, and Idaho National Laboratory to investigate the economics of producing hydrogen by electrolysis using electricity generated by nuclear power. The work under this agreement is divided into the following four tasks: Task 1 – Produce Data and Analyses Task 2 – Economic Analysis of Large-Scale Alkaline Electrolysis Task 3 – Commercial-Scale Hydrogen Production Task 4 – Disseminate Data and Analyses. Reports exist on the prospect that utility companies may benefit from having the option to produce electricity or produce hydrogen, depending on market conditions for both. This study advances that discussion in the affirmative by providing data and suggesting further areas of study. While some reports have identified issues related to licensing hydrogen plants with nuclear plants, this study provides more specifics and could be a resource guide for further study and clarifications. At the same time, this report identifies other area of risks and uncertainties associated with hydrogen production on this scale. Suggestions for further study in some of these topics, including water availability, are included in the report. The goals and objectives of the original project description have been met. Lack of industry design for proton exchange membrane electrolysis hydrogen production facilities of this magnitude was a roadblock for a significant period. However, recent design breakthroughs have made costing this facility much more accurate. In fact, the new design information on proton exchange membrane electrolyzers scaled to the 1 kg of hydrogen per second electrolyzer reduced the model costs from $500 to $100 million. Task 1 was delayed when the original electrolyzer failed at the end of its economic life. However, additional valuable information was obtained when the new electrolyzer was installed. Products developed during this study include a process model and a N2H2 economic assessment model (both developed by the Idaho National Laboratory). Both models are described in this report. The N2H2 model closely tracked and provided similar results as the H2A model and was instrumental in assessing the effects of plant availability on price when operated in the shoulder mode for electrical pricing. Differences between the H2A and N2H2 model are included in this report.

Stephen Schey

2009-07-01T23:59:59.000Z

383

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

P. E. MacDonald

2005-01-01T23:59:59.000Z

384

San Onofre nuclear outage contributes to Southern California’s ...  

U.S. Energy Information Administration (EIA)

Short, timely articles with graphics on energy, facts, issues ... in the Southern California Edison and San ... company providing retail ...

385

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

refabrication. through which nuclear fuel passes. Fusion.with the experience at the Nuclear Fuel Services Plant (seecommitment from the nuclear fuel cycle; see Section 3.2.3. )

Nero, A.V.

2010-01-01T23:59:59.000Z

386

Activities in support of continuing the service of nuclear power plant concrete structures  

SciTech Connect

In general, nuclear power plant concrete structure s performance has been very good; however, aging of concrete structures occurs with the passage of time that can potentially result in degradation if is effects are not controlled. Safety-related nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The interaction of the license renewal process and concrete structures is noted. A summary of operating experience related to aging of nuclear power plant concrete structures is provided. Several candidate areas are identified where additional research would be beneficial for aging management of nuclear power plant concrete structures. Finally, an update on recent activities at Oak Ridge National Laboratory related to aging management of nuclear power plant concrete structures is provided.

Naus, Dan J [ORNL

2012-01-01T23:59:59.000Z

387

A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A Roadmap to Deploy New Nuclear Power Plants in the United States A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report The objective of this document is to provide the Department of Energy (DOE) and the nuclear industry with the basis for a plan to ensure the availability of near-term nuclear energy options that can be in operation in the U.S. by 2010. This document identifies the technological, regulatory, and institutional gaps and issues that need to be addressed for new nuclear plants to be deployed in the U.S. in this timeframe. It also identifies specific designs that could be deployed by 2010, along with the actions and resource requirements that are needed to ensure their

388

A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A Roadmap to Deploy New Nuclear Power Plants in the United States A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report The objective of this document is to provide the Department of Energy (DOE) and the nuclear industry with the basis for a plan to ensure the availability of near-term nuclear energy options that can be in operation in the U.S. by 2010. This document identifies the technological, regulatory, and institutional gaps and issues that need to be addressed for new nuclear plants to be deployed in the U.S. in this timeframe. It also identifies specific designs that could be deployed by 2010, along with the actions and resource requirements that are needed to ensure their

389

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

390

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

391

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 58, NO. 1, FEBRUARY 2011 277 Anomaly Detection in Nuclear Power Plants via  

E-Print Network (OSTI)

applications (e.g., nuclear power reactor plants, petroleum industry and micro-gravity flow systems and Seungjin Kim Department of Mechanical and Nuclear Engineering, The Pennsylvania State University sensing. The underlying algorithm is built upon the recently reported theory of a statistical pattern

Ray, Asok

392

Thirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago  

E-Print Network (OSTI)

than 30 countries signed a deal on Tuesday to build the world's most advanced nuclear fusion reactor nuclear reactors, but critics argue it could be at least 50 years before a commercially viable reactorThirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago Representatives of more

393

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants January 31, 2012 - 2:09pm Addthis The Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC) released a new seismic study today that will help U.S. nuclear facilities in the central and eastern United States reassess seismic hazards. The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities model and report is the culmination of a four-year effort among the participating organizations and replaces previous seismic source models used by industry and government since the late 1980s. The NRC is requesting U.S. nuclear power plants to reevaluate seismic

394

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants January 31, 2012 - 2:09pm Addthis The Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC) released a new seismic study today that will help U.S. nuclear facilities in the central and eastern United States reassess seismic hazards. The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities model and report is the culmination of a four-year effort among the participating organizations and replaces previous seismic source models used by industry and government since the late 1980s. The NRC is requesting U.S. nuclear power plants to reevaluate seismic

395

A Review of Power Outages and Restoration Following the June 2012 Derecho  

Energy.gov (U.S. Department of Energy (DOE))

This report reviews power outages and restoration efforts following the June 29, 2012 Derecho and compares them to outages and restoration efforts following other spring and summer storms in the...

396

Notification of Planned 230kV Outage at Potomac River Generating...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to provide notification of any and all 230kV planned and unplanned outages at Potomac River Generating Station. Notification of Planned 230kV Outage at Potomac River Generating...

