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Friday, November 27, 2020 | History

5 edition of Plant Systems/Components Aging Management 1997 found in the catalog.

Plant Systems/Components Aging Management 1997

Presented at the 1997 Asme Pressure Vessels and Piping Conference, Orlando, Florida, July 27-31, 1997 (Pvp (Series), Vol. 349.)

by Quebec) Pressure Vessels and Piping Conference (1996 : Montreal

  • 399 Want to read
  • 7 Currently reading

Published by American Society of Mechanical Engineers .
Written in English

    Subjects:
  • Industrial chemistry,
  • Materials science,
  • Service life (Engineering),
  • Maintainability,
  • Congresses,
  • Technology & Industrial Arts,
  • Technology,
  • Science/Mathematics,
  • Reference,
  • Maintenance and repair,
  • Engineering - Nuclear,
  • Equipment and supplies,
  • Nuclear power plants

  • Edition Notes

    ContributionsAmerican Society of Mechanical Engineers. Pressure Vessels and Piping Division (Corporate Author), I. T. Kisisel (Editor), J. Sinnappan (Editor)
    The Physical Object
    FormatPaperback
    Number of Pages155
    ID Numbers
    Open LibraryOL7804621M
    ISBN 100791815668
    ISBN 109780791815663

    • Managed regulation driven nuclear power plant reliability, aging management and license renewal programs and projects. for all nuclear powerplant systems, structures and components Title: Extensive experience with .


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Plant Systems/Components Aging Management 1997 by Quebec) Pressure Vessels and Piping Conference (1996 : Montreal Download PDF EPUB FB2

Get this from a library. Plant systems/components aging management, presented at the ASME Pressure Vessels and Piping Conference, Orlando, Florida, July[I T Kisisel; J Sinnappan; American Society of Mechanical Engineers.

Pressure Vessels and Piping Division.;]. A common belief in the nuclear industry is that current maintenance practices manage aging degradation. As part of the NRC`s Nuclear Plant Aging Research Program, a number of aging studies were performed on safety-related systems and components which found that, even with current maintenance and monitoring practices in place, a large number of the reported failures are related to aging.

Get this from a library. Plant systems/components aging management, presented at the Joint ASME/JSME Pressure Vessels and Piping Conference, Honolulu, Hawaii, July[I T Kisisel; T V Narayanan; American Society of Mechanical. This report defines and encourages the use of a set of common Plant Systems/Components Aging Management 1997 book and definitions that characterize aging and aging management of nuclear power plant systems, structures, and components.

Common aging terminology encompasses the areas of degradation causes, degradation/aging, life, failure, and maintenance. The terminology should prove useful.

Plant systems/components aging management PVP-Volume December I. Kisisel; T.V. Narayanan; J. Sinnappan; July A. Spiker; In a survey of 21 nuclear power plants.

3. Aging mitigation strategies for I&C components. Aging is more of a concern with major plant equipment, such as reactor vessels, containment buildings, cables, and other structures, systems, and components (SSCs) that are difficult or impossible to replace.

In contrast, equipment such as I&C systems can be replaced as often as necessary. A common denominator to many of these challenges is the aging of plant systems, structures, and components.

Aging issues have contributed to a drastically altered economical feasibility model of some units. There are many plant assets for which aging effects must be assessed and managed. Aging assessment and the strategic aging management of.

“A Life Extension Evaluation for the Oconee Unit 1 Reactor Vessel Internals,” S. Fyfitch, G. Vames, and G. Robinson, ASME-PVPD-OAC, Nuclear Plant Systems/Components Aging Management and Life Extension Conference, San Diego, CA, June 23–27, Google Scholar.

Abstract: A study for the Nuclear Regulatory Commission was recently undertaken to identify effective maintenance practices that could be adapted by the nuclear industry in the United States to assist in managing the aging degradation of plant systems and components.

Four organizations were examined to assess the influence of maintenance programs on addressing the system and component aging. Managing Plant Systems/Components Aging Management 1997 book aging of digital control systems ensures that nuclear power plant systems are in adequate safety margins during their life cycles.

