WorldWideScience

Sample records for plant performance technical

  1. Organizational factors influencing human performance in nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    In 1991 a Safety Series report on Safety Culture of the International Nuclear Safety Advisory Group (INSAG) was published as 75-INSAG-4 by the IAEA. This report deals with the concept of Safety Culture as it relates to organizations and individuals involved in the operations of nuclear power plants (NPPs). Generally, the role of management and organization in assuring the safe operation of NPPs has been widely recognized and its importance accepted. However, the understanding of what constitutes effective management and organization the area of safety is less developed than the understanding of most of the technical issues which plant operators and regulatory bodies are confronted with. The Technical Committee meeting provided a forum for a broad exchange of information on practices and experiences in the area of organization and management to accomplish operational safety in NPPs and thus enhance Safety Culture. This report and the papers presented at the meeting discuss those factors which influence and improve human performance covering both aspects, i.e. the basic requirements imposed on the operator and the ways of managerial support which enhance the reliable and safety oriented performance of operators. Refs, figs, tabs

  2. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    1998-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include ''engineering tools'' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire PRA analyses are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (author)

  3. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    2000-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include 'engineering tools' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire probabilistic risk analyses (PRA) are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (orig.) [de

  4. Software for automated evaluation of technical and economic performance factors of nuclear power plant units

    International Nuclear Information System (INIS)

    Cvan, M.; Zadrazil, J.; Barnak, M.

    1989-01-01

    Computer codes TEP V2, TEP EDU and TEP V1 are used especially in real-time evaluation of technical and economic performance factors of the power unit. Their basic functions include filtration of credibility of input data obtained by measurement, simultaneous calculation of flows of various types of energy, calculation of technical and economic factors, listings and filing of the results. Code ZMEK is designed for executing changes in the calculation constants file for codes TEP V2 and TEP EDU. Code TEP DEN is used in processing the complete daily report on the technical and economic performance factors of the unit. Briefly described are the basic algorithms of credibility filtration for the measured quantities, the methodology of fundamental balances and the method of guaranteeing the continuity of measurement. Experiences are given with the use of the codes, and the trends are outlined of their future development. (J.B.). 5 refs

  5. Performance evaluation recommendations of nuclear power plants outdoor significant civil structures earthquake resistance. Technical documentation

    International Nuclear Information System (INIS)

    2005-06-01

    The Japan Society of Civil Engineers has updated performance evaluation recommendations of nuclear power plants outdoor significant civil structures earthquake resistance in June 2005. Experimental and analytical considerations on the seismic effects evaluation criteria, such as analytical seismic models of soils for underground structures, effects of vertical motions on time-history dynamic analysis and shear fracture of reinforced concretes by cyclic loadings, were shown in this document and incorporated in new recommendations. (T. Tanaka)

  6. CO2 capture from power plants: Part I. A parametric study of the technical performance based on monoethanolamine

    NARCIS (Netherlands)

    Abu-Zahra, Mohammad R.M.; Schneiders, Léon H.J.; Niederer, John; Feron, Paul H.M.; Versteeg, Geert

    2007-01-01

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  7. CO2 capture from power plants. Part I : A parametric study of the technical performance based on monoethanolamine

    NARCIS (Netherlands)

    Abu-Zahra, M. R. M.; Schneiders, L. H. J.; Niederer, J. P. M.; Feron, P. H. M.; Versteeg, G. F.

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  8. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.M.

    2009-11-30

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  9. Applying Human-performance Models to Designing and Evaluating Nuclear Power Plants: Review Guidance and Technical Basis

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    2009-01-01

    Human performance models (HPMs) are simulations of human behavior with which we can predict human performance. Designers use them to support their human factors engineering (HFE) programs for a wide range of complex systems, including commercial nuclear power plants. Applicants to U.S. Nuclear Regulatory Commission (NRC) can use HPMs for design certifications, operating licenses, and license amendments. In the context of nuclear-plant safety, it is important to assure that HPMs are verified and validated, and their usage is consistent with their intended purpose. Using HPMs improperly may generate misleading or incorrect information, entailing safety concerns. The objective of this research was to develop guidance to support the NRC staff's reviews of an applicant's use of HPMs in an HFE program. The guidance is divided into three topical areas: (1) HPM Verification, (2) HPM Validation, and (3) User Interface Verification. Following this guidance will help ensure the benefits of HPMs are achieved in a technically sound, defensible manner. During the course of developing this guidance, I identified several issues that could not be addressed; they also are discussed.

  10. Nuclear Power Plant Temelin Technical Support Centre

    International Nuclear Information System (INIS)

    Krizek, K.

    2000-01-01

    The erection of the Technical Support Centre for the Nuclear Power Plant Temelin has been a relatively sophisticated and costly issue. It was by proper use of the existing systems, as e.g. I and C, ISE and other systems, that a robust system has been created that is able to meet any requirements laid on the performance of the Technical Support Centre. The decision of the utility CEZ, a.s. that made it possible to establish the Technical Support Centre at the Nuclear Power Plant Temelin has been a right step which shows the level of safety culture within the utility. (author)

  11. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS

  12. Standard Technical Specifications, Westinghouse Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation

  13. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  14. Using Technical Performance Measures

    Science.gov (United States)

    Garrett, Christopher J.; Levack, Daniel J. H.; Rhodes, Russel E.

    2011-01-01

    All programs have requirements. For these requirements to be met, there must be a means of measurement. A Technical Performance Measure (TPM) is defined to produce a measured quantity that can be compared to the requirement. In practice, the TPM is often expressed as a maximum or minimum and a goal. Example TPMs for a rocket program are: vacuum or sea level specific impulse (lsp), weight, reliability (often expressed as a failure rate), schedule, operability (turn-around time), design and development cost, production cost, and operating cost. Program status is evaluated by comparing the TPMs against specified values of the requirements. During the program many design decisions are made and most of them affect some or all of the TPMs. Often, the same design decision changes some TPMs favorably while affecting other TPMs unfavorably. The problem then becomes how to compare the effects of a design decision on different TPMs. How much failure rate is one second of specific impulse worth? How many days of schedule is one pound of weight worth? In other words, how to compare dissimilar quantities in order to trade and manage the TPMs to meet all requirements. One method that has been used successfully and has a mathematical basis is Utility Analysis. Utility Analysis enables quantitative comparison among dissimilar attributes. It uses a mathematical model that maps decision maker preferences over the tradeable range of each attribute. It is capable of modeling both independent and dependent attributes. Utility Analysis is well supported in the literature on Decision Theory. It has been used at Pratt & Whitney Rocketdyne for internal programs and for contracted work such as the J-2X rocket engine program. This paper describes the construction of TPMs and describes Utility Analysis. It then discusses the use of TPMs in design trades and to manage margin during a program using Utility Analysis.