397

Process Data Network Architecture Plan for the Browns Ferry Nuclear Plants  

Science Conference Proceedings (OSTI)

Computer networks are essential in efficiently managing the large volumes of data used in power plant operation. Nuclear plants, however, have been cautious in applying computer technology because of their unique safety, security, and regulatory requirements. This report describes a strategic plan developed to manage the evolution of the network that processes real-time operating data for Tennessee Valley Authority's Browns Ferry nuclear plants.

1994-01-01T23:59:59.000Z

398

Time-Limited Aging Analysis Report for the Edwin I. Hatch Nuclear Power Plant  

Science Conference Proceedings (OSTI)

The option to operate a nuclear power plant beyond its initial license term of 40 years is an important factor in financial decisions and long-term planning for utility asset management and capital improvement. Southern Company has submitted an application for the renewal of its operating licenses for the E. I. Hatch Nuclear Power Plant. As part of the application preparation process, Southern Company has reviewed its design and licensing basis for Plant Hatch for time-limited, aging-related assumptions....

2000-04-11T23:59:59.000Z

399

Impact of Nuclear Power Plant Operations on Carbon-14 Generation, Chemical Forms, and Release  

Science Conference Proceedings (OSTI)

As nuclear power plants continue to implement best practices to reduce the total radioactivity in plant effluents, other radionuclides that were not previously significant fractions of the effluent streams will need to be quantified and reported. Carbon-14 can become a principal radionuclide for the gaseous effluent pathway as the concentrations of other radionuclides decrease. This report documents the potential opportunities for further understanding the impact of nuclear power plant operations on Carb...

2011-12-08T23:59:59.000Z

400

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Summary of Nuclear Power Plant Operating Experience forResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, A.V.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Mitigation of Animal-Caused Outages For Distribution Lines and Substations  

Science Conference Proceedings (OSTI)

A significant number of electric outages throughout North America are caused by animals -- mammals, birds, snakes, etc. These animal-caused outages are increasingly common in both urban and residential areas. By taking a pro-active approach to mitigating outages, utilities will spare the lives of wildlife and address the increasing pressures from environmental groups and concerned utility customers. This document describes a study designed to mitigate animal-caused outages for distribution lines and subs...

1999-12-20T23:59:59.000Z

402

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

Nero, jA.V.

2010-01-01T23:59:59.000Z

403

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Response Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, jA.V.

2010-01-01T23:59:59.000Z

404

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

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

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

2010-12-01T23:59:59.000Z

405

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

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

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

2007-01-01T23:59:59.000Z

406

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

Science Conference Proceedings (OSTI)

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

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

2010-09-01T23:59:59.000Z

407

Safeguards Issues at Nuclear Reactors and Enrichment Plants  

SciTech Connect

The Agency's safeguards technical objective is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection.

Boyer, Brian D [Los Alamos National Laboratory

2012-08-15T23:59:59.000Z

408

Thermal-Fluid Characterizations of ZnO and SiC Nanofluids for Advanced Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Technical Paper / Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics

In Cheol Bang; Ji Hyun Kim

409

Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report  

Science Conference Proceedings (OSTI)

The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

Ritterbusch, S.E.

2000-08-01T23:59:59.000Z

410

96 IEEE power & energy magazine march/april 2005 THE MASSIVE POWER OUTAGE OF  

E-Print Network (OSTI)

of power outages. These devices, which came into play during last year's blackout, typically perform for more outages and the increased cost of out- ages at the consumer level. We can-- and must96 IEEE power & energy magazine march/april 2005 T THE MASSIVE POWER OUTAGE OF August 2003

Amin, S. Massoud

411

A Framework and Review of Customer Outage Costs: Integration and Analysis of  

E-Print Network (OSTI)

by Region, Season, Day of Week, and Year 36 Table 5-2. Average Outage Costs by Duration 36 Table 5, if a calculation of the average outage cost for a given year is calculated it would be heavily influenced and Day of Week and Year of Study This problem surfaces for many of the calculations of outage costs

412

Environmental determinants of unscheduled residential outages in the electrical power distribution of Phoenix, Arizona  

E-Print Network (OSTI)

problem. We model electric interruptions using outage data between the years of 2002 and 2005 across, and interactions between the two. We model electric interruptions using outage data for the years 2002;22:117­21. [14] Fritts TH. Economic costs of electrical system instability and power outages caused by snakes

413

DOE Seeks Additional Input on Next Generation Nuclear Plant | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Seeks Additional Input on Next Generation Nuclear Plant Seeks Additional Input on Next Generation Nuclear Plant DOE Seeks Additional Input on Next Generation Nuclear Plant April 17, 2008 - 10:49am Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) today announced it is seeking public and industry input on how to best achieve the goals and meet the requirements for the Next Generation Nuclear Plant (NGNP) demonstration project work at DOE's Idaho National Laboratory. DOE today issued a Request for Information and Expressions of Interest from prospective participants and interested parties on utilizing cutting-edge high temperature gas reactor technology in the effort to reduce greenhouse gas emissions by enabling nuclear energy to replace fossil fuels used by industry for process heat. "This is an opportunity to advance the development of safe, reliable, and

414

Letter to NEAC to Review the Next Generation Nuclear Plant Activities |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to NEAC to Review the Next Generation Nuclear Plant to NEAC to Review the Next Generation Nuclear Plant Activities Letter to NEAC to Review the Next Generation Nuclear Plant Activities The Next Generation Nuclear Plant (NGNP) project was established under the Energy Policy Act in August 2005 (EPACT-2005). EPACT-2005 defined an overall plan and timetable for NGNP research, design, licensing, construction and operation by the end of FY 2021. At the time that EPACT-2005 was passed, it was envisioned that key aspects of the project included: NGNP is based on R&D activities supported by the Gen-IV Nuclear Energy initiative; ï‚· NGNP is to be used to generate electricity, to produce hydrogen or (to do) both; ï‚· The Idaho National Laboratory (INL) will be the lead national lab for the project; ï‚· NGNP will be sited at the INL in

415

Information Foraging in Nuclear Power Plant Control Rooms  

SciTech Connect

nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

R.L. Boring

2011-09-01T23:59:59.000Z

416

Small break LOCA analysis for Maanshan nuclear power plant  

SciTech Connect

Since 1990, Taiwan Power Company has conducted a LWR LOCA technology transfer program on RELAP5YA computer code from Yankee Atomic Electric Company (YAEC). One objective of this program is to acquire the RELAP5YA computer code from YAEC for Taipower in-house licensing analysis. The RELAP5YA is a computer program developed at YAEC for analysing the dynamic behaviour of thermal-hydraulic systems, and it can cover most of the postulated accidents and transients in light water reactor systems. In this paper, Taipower`s engineers have performed a small break loss of coolant accidents analysis for Maanshan nuclear power plant. Thais action is used to perform the licensing actions for increasing the operation margin on the steam generator tube plugging. The result is shown that the steam generator tube can be plugged slightly without a reduction in safety margins. This analysis covers a spectrum of break size for a small break LOCA. For a complete spectrum of the transient and accident analysis, the large break LOCA and the non-LOCA analysis were performed by the fuel vendor for the reload safety evaluation.