Software is a core component in the execution of control logic and differs between digital and analog control systems. The hardware aging management for the digital control system is similar to that for the analog system, which has. Edited by Sinnappan, Meligi, Narayanan, Bond, Power Plant Systems/Components Aging Management and Life Extension,PVP-Vol.

ISBN Google Scholar 3. Edited by Shah, Macdonald, Aging and Life Extension of Major Light Water Reactor Components,ISBN Google Scholar. Get this from a library.

Plant systems/components aging management, presented at the Pressure Vessels and Piping Conference, Minneapolis, Minnesota, June[I T Kisisel; R L Kurtz; J Sinnappan; T V Narayanan; American Society of Mechanical Engineers.

Pressure Vessels and Piping Division.;]. To ensure the safe operation of nuclear power plants in the United States, it is essential to assess the effects of age-related degradation of plant structures, systems, and components. This concern becomes even more important in view of the submittals of license renewal applications to the NRC under 10 CFR Part @article{osti_, title = {Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications}, author = {Coble, Jamie B and Ramuhalli, Pradeep and Bond, Leonard J and Hines, Wes and Upadhyaya, Belle}, abstractNote = {This report reviews the current state of the art of prognostics and health management (PHM) for nuclear power systems and related.

References J. Vora, Nuclear Plant Aging Research (NPAR) Program Plan, NUREG, US Nuclear Regulatory Commission, Revision 2, June N.N. Kondic, NRC Research Program on Plant Aging: List- ing and Summaries of Reports Issues Through JulyNUREG, Revision 3, September R.

Lofaro and M. Subudhi, The Effects of Age. As existing fleets of nuclear power plants continue to seek long term operation, aging management programs have been developed to mitigate the effects of degradation processes affecting reactor components that are important to safety and generation.

Nuclear plant systems/components aging management and life extension. New York: American Society of Mechanical Engineers, © (OCoLC) Material Type: Conference publication: Document Type: Book: All Authors / Contributors: I T Kisisel; American Society of Mechanical Engineers. Pressure Vessels and Piping Division.

Conference: Aging assessment as a part of a comprehensive life cycle management program Title: Aging assessment as a part of a comprehensive life cycle management.

Nuclear Engineering and Design () North-Holland POTENTIAL APPLICATION OF NRC AGING RESEARCH TO LICENSE RENEWAL * J.P. VORA Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, USA Received: first version 20 Marchrevised version 22 August A strong technical base, when developed and implemented, to manage aging in plant safety related systems.

Get this from a library. Plant systems/components aging management, presented at the Pressure Vessels and Piping Conference, Denver, Colorado, July[I T Kisisel; American Society of Mechanical Engineers.

Pressure Vessels and Piping Division.;]. Devising optimal strategy for maintaining industrial plant can be a difficult task of daunting complexity. This book aims to provide the plant engineer with a comprehensive and systematic approach, a framework of guidelines, for tackling this problem, i.e.

for deciding maintenance objectives, formulating equipment life plans and plant maintenance schedules, designing the maintenance. Institute (EPRI) and U.S. nuclear power plant utilities, is preparing a series of aging management guidelines (AMGs) for commodity types of components (e.g., heat exchangers, electrical cable and terminations, pumps).

Commodities are included in this series based on their importance to continued nuclear plant operation and license renewal. Life Cycle Management is a structured process to manage equipment aging and long-term equipment reliability for nuclear plant Systems, Structures and Components (SSCs).

The process enables the identification of effective repair, replace, inspect, test and maintenance activities and the optimal timing of the activities to maximize the economic. @article{osti_, title = {Nuclear power plant common aging terminology.

Final report}, author = {Grant, W S and Miller, E J and Sliter, G E}, abstractNote = {This report defines and encourages the use of a set of common terms and definitions that characterize aging and aging management of nuclear power plant systems, structures, and components.

Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors.

A comprehensive Nuclear Plant Aging Research (NPAR) Program was imple-mented by the U.S. NRC Office of Nuclear Regulatory Research in to iden-tify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants.