  15. Performance evaluation of cogeneration power plants

    International Nuclear Information System (INIS)

    Bacone, M.

    2001-01-01

    The free market has changed the criteria for measuring the cogeneration plant performances. Further at the technical-economic parameters, are considered other connected at the profits of the power plant [it

  16. Standard technical specifications combustion engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS

  17. On-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

    International Nuclear Information System (INIS)

    Davis, E.; Rasmussen, B.

    2004-01-01

    This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system

  18. Standard Technical Specifications, Babcock and Wilcox Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations

  19. ON-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    E Davis, B Rasmussen

    2004-12-31

    This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system.

  20. Technical Safety Appraisal of the Pinellas Plant

    International Nuclear Information System (INIS)

    1991-01-01

    This report presents the Technical Safety Appraisal (TSA) of the Pinellas Plant in Pinellas County, Florida. The plant is owned and controlled by the US Department of Energy and operated by General Electric Neutron Devices (GEND). The TSA was performed during the period January 15--31, 1989, in support of a Tiger Team Assessment which occurred during the period January 15 to February 2, 1989. The TSA provided the Safety and Health Subteam input to the Tiger Team Assessment. The completion of the assessment process includes: (1) submission of the Team's preliminary findings and concerns, in a Draft Report, to the Manager, Albuquerque Operations Office and to the site contractors at the conclusion of the onsite assessment; (2) review of the Draft Report for technical and factual accuracy; incorporation of the appropriate review comments, suggested changes, and modifications, as well as input from all interested Program Secretarial Offices; preparation of a draft Action Plan by the Albuquerque Operations Office to address the Concerns, and submittal of that Action Plan through the Program Office to ES ampersand H for their review and comment. The Secretary approved the final Action Plan on December 16, 1990, and directed its implementation. The comments and suggestions of the Program Secretarial Offices, the Operations Office, and the site contractor have been incorporated, as appropriate, in this report prior to its publication

  1. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The unproved STS were developed based on the, criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop proved plant-specific technical specifications. This report contains three volumes. This document, Volume 1 contains the Specifications for all chapters and sections of the improved STS

  2. Testing of energy assessment of technical plants, in accordance with the Energy Performance of Buildings Directive, EPBD; Testing av Energivurdering av tekniske anlegg iht Bygningsenergidirektivet, EPBD

    Energy Technology Data Exchange (ETDEWEB)

    Birkeland, Harald

    2008-06-15

    The consulting company Norwegian Energy has previously worked out proposals for inspection systems for technical plants, in accordance with the EU Energy Performance of Buildings Directive, abbreviated EPBD. This project has consisted in practice testing of the proposed inspection systems. In this respect agreements have been made with a number of companies working with heating boiler inspections as well as ventilation and cooling. Testing experiences have been summed up in this report. The most important experiences from this project concern practical matters: The main challenge is to find data and documentation on the plant. Use of time and resources is part of this challenge. The forms must be simplified, with less information to fill in. Some adjustments have been proposed to the previously proposed procedure. The content of the inspection should be clearly defined, without any options for simplifications. Eligibility requirements: There is clearly a need for training and certification procedures for companies/persons which are permitted to carry out inspections according to the EPBD. A proposal for such procedures has been worked out. The inspection should contain both a declaration of impartiality and a guarantee from the inspector that all identified points of improvement have been described. (EW)

  3. Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

  4. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  5. Standard Technical Specifications, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  6. Standard Technical Specifications, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved SM. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3 contains the Bases for Sections 3.4--3.9 of the improved M

  7. Hanford Waste Vitrification Plant technical manual

    Energy Technology Data Exchange (ETDEWEB)

    Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

  8. Hanford Waste Vitrification Plant technical manual

    International Nuclear Information System (INIS)

    Larson, D.E.; Watrous, R.A.; Kruger, O.L.

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

  9. VGB-requirements regarding technical data for power plants

    International Nuclear Information System (INIS)

    Richnow, Joerg

    2009-01-01

    Much of the technical plant data resulting from the planning, construction and start-up of power plants is needed for subsequent management and maintenance. Because of this, VGB has taken the initiative and has defined standard minimum requirements from power plant operators for technical plant data. They relate to the details and structure of this data, the definition of material classes and characteristics for the main power plant components and IT implementation for delivery of the technical plant data. (orig.)

  10. Independent technical review of the Pinellas Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This report documents an Independent Technical Review (ITR) of facilities, organizations, plans, activities and various other elements required to successfully transition the Pinellas Plant from Defense Program (DP) funded operation to either community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Department of Energy (DOE) Deputy Assistant Secretary for Facility Transition and Management (EM-60) and is a consensus of the nine member ITR Team.

  11. Technical diagnosis of industrial plants with radioisotopes

    International Nuclear Information System (INIS)

    Hartmann, G.

    1984-01-01

    A survey is given of the application of radioisotopes in technical diagnosis of industrial plants. Proceeding from the economic importance and the state of the art of radioisotope applications, the principles of tracer techniques are outlined including topical examples of application such as passage of coal through a steam generator, wear in impact crashing of coal, wear and corrosion in pipelines, testing the effective cross section of pipes, and investigations of microstructures. Limits and restrictions of applications are briefly discussed

  12. Investigation of the prospect of energy self-sufficiency and technical performance of an integrated PEMFC (proton exchange membrane fuel cell), dairy farm and biogas plant system

    International Nuclear Information System (INIS)

    Guan, Tingting; Alvfors, Per; Lindbergh, Göran

    2014-01-01

    Highlights: • A PEMFC stack with a 40% of electrical efficiency will make the integrated PEMFC-CHP, biogas plant and dairy farm self-sufficient. • The quality of the reformate gas is good enough to support normal operation of the PEMFC-CHP. • The methane conversion rate and the content of the CH 4 in the biogas need to be balanced in order to obtain the best system performance. • Compared with a coal-fired CHP plant, the integrated system can avoid coal consumption and CO 2 emissions. - Abstract: A PEMFC fuelled with hydrogen is known for its high efficiency and low local emissions. However, the generation of hydrogen is always a controversial issue for the application of the PEMFC due to the use of fossil fuel and the possible carbon dioxide emissions. Presently, the PEMFC-CHP fed with renewable fuels, such as biogas, appears to be the most attractive energy converter–fuel combination. In this paper, an integrated PEMFC-CHP, a dairy farm and a biogas plant are studied. A PEMFC-CHP fed with reformate gas from the biogas plant generates electricity and heat to a dairy farm and a biogas plant, while the dairy farm delivers wet manure to the biogas plant as the feedstock for biogas production. This integrated system has been modelled for steady-state conditions by using Aspen Plus®. The results indicate that the wet manure production of a dairy farm with 300 milked cows can support a biogas plant to give 1280 MW h of biogas annually. Based on the biogas production, a PEMFC-CHP with a stack having an electrical efficiency of 40% generates 360 MW h electricity and 680 MW h heat per year, which is enough to cover the energy demand of the whole system while the total efficiency of the PEMFC-CHP system is 82%. The integrated PEMFC-CHP, dairy farm and biogas plant could make the dairy farm and the biogas plant self-sufficient in a sustainable way provided the PEMFC-CHP has the electrical efficiency stated above. The effect of the methane conversion rate and the