Jer-Cherng Kang; Shou-Chuan Chiang; Lang-Chen Wang [Taiwan Power Company, Taipei (China)

1994-12-31T23:59:59.000Z

417

Aging assessment of surge protective devices in nuclear power plants  

SciTech Connect

An assessment was performed to determine the effects of aging on the performance and availability of surge protective devices (SPDs), used in electrical power and control systems in nuclear power plants. Although SPDs have not been classified as safety-related, they are risk-important because they can minimize the initiating event frequencies associated with loss of offsite power and reactor trips. Conversely, their failure due to age might cause some of those initiating events, e.g., through short circuit failure modes, or by allowing deterioration of the safety-related component(s) they are protecting from overvoltages, perhaps preventing a reactor trip, from an open circuit failure mode. From the data evaluated during 1980--1994, it was found that failures of surge arresters and suppressers by short circuits were neither a significant risk nor safety concern, and there were no failures of surge suppressers preventing a reactor trip. Simulations, using the ElectroMagnetic Transients Program (EMTP) were performed to determine the adequacy of high voltage surge arresters.

Davis, J.F.; Subudhi, M. [Brookhaven National Lab., Upton, NY (United States)] [Brookhaven National Lab., Upton, NY (United States); Carroll, D.P. [Florida Univ., Gainesville, FL (United States)] [Florida Univ., Gainesville, FL (United States)

1996-01-01T23:59:59.000Z

418

A framework and review of customer outage costs: Integration and analysis of electric utility outage cost surveys  

E-Print Network (OSTI)

Std Dev Cost Per Annual Cost Per kWh Usage Peak kW AverageStd Dev Cost Per Annual Cost Per kWh Usage Peak kW Average3-2. Logged Outage Cost per Annual kWh Figure 3-3. Logged

Lawton, Leora; Sullivan, Michael; Van Liere, Kent; Katz, Aaron; Eto, Joseph

2003-01-01T23:59:59.000Z

419

A framework and review of customer outage costs: Integration and analysis of electric utility outage cost surveys  

Science Conference Proceedings (OSTI)

A clear understanding of the monetary value that customers place on reliability and the factors that give rise to higher and lower values is an essential tool in determining investment in the grid. The recent National Transmission Grid Study recognizes the need for this information as one of growing importance for both public and private decision makers. In response, the U.S. Department of Energy has undertaken this study, as a first step toward addressing the current absence of consistent data needed to support better estimates of the economic value of electricity reliability. Twenty-four studies, conducted by eight electric utilities between 1989 and 2002 representing residential and commercial/industrial (small, medium and large) customer groups, were chosen for analysis. The studies cover virtually all of the Southeast, most of the western United States, including California, rural Washington and Oregon, and the Midwest south and east of Chicago. All variables were standardized to a consistent metric and dollar amounts were adjusted to the 2002 CPI. The data were then incorporated into a meta-database in which each outage scenario (e.g., the lost of electric service for one hour on a weekday summer afternoon) is treated as an independent case or record both to permit comparisons between outage characteristics and to increase the statistical power of analysis results. Unadjusted average outage costs and Tobit models that estimate customer damage functions are presented. The customer damage functions express customer outage costs for a given outage scenario and customer class as a function of location, time of day, consumption, and business type. One can use the damage functions to calculate outage costs for specific customer types. For example, using the customer damage functions, the cost experienced by an ''average'' customer resulting from a 1 hour summer afternoon outage is estimated to be approximately $3 for a residential customer, $1,200 for small-medium commercial and industrial customer, and $82,000 for large commercial and industrial customer. Future work to improve the quality and coverage of information on the value of electricity reliability to customers is described.

Lawton, Leora; Sullivan, Michael; Van Liere, Kent; Katz, Aaron; Eto, Joseph

2003-11-01T23:59:59.000Z

420

Department of Energy to Co-Sponsor Workshop on Nuclear Power Plant Life Extension R&D  

Energy.gov (U.S. Department of Energy (DOE))

The U.S. Department of Energy (DOE), U.S. Nuclear Regulatory Commission (NRC), and the Nuclear Energy Institute (NEI) will co-sponsor a “Second Workshop on U.S. Nuclear Power Plant Life Extension Research and Development.”

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability  

SciTech Connect

This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

1986-03-01T23:59:59.000Z

422

Proceedings: EPRI/NEI Technical Information Workshop - Nuclear Plant Groundwater Monitoring  

Science Conference Proceedings (OSTI)

The EPRI Groundwater Protection Workshop focused on the subject of groundwater monitoring related to nuclear plant sites. This subject is very important to both decommissioning and operating plants. The Workshop provided information to assist operating plants in the development of technically sound plant site groundwater monitoring programs. Presentations provided the latest information on groundwater assessments, such as related tools, strategies, technologies and experience. The program included inform...

2007-07-19T23:59:59.000Z

423

Reducing Duration of Refueling Outage by Optimizing Core Design and Shuffling Sequence  

SciTech Connect

Reducing the duration of refueling outage is possible by optimizing the core design and the shuffling sequence. For both options software tools have been developed that have been applied to the three most recent cycles of the Borssele plant in the Netherlands. Applicability of the shuffling sequence optimization to boiling water reactors has been demonstrated by a comparison to a recent shuffle plan used in the Hatch plant located in the United States. Their uses have shown that both core design and shuffling sequence optimization can be exploited to reduce the time needed for reloading a core with an in-core shuffling scheme. Ex-core shuffling schemes for pressurized water reactors can still have substantial benefit from a core design using a minimized number of insert shuffles.