This is Revi-sion 2 to the Nuclear Plant Aging Research Program. Aging of components within compressed air systems, leading to degraded function of the system, is the subject of this study.

This work was performed under the auspices of the NRC's Office of Nuclear Regulatory Research as part of the Nuclear Plant Aging Research (NPAR) program. The authors designed a SCWR internal components structure with combined application of Ti and N The mechanical properties and irradiation performances of these materials were proved to be available, and finite elements calculation suggests that this new structure can evidently reduce the thermal stress of SCWR internal components.

The Light Water Reactor Sustainability Program is a U.S. government research and development program. It is directed by the United States Department of Energy and is aimed at performing research and compiling data necessary to qualify for licenses to extend the life of America's current electricity generating nuclear power plants beyond 60 years of life.

Benchmark aging for both jacket and insulation material was carried out in air at a temperature of °C or in a uniform Gy/h gamma field over a period of 60 days. Their mechanical properties over the course of their exposures were compared with reference data from comparable cable jacket/insulation compositions and aging conditions.

- Plant assessment of Systems, Structures, and Components for Upgrade or Replacement, based Aging Management. E.G. Roof Replacement, Constant Velocity Title: Consultant at Design Basis. This paper discusses the U.S. Nuclear Regulatory Commissions Proactive Management of Materials Degradation (PMMD) program and its application to nuclear power plant structures, systems and components.

management programs (AMP) that were determined to be acceptable to manage aging effects of systems, structures and components (SSC) in the scope of license renewal, as required by 1 0 CFR P "Requirements for Renewal of Operating Licenses for Nuclear Power Plants.".

During the recent aging management programs, reactor internal component environmental fatigue evaluations for several pressurized water reactors were evaluated. The analyses calculated the cumulative fatigue usage using the recorded plant-specific transient cycles and the projected cycles for 60 years of plant life.

Managing nuclear power plant aging is one of the important technical issues which needs to be addressed by utilities in order to extend the operating life of some of the early LWR power stations.

• Plant Systems Management Nov – Aug 12 years 10 months. •Trended systems/components performance to minimize systems vulnerabilities and increase system : Innovative visionary leader with. System Descriptions * The plant was divided into about 50 systems that more closely matched the descriptions in the FSAR and the GALL, for consistency.

* Actual plant systems were assigned to one of these 50 LR systems. * Table provides a list of LR systems and overall results of the scoping process. 15 SECTION SCOPING AND SCREENING. ANSx, Process for Aging Management and Life Extension of Nonreactor Nuclear Facilities (new standard) ANSx, Photon and Neutron Fluence-to-Dose Conversion Coefficients [new standard/supersedes ANS- (W)] ANSx, Criticality Accident Alarm System [revision of ANSI/ANS (R)].

Life Cycle Management - Conducted aging management reviews of various safety-components and systems. Reviewed operating experience and preventive maintenance bases for various plant : Engineering Manager Charlotte at.

Special features of the book include: * More than figures and lines drawings that illustrate all aspects of the subject. * Coverage of related components and systems in power plants such as turbine-generators, feedwater heaters, condenser, and cooling towers.

* Definitions and analyses of the features of various plant systems. In order to evaluate properties of inner defects at plant structures quantitatively, non-destructive inspection using ultrasonic testing (UT) has performed an important role for plant maintenances.

At nuclear power plants, there are many structures made of cast austenitic stainless steel (e.g. casings, valve gages, pipes and so on).Integrated Pest Management (IPM) is a paradigm that is widely adopted by all pest control disciplines but whose early definitions and philosophical basis belong to entomologists.

Plant pathology research and extension work has historically emphasized integration of several control strategies and fits both historical and modern definitions of IPM. While the term IPM has been used only sparingly.Materials Issues in Nuclear-Waste Management July ;as well as systems and components, be assessed and managed during both the current operating license period as well as subsequent license renewal periods.

Assessment and management of aging in nuclear power plant concrete structures requires a more systematic approach than simple.