  13. Technical Efficiency Performance of Conventional Banks

    OpenAIRE

    Endri, Endri

    2012-01-01

    This study aims to measure the performance of the technical efficiency of the conventional commercial banks during the period 2008-2009 by using non-parametric method of Data Envelopment Analysis (DEA). Test results showed that the total of all conventional commercial banks during the period 2008-2009 has not shown that optimal performance in which the level of technical efficiency is still below 100 percent. Appalling conditions, the efficiency of national banks experienced a decline of 73.5...

  14. Independent technical review of the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This report documents an Independent Technical Review (ITR) of the facilities, organizations, plans, and activities required to transition particular elements of the Mound Plant from Defense Program (DP) funded operation as appropriate either to community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Dr. Willis Bixby, Deputy Assistant Secretary, U.S. Department of Energy EM-60, Office of Facility Transition and Management and is a consensus of the nine member ITR Team. Information for the review was drawn from documents provided to the ITR Team by the Miamisburg Area Office (MB) of the DOE, EG&G, the City of Miamisburg, and others; and from presentations, discussions, interviews, and facility inspections at the Mound Plant during the weeks of March 14 and March 28, 1994. During the week of April 25, 1994, the ITR Team met at Los Alamos, New Mexico to develop consensus recommendations. A presentation of the core recommendations was made at the Mound Plant on May 5, 1994. This is an independent assessment of information available to, and used by, the Mound Plant personnel. Repetition of the information is not meant to imply discovery by the ITR Team. Team members, however, acting as independent reviewers, frequently assess the information from a perspective that differs significantly from that of the Mound Plant personnel. The report is based on information obtained and conditions observed during the March 1994 review interval. The ITR process and normal site work often initiate rapid, beneficial changes in understanding and organization immediately following the review. These changes frequently alter conditions observed during the review, but the report does not address changes subsequent to the review interval.

  15. Designing Second Language Performance Assessments. Technical Report.

    Science.gov (United States)

    Norris, John M.; Brown, James Dean; Hudson, Thom; Yoshioka, Jim

    This technical report focuses on the decision-making potential provided by second language performance assessments. First, performance assessment is situated within the broader discussion of alternatives in language assessment and in educational assessment in general. Next, issues in performance assessment design, implementation, reliability, and…

  16. Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-11-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  17. Evaluation of Watts Bar Nuclear Plant Unit 1 Technical Specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  18. Technical specifications and performance of CANDU fuel

    International Nuclear Information System (INIS)

    Sejnoha, R.

    1997-01-01

    The relations between Technical Specifications and fuel performance are discussed in terms of design limits and margins. The excellent performance record of CANDU reactor fuel demonstrates that the fuel design defined in the Technical Specifications (and with it other components of the procurement cycle, such as fuel manufacturing), satisfy the requirements. New requirements, changing conditions of fuel application and accumulating experience make periodic updates of the Technical Specifications necessary. Under the CANDU Owners Group (COG) Working Party 9, a Work Package has been conducted to support the review of the Specifications and the documentation of the rationales for their requirements. So far, the review has been completed for 4 Specifications: 1 for Zircaloy tubing, and 3 for uranium dioxide powder. It is planned to complete the review of all 11 currently used specifications by 1999. The paper summarizes the results achieved to mid 1997. (author)

  19. Guidelines for the technical evaluation of replacement items in nuclear power plants (NCIG-11)

    International Nuclear Information System (INIS)

    Craig, W.E.; Fakhar, A.A.; Shulman, M.N.

    1989-12-01

    This document presents guidelines and supporting information for the technical evaluation of replacement items in nuclear power plants. These guidelines contain six major sections which provide the practical knowledge and a programmatic approach to determine the technical and quality requirements necessary to generate purchase documents to procure the proper replacement items. The technical evaluation methodology includes the following steps. (1) Identification of the need for a technical evaluation. (2) Component/part functional classification procedures. (3) Performance of a Failure Modes and Effects Analysis. (4) Selection of Critical Characteristics for Design Determination. (5) Performance of a ''Like-For-Like'' or ''Alternate'' item Evaluation. (6) Preparation of the Technical and Quality Requirements Specification. Work on this document was initiated in response to the increased emphasis by the utilities owning nuclear power plants and nuclear industry on procurement of replacement items for use in safety related applications at nuclear power plants. 20 refs., 9 figs., 14 tabs

  20. Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  1. Technical strategy map to employing nuclear power plant aging management

    International Nuclear Information System (INIS)

    Sekimura, Naoto; Kanno, Masanori

    2008-01-01

    Stated in this report are back ground of technical strategy map for nuclear power plant aging management, result of the first road map, significance of technical strategy map, introduction scenario, technology map, road map, upgrade in every year, three groups of academia, industry and government, plan of technical strategy map, upgrade system, comprehensive introduction scenario, measures of nuclear power plant aging management in Japan and the world, new inspection system, outline of 'technical strategy map 2008', preparation of technical information bases in industry, academia and government, collaboration of them, safety researches of neutron radiation damage, stress corrosion crack, fatigue, piping thinning, insulation degradation, concrete degradation, thermal aging, evaluation technologies of earthquake resistance, preparation of rules and standards, ideal maintenance, and training talent. (S.Y.)

  2. Technical manual for calculating cooling pond performance

    International Nuclear Information System (INIS)

    Krstulovich, S.F.

    1988-01-01

    This manual is produced in response to a growing number of requests for a technical aid to explain methods for simulating cooling pond performance. As such, it is a compilation of reports, charts and graphs developed through the years for use in analyzing situations. Section II contains a report summarizing the factors affecting cooling pond performance and lists statistical parameters used in developing performance simulations. Section III contains the graphs of simulated cooling pond performance on an hourly basis for various combinations of criteria (wind, solar, depth, air temperature and humidity) developed from the report in Section II. Section IV contains correspondence describing how to develop further data from the graphs in Section III, as well as mathematical models for the system of performance calculation. Section V contains the formulas used to simulate cooling pond performances in a cascade arrangement, such as the Fermilab Main Ring ponds. Section VI contains the calculations currently in use to evaluate the Main Ring pond performance based on current flows and Watts loadings. Section VII contains the overall site drawing of the Main Ring cooling ponds with thermal analysis and physical data

  3. Development of innovative techniques and principles that may be used as models to improve plant performance. Technical progress report, February 1, 1990--January 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Hanna, W.W.; Burton, G.W.