Wakker, P.H.; Verhagen, F.C.M.; Bloois, J.T. van; Sutton, W.R. III

2005-07-15T23:59:59.000Z

424

Future AI and Robotics Technology for Nuclear Plants Decommissioning  

E-Print Network (OSTI)

Robotics Program The Robotics Program within the Nuclear Engineering Division is developing new technologies. Currently, we are exploring opportunities in applications for nuclear reactor operation, maintenance of remote energy installations, decontamination and decommissioning, and minimally invasive surgery

Hu, Huosheng

425

Assessment of next generation nuclear plant intermediate heat exchanger design.  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made an assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. A detailed thermal hydraulic analysis, using models developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop. Two IHX designs namely, shell and straight tube and compact heat exchangers were considered in an earlier assessment. Helical coil heat exchangers were analyzed in the current report and the results were compared with the performance features of designs from industry. In addition, a comparative analysis is presented between the shell and straight tube, helical, and printed circuit heat exchangers from the standpoint of heat exchanger volume, primary and secondary sides pressure drop, and number of tubes. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses were performed for the helical heat exchanger design and the results were compared with earlier-developed results on shell and straight tube and printed circuit heat exchangers.

Majumdar, S.; Moisseytsev, A.; Natesan, K.; Nuclear Engineering Division

2008-10-17T23:59:59.000Z

426

Notification of Planned 230kV Outage at Potomac River Generating Station |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Notification of Planned 230kV Outage at Potomac River Generating Notification of Planned 230kV Outage at Potomac River Generating Station Notification of Planned 230kV Outage at Potomac River Generating Station Docket No. EO-05-01. In accordance with DOE Order No. 202-05-03 Pepco is required to provide notification of any and all 230kV planned outages at Potomac River Generating Station. On Tuesday February 20, 2007 Potomac Electric Power Company (Pepco) will be taking a planned outage on the 23106 high voltage circuit between the Palmer's Corner Substation and the Potomac River Generating Station. Notification of Planned 230kV Outage at Potomac River Generating Station More Documents & Publications Re: Potomac River Generating Station Department of Energy Case No. EO-05-01: Advanced Notice of Power Outages. Special Environmental Analysis For Actions Taken under U.S. Department of

427

Further Notice of 230kV Circuit Planned Outages | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Further Notice of 230kV Circuit Planned Outages Further Notice of 230kV Circuit Planned Outages Further Notice of 230kV Circuit Planned Outages Docket No. EO-05-01. Order No. 202-05-03: Pursuant 10 the United States Department of Energy "DOE") Order No. 102-05-3, issued December 20, 2005 ("DOE Potomac River Order''), Pepco hereby files this Further Notice Of 230kV Circuit Planned Outages serving the Potomac River Substation, and through thaI station, the District of Columbia. Further Notice of 230kV Circuit Planned Outages More Documents & Publications Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac Electric Power Company (PEPCO) Concerning Planned Outages of the 230 kV circuits Docket No. EO-05-01: Further Notice of 230kV Circuit Planned Outages

428

Further Notice of 230kV Circuit Planned Outages | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Further Notice of 230kV Circuit Planned Outages Further Notice of 230kV Circuit Planned Outages Further Notice of 230kV Circuit Planned Outages Docket No. EO-05-01. Order No. 202-05-03: Pursuant 10 the United States Department of Energy "DOE") Order No. 102-05-3, issued December 20, 2005 ("DOE Potomac River Order''), Pepco hereby files this Further Notice Of 230kV Circuit Planned Outages serving the Potomac River Substation, and through thaI station, the District of Columbia. Further Notice of 230kV Circuit Planned Outages More Documents & Publications Docket No. EO-05-01: Further Notice of 230kV Circuit Planned Outages Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac Electric Power Company (PEPCO) Concerning Planned Outages of the 230 kV circuits

429

Plant maintenance and advanced reactors, 2005  

SciTech Connect

The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: First U.S. EPRs in 2015, by Ray Ganthner, Framatome ANP; Pursuing several opportunities, by William E. (Ed) Cummins, Westinghouse Electric Company; Vigorous plans to develop advanced reactors, by Yuliang Sun, Tsinghua University, China; Multiple designs, small and large, by Kumiaki Moriya, Hitachi Ltd., Japan; Sealed and embedded for safety and security, by Handa Norihiko, Toshiba Corporation, Japan; Scheduled online in 2010, by Johan Slabber, PMBR (Pty) Ltd., South Africa; Multi-application reactors, by Nikolay G. Kodochigov, OKBM, Russia; Six projects under budget and on schedule, by David F. Togerson, AECL, Canada; Creating a positive image, by Scott Peterson, Nuclear Energy Institute (NEI); Advanced plans for nuclear power's renaissance, by John Cleveland, International Atomic Energy Agency, Austria; and, Plant profile: last five outages in less than 20 days, by Beth Rapczynski, Exelon Nuclear.

Agnihotri, Newal (ed.)

2005-09-15T23:59:59.000Z

430

Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1  

Science Conference Proceedings (OSTI)

This report was prepared in response to regulatory and management concern regarding the reliability of medium-voltage cable systems at nuclear plants. The staff of the U.S. Nuclear Regulatory Commission (NRC) have been concerned that wetted (up to and including submergence) medium-voltage cable circuits may be degrading to the point at which multiple cable circuits may fail when called on to perform functions affecting safety. A utility manager’s concern is that cables may fail, causing ...

2013-06-03T23:59:59.000Z

431

Identification of hazards in non-nuclear power plants. Volume II. Phase II  

DOE Green Energy (OSTI)

This study extends the Phase I study to also include a hazards evaluation for two new emerging coal power plant technologies: coal fired atmospheric fluidized bed and pressurized fluidized bed power generating systems. The study also considers the sensitivity of the hazards ranking for all the non-nuclear power plants to the effects of population density, mode of plant operation, technical changes, location and environmental (temperature) effects. Information is provided under the following section headings: background; environmental and public health concerns associated with fluidized-bed combustion power plants; description of a conceptual atmospheric fluidized-bed power plant; pressurized fluidized-bed combustion combined cycle (PFBCC) power plant; hazard ranking and risk assessment for non-nuclear power plants; and, hazards sensitivity analysis.

Fell, R.W.

1979-08-01T23:59:59.000Z

432

Mathematical model of steam generator feed system at power unit of nuclear plant  

Science Conference Proceedings (OSTI)

A mathematical model of a steam generator feed system at a power unit of a nuclear plant with variable values of transfer function coefficients is presented. The model is realized in the MATLAB/Simulink/Stateflow event-driven simulation.

E. M. Raskin; L. A. Denisova; V. P. Sinitsyn; Yu. V. Nesterov

2011-05-01T23:59:59.000Z

433

A holistic investigation of complexity sources in nuclear power plant control rooms  

E-Print Network (OSTI)

The nuclear power community in the United States is moving to modernize aging power plant control rooms as well as develop control rooms for new reactors. New generation control rooms, along with modernized control rooms, ...

Sasangohar, Farzan

2011-01-01T23:59:59.000Z

434

Guidelines for the Technical Evaluation of Replacement Items in Nuclear Power Plants (NCIG-11)  

Science Conference Proceedings (OSTI)

Using a systematic technical evaluation process, utilities can ensure that replacement parts for nuclear power plants are equivalent to the originals. Guidelines developed by EPRI and NCIG provide practical information and a systematic approach to procurement.

1990-01-08T23:59:59.000Z

435

Probabilistic methods in seismic risk assessment for nuclear power plants: proceedings  

SciTech Connect

The state-of-the-art in seismic risk analysis applied to the design and siting of nuclear power plants was addressed in this meeting. Presentations were entered individually into the date base. (ACR)

Not Available

1983-01-01T23:59:59.000Z

436

Losses of Offsite Power at U.S. Nuclear Power Plants - 2011  

Science Conference Proceedings (OSTI)

This report describes the loss of offsite power experience at U.S. nuclear power plants during the year 2011 and provides insights into the causes of offsite power losses during the period 2002–2011.

2012-06-11T23:59:59.000Z

437

DC power transmission from the Leningradskaya Nuclear Power Plant to Vyborg  

SciTech Connect

DC power transmission from the Leningradskaya Nuclear Power Plant (LAES) to city of Vyborg is proposed. This will provide a comprehensive solution to several important problems in the development and control of the unified power system (EES) of Russia.

Koshcheev, L. A. [JSC 'NIIPT' (Russian Federation); Shul'ginov, N. G. [JSC 'SO EES' (Russian Federation)

2011-05-15T23:59:59.000Z

438

How much spent (used) fuel is stored at U.S. nuclear power plants ...  

U.S. Energy Information Administration (EIA)

How much spent (used) fuel is stored at U.S. nuclear power plants? In 2002, the most recent year for which EIA has data, there were 161,662 fuel assemblies, or 46,268 ...

439

A Software Configuration Management System for the Maintenance of Nuclear Power Plant Simulators  

Science Conference Proceedings (OSTI)

This paper reports on the KSG experiencies to introduce a configuration management system for the maintenance of nuclear power plant simulator software. After a discussion on the KSG specific requirements on a computer based software configuration management ...

Burkhard Holl

1997-03-01T23:59:59.000Z

440

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications  

Science Conference Proceedings (OSTI)

This report documents the verification and validation (VV) of five selected fire models commonly used in support of risk-informed and performance-based (RI/PB) fire protection at nuclear power plants (NPPs).

2007-05-30T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Fire Events Database for U.S. Nuclear Power Plants: Update Through 1999  

Science Conference Proceedings (OSTI)

This report documents an update to the EPRI Fire Events Database for U.S. Nuclear Power Plants. This database was last published in January 1993 as NSAC-178L.

2000-10-19T23:59:59.000Z

442

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward  

SciTech Connect

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

John Collins

2009-01-01T23:59:59.000Z

443

HPSS Outage Tue Mar 19 - Fri Mar 22  

NLE Websites -- All DOE Office Websites (Extended Search)

HPSS HPSS Outage Tue Mar 19 - Fri Mar 22 HPSS Outage Tue Mar 19 - Fri Mar 22 March 12, 2013 by Francesca Verdier (0 Comments) The NERSC HPSS "User" system (archive.nersc.gov) will be down for four days from Tue Mar 19 07:00 to Fri Mar 22 17:00). The system will be upgraded from HPSS version 6.2 to version 7.3. This new version of the HPSS server software is not compatible with current GridFTP servers. This means the NERSC HPSS systems will not support any grid-based transfer methods (including GlobusOnline) following the upgrade. We expect to install a fix for this problem during a scheduled downtime by the end of April. This is a major upgrade that will require users of the HPSS User system to switch to new versions of the HPSS client software tools hsi and htar.

444

Integration of Biorefineries and Nuclear Cogeneration Power Plants - A Preliminary Analysis  

SciTech Connect

Biomass-based ethanol and nuclear power are two viable elements in the path to U.S. energy independence. Numerous studies suggest nuclear power could provide a practical carbon-free heat source alternative for the production of biomass-based ethanol. In order for this coupling to occur, it is necessary to examine the interfacial requirements of both nuclear power plants and bioethanol refineries. This report describes the proposed characteristics of a small cogeneration nuclear power plant, a biochemical process-based cellulosic bioethanol refinery, and a thermochemical process-based cellulosic biorefinery. Systemic and interfacial issues relating to the co-location of either type of bioethanol facility with a nuclear power plant are presented and discussed. Results indicate future co-location efforts will require a new optimized energy strategy focused on overcoming the interfacial challenges identified in the report.

Greene, Sherrell R [ORNL; Flanagan, George F [ORNL; Borole, Abhijeet P [ORNL

2009-03-01T23:59:59.000Z

445

Sun-Sentinel How Florida's nuclear plants compare to Japan's  

E-Print Network (OSTI)

Point plant near Miami and two at its plant in St. Lucie County. Progress has one near Crystal River operation began," said FPL Spokesman Mike Waldron. #12;Progress Energy's Crystal River reactor and one was an effort to wrap up the issue at the Crystal River plant. "Was the company merely unlucky

Belogay, Eugene A.