    1992-06-01

    Methods and techniques for transferring germplasm from wild to cultivated species are being developed. The transferred germplasm is being shown to be valuable in plant breeding and in cultivar development. In the primary gene pool of the grassy Pennisetum glaucum subspecies monodii germplasm, some cytoplasms are being identified that appear to have significant effects on forage yields and morphological characteristics. One cytoplasm, A{sub 4}, is very stable for male sterility and fertility is not easily restored by other lines. It should be a valuable cytoplasm for producing commercial forage hybrids. Disease resistance and yield genes transferred from monodii to cultivated pearl millet lines are having a major impact on increasing production of animals grazing disease resistant Tifleaf 2 pearl millet. Genes controlling resistance to many of the world-wide diseases on pearl millet are being identified in the monodii germplasm. Valuable germplasm has been transferred from the secondary gene pool P. purpuroum) which is used as the pollinator of the first pearl millet grain hybrid in the US Production of 7-chromosome gametes in 42-chromosome interspecific hybrids appears to be genotype specific and makes possible transfer of germplasm from the secondary gene pool to cultivated diploid pearl millet. Significant progress has been made in transferring genes controlling apomixis from P. squamulatum (tertiary gene pool) to cultivated pearl millet. Highly apomictic BC{sub 4} plants have been recovered, one of which sets five times as much seed as the best BC{sub 3} plant.

  4. Tele-maintenance 'intelligent' system for technical plants result management

    International Nuclear Information System (INIS)

    Concetti, Massimo; Cuccioletta, Roberto; Fedele, Lorenzo; Mercuri, Giampiero

    2009-01-01

    The management of technical plant for productivity and safety is generally a complex activity, particularly when many plants distributed in the territory are considered (i.e. the more and more frequent case of outsourced plants maintenance by specialized companies), granted quality and cost results are required (i.e. the case of some rather innovative contract solutions) and the technology involved is heterogeneous and innovative (i.e. electro-mechanical plants). In order to efficiently achieve the above aims an 'intelligent' maintenance-management system for the distant monitoring and controlling by a remote control center has been developed. The so-called GrAMS (granted availability management system) system is conceived to give to organizations involved in technical-industrial plants management the possibility to tend to a 'well-known availability' and 'zero-failures' management. In particular, this study deals with the diagnostic aspects and safety level of technical plants (such as elevators, thermo-technical plants, etc.), and with the involvement of ad hoc designed software analysis tools based on neural networks and reliability indicators. Part of the research dealing with the tele-maintenance intelligent system has been financed by the Italian High Institute for Safety (ISPESL) and led to the development of a pre-industrial prototype whose realization and testing is here described

  5. IASI instrument: technical description and measured performances

    Science.gov (United States)

    Hébert, Ph.; Blumstein, D.; Buil, C.; Carlier, T.; Chalon, G.; Astruc, P.; Clauss, A.; Siméoni, D.; Tournier, B.

    2017-11-01

    IASI is an infrared atmospheric sounder. It will provide meteorologist and scientific community with atmospheric spectra. The IASI system includes 3 instruments that will be mounted on the Metop satellite series, a data processing software integrated in the EPS (EUMETSAT Polar System) ground segment and a technical expertise centre implemented in CNES Toulouse. The instrument is composed of a Fourier transform spectrometer and an associated infrared imager. The optical configuration is based on a Michelson interferometer and the interferograms are processed by an on-board digital processing subsystem, which performs the inverse Fourier transforms and the radiometric calibration. The infrared imager co-registers the IASI soundings with AVHRR imager (AVHRR is another instrument on the Metop satellite). The presentation will focus on the architectures of the instrument, the description of the implemented technologies and the measured performance of the first flight model. CNES is leading the IASI program in association with EUMETSAT. The instrument Prime is ALCATEL SPACE.

  6. Technical safety appraisal of the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    1992-05-01

    On June 27, 1989, Secretary of Energy, Admiral James D. Watkins, US Navy (Retired), announced a 10-point initiative to strengthen environment, safety, and health (ES ampersand H) programs and waste management operations in the Department of Energy (DOE). One of the initiatives involved conducting independent Tiger Team Assessments (TTA) at DOE operating facilities. A TTA of the Idaho National Engineering Laboratory (INEL) was performed during June and July 1991. Technical Safety Appraisals (TSA) were conducted in conjunction with the TTA as its Safety and Health portion. However, because of operational constraints the the Idaho Chemical Processing Plant (ICPP), operated for the DOE by Westinghouse Idaho Nuclear Company, Inc. (WINCO), was not included in the Safety and Health Subteam assessment at that time. This TSA, conducted April 12 - May 8, 1992, was performed by the DOE Office of Performance Assessment to complete the normal scope of the Safety and Health portion of the Tiger Team Assessment of the Idaho National Engineering Laboratory. The purpose of TSAs is to evaluate and strengthen DOE operations by verifying contractor compliance with DOE Orders, to assure that lessons learned from commercial operations are incorporated into facility operations, and to stimulate and encourage pursuit of excellence; thus, the appraisal addresses more issues than would be addressed in a strictly compliance-oriented appraisal. A total of 139 Performance Objectives have been addressed by this appraisal in 19 subject areas. These 19 areas are: organization and administration, quality verification, operations, maintenance, training and certification, auxiliary systems, emergency preparedness, technical support, packaging and transportation, nuclear criticality safety, safety/security interface, experimental activities, site/facility safety review, radiological protection, worker safety and health compliance, personnel protection, fire protection, medical services and natural

  7. Standard technical specifications: Babcock and Wilcox Plants. Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock ampersand Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  8. Worldwide nuclear-plant performance

    International Nuclear Information System (INIS)

    Surrey, J.; Thomas, S.

    1980-01-01

    The authors compare the performance of different reactor systems to identify the determinants of plant performance, to examine the evidence of technological maturation, and to discover the principal causes of outage or unavailability. In the light of the findings, they discuss the implications for the UK regarding reactor choice and technology development. They make no judgements about the relative merits of nuclear and fossil-fuel plants, or about safety. (author)

  9. Programs to improve plant performance

    International Nuclear Information System (INIS)

    Felmus, N.L.

    1987-01-01

    Looking toward the 1990's, we see a period in which our industry will face the challenge of improving the performance of the nuclear plants which are built and operating. The skills and technology are at hand to make good plant performance a reality and we believe the time has come to use them to achieve that end. As reserve margins decline, utilities and their regulators will increasingly seek to tap the unexploited capacity tied up in plants operating below their optimum availability. This paper describes a number of the programs, plant improvements and operations improvements which can yield a significant increase in nuclear plant availability and capacity factor now and into the 1990's. (author)

  10. Canadian CANDU plant data systems for technical surveillance and analysis

    International Nuclear Information System (INIS)

    Deverno, M.; Pothier, H.; Xian, C.; Grosbois, J. De; Bosnich, M.