446

Model validation for the August 10, 1996 WSCC system outage  

SciTech Connect

A major power outage occurred in western North America on August 10, 1996. In this paper the authors describe simulation of the disturbance using a transient stability program. Initially, the sequence of events was simulated using the standard WSCC dynamic data base, and the simulations did not agree with the disturbance recordings. Several model additions and data modifications were made before the simulations approximated the disturbance recordings. These model changes are discussed in the paper.

Kosterev, D.N.; Taylor, C.W.; Mittelstadt, W.A. [Bonneville Power Administration, Portland, OR (United States). Transmission Operations and Planning

1999-08-01T23:59:59.000Z

447

Common Information Model Meter Outage Nominal Interoperability Test Procedure  

Science Conference Proceedings (OSTI)

The CIM Meter Outage Nominal Interoperability Test Procedure is one in a series of EPRI CIM Interoperability Test Procedures (ETIPs) created by EPRI whose purpose is to thoroughly document the actors, interfaces, and test steps for the interoperability testing of specific parts of the International Electrotechnical Commission (IEC) Common Information Model (CIM) standard. The Test Procedures are initially being used for EPRI demonstration tests and are intended, over time, to form the basis of a set of C...

2011-12-16T23:59:59.000Z

448

Examination of the Exacter Outage-Avoidance System  

Science Conference Proceedings (OSTI)

A routine inspection program is one tool that utilities can use to reduce failures on their circuits and minimize customer outages. By identifying problems for repair before they develop into failures, an inspection program can be a cost-effective method for enhancing the quality and reliability of electric service. The present methods used to detect and locate underperforming power system hardware can be time consuming and can involve physical complexities and require line crews with bucket trucks to tr...

2009-11-30T23:59:59.000Z

449

Assessment of Seismic Hazard at 34 U.S. Nuclear Plant Sites  

Science Conference Proceedings (OSTI)

Interest in recent years in early site permits (ESPs) for new nuclear plants has prompted a reevaluation of seismic design criteria and a reexamination of the basis for current criteria. Currently, Regulatory Guide 1.208 bases seismic design requirements on a performance-based approach using probabilistic seismic hazard analysis (PSHA). The performance-based approach was based on PSHA results at 29 nuclear plant sites, using results that were published in 1989 and 1994. These results were supported by pr...

2008-08-27T23:59:59.000Z

450

Study of the potential uses of the Barnwell Nuclear Fuel Plant (BNFP). Final report  

Science Conference Proceedings (OSTI)

The purpose of this study is to provide an evaluation of possible international and domestic uses for the Barnwell Nuclear Fuel Plant, located in South Carolina, at the conclusion of the International Nuclear Fuel Cycle Evaluation. Four generic categories of use options for the Barnwell plant have been considered: storage of spent LWR fuel; reprocessing of LWR spent fuel; safeguards development and training; and non-use. Chapters are devoted to institutional options and integrated institutional-use options.

Not Available

1980-03-25T23:59:59.000Z

451

Characterization and Dose Modeling of Soil, Sediment and Bedrock During Nuclear Power Plant Decommissioning  

Science Conference Proceedings (OSTI)

A decommissioning nuclear power plant must confirm that the radionuclides present in the soils, sediments, and bedrock left on site at the time of license termination will meet the appropriate dose limits for site release. This process involves the characterization, dose modeling, and if required, remediation, of these media. At some decommissioning nuclear power plants, the management of contaminated soil, sediments, and bedrocks was a major project that led to generation of remediation projects and rad...

2009-11-20T23:59:59.000Z

452

Jose Cabrera Nuclear Power Plant Full System Chemical Decontamination Experience Report  

Science Conference Proceedings (OSTI)

Chemical decontamination is one of the key challenging tasks of decommissioning a nuclear power plant. This report describes a full system chemical decontamination at SpainJosCabrera Nuclear Power Plant that sought to facilitate future dismantling by removing contamination and lowering radiation fields. Because of several unique features of the JosCabrera decontamination project, it has provided new good practices and useful lessons learned.

2009-11-17T23:59:59.000Z

453

Aging Management Guidelines for Commercial Nuclear Power Plants -- Electrical and Mechanical Penetrations  

Science Conference Proceedings (OSTI)

As part of the application process for license renewal, nuclear utilities must perform an evaluation to confirm that they have appropriately considered aging effects on plant components within the scope of the License Renewal Rule. This report provides guidelines for managing relevant degradation mechanisms applicable to electrical and mechanical penetrations in nuclear power plants. Use of these guidelines will provide utilities with a basis for verifying that effective methods for managing age-related ...

2002-04-25T23:59:59.000Z

454

Technical Guideline for Cyber Security Requirements and Life Cycle Implementation Guidelines for Nuclear Plant Digital Systems  

Science Conference Proceedings (OSTI)

Nuclear power plants face increasing regulatory requirements from the U.S. Nuclear Regulatory Commission (NRC) and the Federal Energy Regulatory Commission (FERC) for cyber security of digital devices, components, and systems. The focus of these cyber security requirements is to protect plant digital computer systems, communications systems, and networks from cyber attacks that would affect reactor safety or generation reliability. This EPRI guideline document provides technical guidance for addressing c...

2010-10-29T23:59:59.000Z

455

Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant  

SciTech Connect

The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents.

Perkins, W.C.; Durant, W.S.; Dexter, A.H.

1980-12-01T23:59:59.000Z

456

Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report  

Science Conference Proceedings (OSTI)

OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

NONE

2000-08-01T23:59:59.000Z

457

Incentive regulation of nuclear power plants by state public utility commissions  

Science Conference Proceedings (OSTI)

This report on incentive regulation of nuclear power plants by state public utility commissions (PUCs). Economic performance incentives established by state PUCs are applicable to the construction or operation of about 45 nuclear power reactors owned by 30 utilities in 17 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant.

Petersen, J.C.

1987-12-01T23:59:59.000Z

458

Incentive regulation of nuclear power plants by state Public Utility Commissions  

Science Conference Proceedings (OSTI)

Economic performance incentives established by state Public Utility Commissions (PUCs) currently are applicable to the construction or operation of approximately 73 nuclear power reactors owned by 27 utilities with investment greater than 10% in 18 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its headquarters and regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report on incentive regulation of nuclear power plants by state PUCs presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant.

Martin, R.L.; Olson, J. (Battelle Human Affairs Research Center, Seattle, WA (USA)); Hendrickson, P. (Pacific Northwest Lab., Richland, WA (USA))

1989-12-01T23:59:59.000Z

459

Risk Assessment of Cascading Outages: Methodologies and Challenges  

Science Conference Proceedings (OSTI)

Abstract- This paper is a result of ongoing activity carried out by Understanding, Prediction, Mitigation and Restoration of Cascading Failures Task Force under IEEE Computer Analytical Methods Subcommittee (CAMS). The task force's previous papers are focused on general aspects of cascading outages such as understanding, prediction, prevention and restoration from cascading failures. This is the first of two new papers, which extend this previous work to summarize the state of the art in cascading failure risk analysis methodologies and modeling tools. This paper is intended to be a reference document to summarize the state of the art in the methodologies for performing risk assessment of cascading outages caused by some initiating event(s). A risk assessment should cover the entire potential chain of cascades starting with the initiating event(s) and ending with some final condition(s). However, this is a difficult task and heuristic approaches and approximations have been suggested. This paper discusses different approaches to this and suggests directions for future development of methodologies. The second paper summarizes the state of the art in modeling tools for risk assessment of cascading outages.

Vaiman, Marianna; Bell, Keith; Chen, Yousu; Chowdhury, Badrul; Dobson, Ian; Hines, Paul; Papic, Milorad; Miller, Stephen; Zhang, Pei

2012-05-31T23:59:59.000Z

460

Outage-Efficient Downlink Transmission Without Transmit Channel State Information  

E-Print Network (OSTI)

This paper investigates downlink transmission over a quasi-static fading Gaussian broadcast channel (BC), to model delay-sensitive applications over slowly time-varying fading channels. System perfor-mance is characterized by outage achievable rate regions. In contrast to most previous work, here the problem is studied under the key assumption that the transmitter only knows the probability distributions of the fading coefficients, but not their realizations. For scalar-input channels, two coding schemes are proposed. The first scheme is called blind dirty paper coding (B-DPC), which utilizes a robustness property of dirty paper coding to perform precoding at the transmitter. The second scheme is called statistical superposition coding (S-SC), in which each receiver adaptively performs successive decoding with the process statistically governed by the realized fading. Both B-DPC and S-SC schemes lead to the same outage achievable rate region, which always dominates that of time-sharing, irrespective of the particular fading distributions. The S-SC scheme can be extended to BCs with multiple transmit antennas. Index Terms Broadcast channel, (blind) dirty paper coding, downlink, non-ergodic fading, outage achievable rate region, quasi-static fading, (statistical) superposition coding

Wenyi Zhang; Shivaprasad Kotagiri; Student Member; J. Nicholas Laneman; Senior Member

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Nuclear Maintenance Applications Center: Application Guide for Motor-Operated Valves in Nuclear Power Plants - Revision 2  

Science Conference Proceedings (OSTI)

Motor-operated gate and globe valves are widely used in both safety-related and non-safety-related systems in nuclear power plants. Their proper operation is essential for reliable plant performance and can help eliminate costly downtime. This second revision of the Application Guide for Motor-Operated Valves provides the latest in methods for conducting engineering evaluations in order to confirm that motor-operated gate, globe, and butterfly valves will perform their required function and offers sugges...

2007-08-22T23:59:59.000Z

462

Abstract--Cascading outages can cause large blackouts, and a variety of methods are emerging to study this challenging topic.  

E-Print Network (OSTI)

1 Abstract-- Cascading outages can cause large blackouts, and a variety of methods are emerging Analysis, Risk Analysis, Preventing Cascades. I. INTRODUCTION A cascading outage is a sequence of events component outages (based on [1] and [2]). In some cases cascading outages halt before the sequence results

Hines, Paul

463

Trial Plant Review of an American Nuclear Society External Event Probabilistic Risk Assessment Standard  

Science Conference Proceedings (OSTI)

This study examined a representative set of Seismic Probabilistic Risk Assessments (SPRAs) and Seismic Margin Assessments (SMAs) performed for U.S. nuclear plants and evaluated them against the American Nuclear Society's draft External-Event PRA Methodology Standard for conducting Probabilistic Risk Assessment of external events.

2003-09-22T23:59:59.000Z

464

Qualification of safety-critical systems in TVO nuclear power plants  

Science Conference Proceedings (OSTI)

Teollisuuden Voima Oy (TVO) operates two nuclear power plant units in Finland and has started to build a third one. The current nuclear power units have to continuously maintain and update existing instrumentation and control systems (I&C). Each new ... Keywords: FMECA, SPICE, instrumentation and control, qualification, safety-critical systems

Juha Halminen; Risto Nevalainen

2007-11-01T23:59:59.000Z

465

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

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

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

2004-06-01T23:59:59.000Z

466

Nuclear norm minimization for the planted clique and biclique ...  

E-Print Network (OSTI)

Jan 21, 2009 ... Both problems are NP-hard. We write both problems as matrix-rank minimization and then relax them using the nuclear norm. This technique ...

467

The Management of Aging in Nuclear Power Plant Concrete Structures  

Science Conference Proceedings (OSTI)

An example of application of structural reliability theory to investigate the impact of ... Cladding and Duct Materials for Advanced Nuclear Recycle Reactors

468

Program on Technology Innovation: Information Integration for Equipment Reliability at Nuclear Plants  

Science Conference Proceedings (OSTI)

This report investigates the status of information integration for equipment reliability (ER) at nuclear power plants. ER consists of a comprehensive set of processes that span the organization and require extensive data gathering, retrieval, and information integration. To assist nuclear operators, the Institute of Nuclear Power Operations (INPO) issued AP-913, Equipment Reliability Process Description, as a standard approach to implement effective ER processes among its members. Despite the success tha...

2009-04-30T23:59:59.000Z

469

Plant Support Engineering: Degradation Research for Nuclear Service Level I Coatings  

Science Conference Proceedings (OSTI)

Nuclear power plants have experienced degradation of the protective coating systems (nuclear Service Level I coatings) inside reactor containment. The degradation is a matter of concern, but the history of degradation and its causes have not been thoroughly documented. In response, the Electric Power Research Institute (EPRI) and the Nuclear Utilities Coating Council (NUCC) began a research project designed to gain an understanding of the degradation and the potential influence of aging on the qualified ...