    1996-01-01

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs

  11. Canadian CANDU plant data systems for technical surveillance and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Deverno, M; Pothier, H; Xian, C [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Fredericton, NB (Canada); Grosbois, J De; Bosnich, M [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Chalk River, ON (Canada). Chalk River Labs.

    1997-12-31

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs.

  12. Technical Integration of SMART Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. H.; Park, P. H.; Noh, P. C. (and others)

    2006-12-15

    Preliminary experimental tests were carried out using the thermal-hydraulic integral test facility, VISTA (Experimental Verification by Integral Simulation of Transients and Accidents), which has been constructed to simulate the SMART-P. The VISTA facility is an integral test facility including the primary and secondary systems as well as safety-related Passive Residual heat removal (PRHR) systems. The integrated SMART desalination plant consists of Multi Effect Distillation Process combined with Thermal-Vapor Compressor(MED-TVC) and coupled with the extracted steam from turbine through the steam transformer. Steam transformer produces the main pressure steam and supplies to the MED-TVC unit. MED-TVC was selected as a desalination process coupled with SMART, since the thermal vapor compression is very effective where the steam is available at high temperature and pressure conditions than required in the evaporator. The standard design of the SMART desalination plant is under development as a part of the SMART project. This report describes design concept of these systems and their requirements.

  13. Thermal Power Plant Performance Analysis

    CERN Document Server

    2012-01-01

    The analysis of the reliability and availability of power plants is frequently based on simple indexes that do not take into account the criticality of some failures used for availability analysis. This criticality should be evaluated based on concepts of reliability which consider the effect of a component failure on the performance of the entire plant. System reliability analysis tools provide a root-cause analysis leading to the improvement of the plant maintenance plan.   Taking in view that the power plant performance can be evaluated not only based on  thermodynamic related indexes, such as heat-rate, Thermal Power Plant Performance Analysis focuses on the presentation of reliability-based tools used to define performance of complex systems and introduces the basic concepts of reliability, maintainability and risk analysis aiming at their application as tools for power plant performance improvement, including: ·         selection of critical equipment and components, ·         defini...

  14. Gas turbines: performance curves influence in the analysis of the technical viability of thermal power plants; Analise de viabilidade tecnica de plantas termeletricas

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Marcelo Augusto Milan da; Borba, Ricardo Alexandre Pereira; Bazzo, Edson [Santa Catarina Univ., Florianopolis, SC (Brazil). Dept. de Engenharia Mecanica. Lab. de Combustao e Engenharia de Sistemas Termicos (LABCET)]. E-mail: milan@cet.ufsc.br

    2003-07-01

    The performance of gas turbines is analyzed taking into account the oscillations of electrical load and environmental conditions for thermal power generating application. Two scenarios are considered for analysis, taking into account one year collected data, obtained at every hour from a ceramic company in the south region of Santa Catarina. The first scenario consists of a current used simplified model, considering the oscillation of electrical load but having the gas turbine running at ISO operation (15 deg C, 0 m, 60% u.r.). The second scenario corresponds to the proposed model, considering also the oscillations in the environmental temperature and moisture air. Three gas turbines were selected for analysis. The found results suggest the application of the proposed model as the basis in the evaluation of future projects. (author)

  15. Waste Isolation Pilot Plant Technical Assessment Team Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-17

    This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

  16. Relationship between intraoperative non-technical performance and technical events in bariatric surgery.

    Science.gov (United States)

    Fecso, A B; Kuzulugil, S S; Babaoglu, C; Bener, A B; Grantcharov, T P

    2018-03-30

    The operating theatre is a unique environment with complex team interactions, where technical and non-technical performance affect patient outcomes. The correlation between technical and non-technical performance, however, remains underinvestigated. The purpose of this study was to explore these interactions in the operating theatre. A prospective single-centre observational study was conducted at a tertiary academic medical centre. One surgeon and three fellows participated as main operators. All patients who underwent a laparoscopic Roux-en-Y gastric bypass and had the procedures captured using the Operating Room Black Box ® platform were included. Technical assessment was performed using the Objective Structured Assessment of Technical Skills and Generic Error Rating Tool instruments. For non-technical assessment, the Non-Technical Skills for Surgeons (NOTSS) and Scrub Practitioners' List of Intraoperative Non-Technical Skills (SPLINTS) tools were used. Spearman rank-order correlation and N-gram statistics were conducted. Fifty-six patients were included in the study and 90 procedural steps (gastrojejunostomy and jejunojejunostomy) were analysed. There was a moderate to strong correlation between technical adverse events (r s  = 0·417-0·687), rectifications (r s  = 0·380-0·768) and non-technical performance of the surgical and nursing teams (NOTSS and SPLINTS). N-gram statistics showed that after technical errors, events and prior rectifications, the staff surgeon and the scrub nurse exhibited the most positive non-technical behaviours, irrespective of operator (staff surgeon or fellow). This study demonstrated that technical and non-technical performances are related, on both an individual and a team level. Valuable data can be obtained around intraoperative errors, events and rectifications. © 2018 BJS Society Ltd Published by John Wiley & Sons Ltd.

  17. Process of technical performance: essential features and their economic view

    OpenAIRE

    Zhylinska, O.

    2010-01-01

    Essential features of technical performance have been defined in the context of similarity of its components such as research and development, training of technical/engineering personnel and providing technical services. Also peculiarities of economic view have been examined in terms of information model of managing.

  18. Technical evaluation of bids for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    In continuation of its efforts to provide comprehensive and impartial guidance to Member States facing the need to introduce nuclear power, the International Atomic Energy Agency is issuing this guidebook as part of a series of guidebooks and codes of practice and, in particular, as a necessary supplement to 'Economic Evaluation of Bids for Nuclear Power Plants: A Guidebook', published by the IAEA in 1976 as Technical Reports Series No.175. The present publication is intended for project managers and senior engineers of electric utilities who are concerned with the evaluation of bids for a nuclear power project. It assumes that the reader has a good knowledge of the technical characteristics of nuclear power plants and of nuclear power project implementation. Its purpose is to provide the information necessary to organize, guide and supervise the technical evaluation of bids for a nuclear power project. It goes without saying that the technical staff carrying out the evaluation must have prior technical experience which cannot be provided by a guidebook

  19. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  20. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  1. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  2. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  3. Standard Technical Specifications, General Electric plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  4. Technical basis for staffing levels at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shurberg, D.A.; Haber, S.B. [Brookhaven National Lab., Upton, NY (United States); Morisseau, D. [Nuclear Regulatory Commission, Washington, DC (United States)] [and others