2007-09-24T23:59:59.000Z

470

COST COMPARISONS OF CAPITOL INVESTMENT IN VARIOUS NUCLEAR POWER PLANTS FOR CENTRAL STATION APPLICATION  

SciTech Connect

The capital costs for a number of power reactors are compared after escalation to equivalent construction dates. It is shown that the most important factor affecting nuclear power plant capital costs is the net capacity of the plant. Steam conditions are shown to have a relatively minor effect on capital costs. (auth)

Bender, M.; Stulting, R.D.

1958-10-14T23:59:59.000Z

471

Assessement of Codes and Standards Applicable to a Hydrogen Production Plant Coupled to a Nuclear Reactor  

DOE Green Energy (OSTI)

This is an assessment of codes and standards applicable to a hydrogen production plant to be coupled to a nuclear reactor. The result of the assessment is a list of codes and standards that are expected to be applicable to the plant during its design and construction.

M. J. Russell

2006-06-01T23:59:59.000Z

472

Location dependent common cause analysis with an application to fires. [Nuclear power plants  

SciTech Connect

The purpose of the work described is to develop a methodology by which the public risk arising from localized common cause events (e.g., fires) in nuclear plants can be assessed. Attention was paid to maximizing both the completeness and efficiency of the analysis. This methodology was then applied to the analysis of fire events in the Clinch River Breeder Reactor Plant (CRBRP).

Leaver, D.; vonHerrmann, J.; Olmos, J.; Boardman, R.

1978-01-01T23:59:59.000Z

473

Life Cycle Management Plan for Main Generator and Exciter at Callaway Nuclear Plant: Generic Version  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This report provides Ameren UE with an optimized LCM plan for the main generator and exciter at Callaway Plant.

2003-09-30T23:59:59.000Z

474

Exergetic analyse for the cooling systems with R-407 refrigerant for application in nuclear plants  

Science Conference Proceedings (OSTI)

The experimental Pilot plant for tritium and deuterium separation, part of National Research and Development Institute for Cryogenics and Isotopic Technologies - ICSI Rm. Valcea, as principal target have to establish the technology of the water-hydrogen ... Keywords: R407 refrigerant, irreversibility, nuclear plants, refrigeration efficiency

Sorin Gherghinescu

2010-06-01T23:59:59.000Z

475

Pre-validation of nuclear power plant control room design  

Science Conference Proceedings (OSTI)

Evaluation of the design of complex automation and control room systems is an essential phase in the design process in the nuclear field. For example, in order to meet the nuclear regulatory requirements, the new control room systems have to be evaluated ... Keywords: concept of operations, control room, pre-validation, verification & validation

Jari Laarni; Paula Savioja; Hannu Karvonen; Leena Norros

2011-07-01T23:59:59.000Z

476

Plant Support Engineering: Aging Management Program Development Guidance for Instrument and Control Cable Systems for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This document provides guidance for developing and implementing a cable aging management program for low-voltage instrument and control cable circuits in nuclear power plants. Guidance is provided for identifying cables located in adverse localized environments and determining if those environments have caused significant cable circuit degradation.

2010-11-29T23:59:59.000Z

477

Adult leukemia and proximity-based surrogates for exposure to Pilgrim plant`s nuclear emissions  

Science Conference Proceedings (OSTI)

Possible associations between adult leukemia incidence and proximity-based surrogate measures of potential for exposure to radioactive emission from the Pilgrim nuclear power plant in Plymouth, Massachusetts, were investigated. Include din this study were 105 nonchronic lymphocytic leukemia cases, diagnosed between 1978 and 1986 at age 13 y or older, that occured in 22 towns near Pilgrim; population controls numbered 208. Residence within 4 mi (6.4 km) of Pilgrim during {open_quotes}high-emissions{close_quotes} years was related to case-control status (adjusted odds ratio [OR] = 3.88, 95% confidence interval [95% Cl] = 0.81-10.64). A high {open_quotes}exposure{close_quotes} score (i.e., a value that accounted for downwind time) was also related to case-control status (OR = 3.46, 95% Cl = 1.50-7.96). Some statistically significant dose-response trends were found. Cautious interpretation of associations is warranted in light of the low levels of reported emission. 42 refs., 1 fig., 4 tabs.

Morris, M.S.; Knorr, R.S. [Massachusetts Dept. of Public Health, Boston, MA (United States)

1996-07-01T23:59:59.000Z

478

Establishing a Groundwater Protection Program for New Nuclear Generating Units: Appendix to the EPRI Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

New nuclear power plants should plan for groundwater protection early in the planning process. The construction project team should be made aware of the need to establish the groundwater protection program prior to the construction planning process. This document provides guidance for establishing Groundwater Protection Programs for new nuclear generating units. It applies to new nuclear generating units on both new and existing nuclear power plant ...

2013-03-27T23:59:59.000Z

479

Assessment of Nuclear Safety Culture at the Pantex Plant, November...  

NLE Websites -- All DOE Office Websites (Extended Search)

the Plant. Human Performance Improvement Coordinator works with the Safety Team and Human Error team from BBS to conduct human performance evaluations. B-12 Data on the...

480

Development of hydrogeological modelling approaches for assessment of consequences of hazardous accidents at nuclear power plants  

SciTech Connect

This paper introduces some modeling approaches for predicting the influence of hazardous accidents at nuclear reactors on groundwater quality. Possible pathways for radioactive releases from nuclear power plants were considered to conceptualize boundary conditions for solving the subsurface radionuclides transport problems. Some approaches to incorporate physical-and-chemical interactions into transport simulators have been developed. The hydrogeological forecasts were based on numerical and semi-analytical scale-dependent models. They have been applied to assess the possible impact of the nuclear power plants designed in Russia on groundwater reservoirs.

Rumynin, V.G.; Mironenko, V.A.; Konosavsky, P.K.; Pereverzeva, S.A. [St. Petersburg Mining Inst. (Russian Federation)

1994-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant outages" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.