    1995-04-01

    The objective of this project is to provide a technical basis for the establishment of criteria for minimum staffing levels of licensed and non-licensed NPP shift personnel. Minimum staffing levels for the purpose of this study, are defined as those necessary for successful accomplishment of all safety and additional functions that must be performed in order for the licensee to meet applicable regulatory requirements. This project involves a multi-faceted approach to the investigation of the issue. Relevant NRC documentation was identified and reviewed. Using the information obtained from this documentation review, a test plan was developed to aid in the collection of further information regarding the adequacy of current shift staffing levels. The test plan addresses three different activities to be conducted to provide information to the NRC for use in the assessment of current minimum staffing levels. The first activity is collection of data related to industry shift staffing practices through site visits to seven nuclear power plants. The second activity is a simulator study, which will use licensed operator crews responding to a simulated event, under two different staffing levels. Finally, workload models will be constructed for both licensed and non-licensed personnel, using a priori knowledge of the simulator scenarios with data resulting from one of the staffing levels studied in the simulator, and the data collected from the site visits. The model will then be validated against the data obtained from the second staffing level studied in the simulator. The validated model can then be used to study the impact of changing staffing-related variables on the plant shift crew`s ability to effectively mitigate an event.

  5. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

  6. Floating natural gas processing plants. Technical ideal or feasible technology

    Energy Technology Data Exchange (ETDEWEB)

    Backhaus, H

    1977-04-01

    Realizability of floating natural gas processing plants is decisively influenced by the economy of the system. Illustrated by the example of the natural gas product LPG (liquefied petroleum gas), a model cost calculation is carried out. It is demonstrated that the increase in the price level during the 1973/1974 energy crisis is an important factor for the realiability in terms of economy of such complicated technical systems. Another aspect which the model calculation revealed is that the economy of floating natural gas processing plants and storage systems can only be estimated in connection with other system components.

  7. U Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of an Aggregate Area Management Study of U Plant. It provides a technical baseline of the aggregate area and results from an environmental investigation that was undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC), which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. U Plant refers to the 221-U Process Canyon Building, a chemical separation facility constructed during World War II. It also includes the Uranium Oxide (UO 3 ) Plant constructed at the same time as 221-U as an adjunct to the original plutonium separation process but which, like 221-U, was converted for other missions. Waste sites are associated primarily with U Plant's 1952 through 1958 Uranium Metal Recovery Program mission and the U0 3 Plant's ongoing U0 3 mission. Waste sites include cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, a waste vault, and the lines and encasements that connect them. It also includes the U Pond and its feed ditches and an underground tank farm designed for high-level liquid wastes

  8. Technical concepts of further improvement of nuclear power plant safety

    International Nuclear Information System (INIS)

    Sochor, R.

    1983-01-01

    The following technical concepts are described which secure the integrity of the containment in case of an accident whose scale exceeds the so-called design basis accident: siting nuclear power plants underground which raises construction costs by 20 - 25%; completing the containment with equipment preventing the outflow of molten corium; completing the containment with emergency pressure space for discharging overpressure - this emergency space is filled with gravel which will trap approximately 50% of fission waste. (Ha)

  9. Plant operator performance evaluation system

    International Nuclear Information System (INIS)

    Ujita, Hiroshi; Fukuda, Mitsuko; Kubota, Ryuji.

    1989-01-01

    A plant operator performance evaluation system to analyze plant operation records during accident training and to identify and classify operator errors has been developed for the purpose of supporting realization of a training and education system for plant operators. A knowledge engineering technique was applied to evaluation of operator behavior by both even-based and symptom-based procedures, in various situations including event transition due to multiple failures or operational errors. The system classifies the identified errors as to their single and double types based on Swain's error classification and the error levels reflecting Rasmussen's cognitive level, and it also evaluates the effect of errors on plant state and then classifies error influence, using 'knowledge for phenomena and operations', as represented by frames. It has additional functions for analysis of error statistics and knowledge acquisition support of 'knowledge for operations'. The system was applied to a training analysis for a scram event in a BWR plant, and its error analysis function was confirmed to be effective by operational experts. (author)

  10. Control of heavy loads at nuclear power plants: Resolution of Generic Technical Activity A-36. Technical report

    International Nuclear Information System (INIS)

    George, H.J.

    1980-07-01

    This report summarizes work performed by the NRC staff in the resolution of Generic Technical Activity A-36, Control of Heavy Loads Near Spent Fuel. Generic Technical Activity A-36 is one of the generic technical subjects designated as unresolved safety issues pursuant to Section 210 of the Energy Reorganization Act of 1974. The report describes the technical studies and evaluations performed by the NRC staff, the staff's guidelines based on these studies, and the staff's plans for implementaton of its technical guidelines

  11. Containment-emergency-sump performance. Technical findings related to Unresolved Safety Issue A-43

    International Nuclear Information System (INIS)

    1983-04-01

    This report summarizes key technical findings related to the Unresolved Safety Issue A-43, Containment Emergency Sump Performance, and provides recommendations for resolution of attendant safety issues. The key safety questions relate to: (a) effects of insulation debris on sump performance; (b) sump hydraulic performance as determined by design features, submergence, and plant induced effects, and (c) recirculation pump performance wherein air and/or particulate ingestion can occur. The technical findings presented in this report provide information relevant to the design and performance evaluation of the containment emergency sump

  12. Automation of technical specification monitoring for nuclear power plants

    International Nuclear Information System (INIS)

    Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

    1986-01-01

    The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)

  13. Technical Safety Appraisal of the Rocky Flats Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Blake P.

    1989-01-01

    This report provides the results of a Technical Safety Appraisal (TSA) of the Rocky Flats Plant (RFP) conducted November 14 to 18 and November 28 to December 9, 1988. This appraisal covered the effectiveness and improvements in the RFP safety program across the site, evaluating progress to date against standards of accepted practice. The appraisal included coverage of the timeliness and effectiveness of actions taken in response to the recommendations/concerns in three previous Technical Safety Appraisals (TSAs) of RFP Bldg. 707 conducted in July 1986, Bldgs. 771/774 conducted in October/November 1986, and Bldgs. 776/777 conducted in January/February 1988. Results of this appraisal are given in Section IV for each of 14 technical safety areas at RFP. These results include a discussion, conclusions and any new safety concerns for each technical safety area. Appendix A contains a description of the system for categorizing concerns, and the concerns are tabulated in Appendix B. Appendix C reports on the evaluation of the contractor's actions and the current status of each of the 230 recommendations and concerns contained in the three previous TSA reports.

  14. S Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document is prepared in support of an Aggregate Area Management Study of S Plant, 200 West Area, at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. It provides a technical baseline of the aggregate area and the results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC). This document is based on review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. This report describes the REDOX facility and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them

  15. Z plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of the development of a Aggregate Area Management Study of Z Plant, 200 West Area, at the US Department of Energy (DOE) Hanford Site near Richland, Washington. It provides a technical description and operational history of the aggregate area and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC) which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted in support of this report

  16. Vocational and Technical Education Performance Standards and Competencies.

    Science.gov (United States)

    Connecticut State Board of Education, Hartford.

    These Connecticut vocational and technical performance standards and competencies are a guide for overall quality attainment in these seven vocational and technical program areas: agricultural science technology education; business and finance technology education; cooperative work education; family and consumer sciences education; marketing…

  17. Technical evaluation of RETS-required reports for the Edwin I. Hatch Nuclear Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Young, T.E.; Magleby, E.H.

    1985-01-01

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Edwin I. Hatch Nuclear Plant were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 7 refs

  18. Technical knowledge/skill transfer in nuclear power plant manufacturer

    International Nuclear Information System (INIS)

    Arima, Hiroshi; Sagawa, Wataru; Ogawa, Yukio

    2009-01-01

    Due to environmental concerns such as global warming, needs for nuclear power is increasing. However, many expert engineers and technicians are now entering a period of retirement. And due to weak demands of new plant construction for long years, opportunity for technology learning/experience had been lost. Therefore, to secure human resource and to develop their ability are urgent issues for nuclear industries. Hitachi nuclear division continues efforts for technology transfer and human resource training. This paper describes the following two activities. (1) Improvement of common technical basis, and implementation of PDCA cycle, (2) Development of supporting tools to accelerate technology transfer through OJT (On the Job Training). (author)

  19. Technical guidelines for aseismic design of nuclear power plants

    International Nuclear Information System (INIS)

    Park, Y.J.; Hofmayer, C.H.

    1994-06-01

    This document is a translation, in its entirety, of the Japan Electric Association (JEA) publication entitled open-quotes Technical Guidelines for Aseismic Design of Nuclear Power Plants - JEAG 4601-1987.close quotes This guideline describes in detail the aseismic design techniques used in Japan for nuclear power plants. It contains chapters dealing with: (a)the selection of earthquake ground motions for a site, (b) the investigation of foundation and bedrock conditions, (c) the evaluation of ground stability and the effects of ground movement on buried piping and structures, (d) the analysis and design of structures, and (e) the analysis and design of equipment and distribution systems (piping, electrical raceways, instrumentation, tubing and HVAC duct). The guideline also includes appendices which summarize data, information and references related to aseismic design technology

  20. Technical indicators of financial performance in the dairy herd

    DEFF Research Database (Denmark)

    Kristensen, Erling Lundager; Østergaard, Søren; Krogh, Mogens Agerbo

    2008-01-01

    Monte Carlo simulation was used to predict the long-term financial performance related to the technical performance of dairy herds. The indicators addressed were derived from data collected routinely in the herd. They indicated technical performance that can be affected by the farmer...... or the consultant, and they were derived from expected cause-effect relations between technical performance and financial performance at the herd level. The study included the indicators shape of lactation curve, reproduction efficiency, heifer management, variation between cows in lactation curve persistency...... cow was analyzed as the measure of financial performance. The potential effects of the selected indicators on the gross margin were estimated by means of an ANOVA. The final model allowed estimation of the financial value of specific changes within the key performance indicators. This study indicated...

  1. Gamma camera performance: technical assessment protocol

    International Nuclear Information System (INIS)

    Bolster, A.A.; Waddington, W.A.

    1996-01-01

    This protocol addresses the performance assessment of single and dual headed gamma cameras. No attempt is made to assess the performance of any associated computing systems. Evaluations are usually performed on a gamma camera commercially available within the United Kingdom and recently installed at a clinical site. In consultation with the manufacturer, GCAT selects the site and liaises with local staff to arrange a mutually convenient time for assessment. The manufacturer is encouraged to have a representative present during the evaluation. Three to four days are typically required for the evaluation team to perform the necessary measurements. When access time is limited, the team will modify the protocol to test the camera as thoroughly as possible. Data are acquired on the camera's computer system and are subsequently transferred to the independent GCAT computer system for analysis. This transfer from site computer to the independent system is effected via a hardware interface and Interfile data transfer. (author)

  2. Gamma camera performance: technical assessment protocol

    Energy Technology Data Exchange (ETDEWEB)

    Bolster, A.A. [West Glasgow Hospitals NHS Trust, London (United Kingdom). Dept. of Clinical Physics; Waddington, W.A. [University College London Hospitals NHS Trust, London (United Kingdom). Inst. of Nuclear Medicine

    1996-12-31

    This protocol addresses the performance assessment of single and dual headed gamma cameras. No attempt is made to assess the performance of any associated computing systems. Evaluations are usually performed on a gamma camera commercially available within the United Kingdom and recently installed at a clinical site. In consultation with the manufacturer, GCAT selects the site and liaises with local staff to arrange a mutually convenient time for assessment. The manufacturer is encouraged to have a representative present during the evaluation. Three to four days are typically required for the evaluation team to perform the necessary measurements. When access time is limited, the team will modify the protocol to test the camera as thoroughly as possible. Data are acquired on the camera`s computer system and are subsequently transferred to the independent GCAT computer system for analysis. This transfer from site computer to the independent system is effected via a hardware interface and Interfile data transfer. (author).

  3. Performance improvement plan in customer technical services

    International Nuclear Information System (INIS)

    Lachambre, L.

    1995-01-01

    This presentation centred around the philosophy, goals, and initiatives associated with Gaz Metropolitain's performance improvement plan. Various aspects of the plan including customer surveys, new customer service policies, the creation of small working units, the decentralization of the Montreal service department, and customer-harmonized shift schedules were explored. Implementation of new service plans and contracts, the formation of improvement groups related to human resources, human resource and productivity management, leadership training, and the use of performance indicators were also explained

  4. Technical Basis for Assessing Uranium Bioremediation Performance

    International Nuclear Information System (INIS)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N'Guessan

    2008-01-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation

  5. Technical Basis for Assessing Uranium Bioremediation Performance

    Energy Technology Data Exchange (ETDEWEB)

    PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL N’Guessan

    2008-04-01

    In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation.

  6. Performance of operating and advanced light water reactor designs. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-10-01

    Nuclear power can provide security of energy supply, stable energy costs, and can contribute to greenhouse gas reduction. To fully realize these benefits, a continued and strong focus must be maintained on means for assuring the economic competitiveness of nuclear power relative to alternatives. Over the past several years, considerable improvements have been achieved in nuclear plant performance. Worldwide, the average energy availability factor has increased from 66 per cent in 1980 to 81 per cent in 1999, with some utilities achieving significantly higher values. This is being achieved through integrated programmes including personnel training and quality assurance, improvements in plant system and component design and plant operation, by various means to reduce outage duration for maintenance and refuelling and other scheduled shutdowns, and by reducing the number of forced outages. Application of technical means for achieving high performance of nuclear power plants is an important element for assuring their economic competitiveness. For the current plants, proper management includes development and application of better technologies for inspection, maintenance and repair. For future plants, the opportunity exists during the design phase to incorporate design features and technologies for achieving high performance. This IAEA Technical Committee meeting (TCM) provided a forum for information exchange on design features and technologies incorporated into LWR plants commissioned within the last 15-20 years, and into evolutionary LWR designs still under development, for achieving performance improvements with due regard to stringent safety requirements and objectives. It also addressed on-going technology development expected to achieve further improvements and/or significant cost reductions. The TCM was attended by 32 participants from 14 Member States: Argentina, Bulgaria, Czech Republic, Finland, France, Germany, Hungary, Japan, Republic of Korea, Mexico

  7. Plant performance monitoring program at Krsko NPP

    International Nuclear Information System (INIS)

    Bach, B.; Kavsek, D.

    2004-01-01

    A high level of nuclear safety and plant reliability results from the complex interaction of a good design, operational safety and human performance. This is the reason for establishing a set of operational plant safety performance indicators, to enable monitoring of both plant performance and progress. Performance indicators are also used for setting challenging targets and goals for improvement, to gain additional perspective on performance relative to other plants and to provide an indication of a potential need to adjust priorities and resources to achieve improved overall plant performance. A specific indicator trend over a certain period can provide an early warning to plant management to evaluate the causes behind the observed changes. In addition to monitoring the changes and trends, it is also necessary to compare the indicators with identified targets and goals to evaluate performance strengths and weaknesses. Plant Performance Monitoring Program at Krsko NPP defines and ensures consistent collection, processing, analysis and use of predefined relevant plant operational data, providing a quantitative indication of nuclear power plant performance. When the program was developed, the conceptual framework described in IAEA TECDOC-1141 Operational Safety Performance Indicators for Nuclear Power Plants was used as its basis in order to secure that a reasonable set of quantitative indications of operational safety performance would be established. Safe, conservative, cautious and reliable operation of the Krsko NPP is a common goal for all plant personnel. It is provided by continuous assurance of both health and safety of the public and employees according to the plant policy stated in program MD-1 Notranje usmeritve in cilji NEK, which is the top plant program. Establishing a program of monitoring and assessing operational plant safety performance indicators represents effective safety culture of plant personnel.(author)

  8. Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

    International Nuclear Information System (INIS)

    Sturm, A.; Foerster, R.

    1977-01-01

    Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

  9. PUREX Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The PUREX aggregate area is made up of six operable units; 200-PO-1 through 200-PO-6 and consists of liquid and solid waste disposal sites in the vicinity of, and related to, PUREX Plant operations. This report describes PUREX and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  10. Cycling of conventional power plants: Technical limits and actual costs

    International Nuclear Information System (INIS)

    Van den Bergh, Kenneth; Delarue, Erik

    2015-01-01

    Highlights: • Literature reports a wide range of cycling parameters (technical and cost-related). • The impact of different cycling parameters is assessed. • The German 2013 system is studied as a case study. • Even for stringent parameters, the dynamic limit of the portfolio is not reached. • Cycling costs can be reduced with 40% when taken into account in the scheduling. - Abstract: Cycling of conventional generation units is an important source of operational flexibility in the electricity generation system. Cycling is changing the power output of conventional units by means of ramping and switching (starting up and shutting down). In the literature, a wide range of technical and cost-related cycling parameters can be found. Different studies allocate different cycling parameters to similar generation units. This paper assesses the impact of different cycling parameters allocated to a conventional generation portfolio. Both the technical limitations of power plants and all costs related to cycling are considered. The results presented in this paper follow from a unit commitment model, used for a case study based on the German 2013 system. The conventional generation portfolio has to deliver different residual load time series, corresponding to different levels of renewables penetration. The study shows, under the assumptions made, that although the dynamic limits of some units are reached, the limits of the conventional generation portfolio as a whole are not reached, even if stringent dynamic parameters are assigned to the generation portfolio and a highly variable residual load is imposed to the system. The study shows also the importance of including full cycling costs in the unit commitment scheduling. The cycling cost can be reduced by up to 40% when fully taken into account

  11. B Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The B aggregate area is made up of 13 operable units; 200-BP 1 through 200-BP 1 1, 200-IU-6, and 200-SS-1 that consist of liquid and solid waste disposal sites in the vicinity of, and related to, B Plant operations. This report describes B Plant and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  12. Technical Report Cellulosic Based Black Liquor Gasification and Fuels Plant Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Fornetti, Micheal [Escanaba Paper Company, MI (United States); Freeman, Douglas [Escanaba Paper Company, MI (United States)

    2012-10-31

    The Cellulosic Based Black Liquor Gasification and Fuels Plant Project was developed to construct a black liquor to Methanol biorefinery in Escanaba, Michigan. The biorefinery was to be co-located at the existing pulp and paper mill, NewPage’s Escanaba Paper Mill and when in full operation would: • Generate renewable energy for Escanaba Paper Mill • Produce Methanol for transportation fuel of further refinement to Dimethyl Ether • Convert black liquor to white liquor for pulping. Black liquor is a byproduct of the pulping process and as such is generated from abundant and renewable lignocellulosic biomass. The biorefinery would serve to validate the thermochemical pathway and economic models for black liquor gasification. It was a project goal to create a compelling new business model for the pulp and paper industry, and support the nation’s goal for increasing renewable fuels production and reducing its dependence on foreign oil. NewPage Corporation planned to replicate this facility at other NewPage Corporation mills after this first demonstration scale plant was operational and had proven technical and economic feasibility. An overview of the process begins with black liquor being generated in a traditional Kraft pulping process. The black liquor would then be gasified to produce synthesis gas, sodium carbonate and hydrogen sulfide. The synthesis gas is then cleaned with hydrogen sulfide and carbon dioxide removed, and fed into a Methanol reactor where the liquid product is made. The hydrogen sulfide is converted into polysulfide for use in the Kraft pulping process. Polysulfide is a known additive to the Kraft process that increases pulp yield. The sodium carbonate salts are converted to caustic soda in a traditional recausticizing process. The caustic soda is then part of the white liquor that is used in the Kraft pulping process. Cellulosic Based Black Liquor Gasification and Fuels Plant project set out to prove that black liquor gasification could

  13. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  14. The performance trends of nuclear power plants worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Glorian, D. [Electricite de France (EDF), 93 - Saint-Denis (France)

    2001-07-01

    Looking back to the worldwide operating experience feedback, which performance trends and conclusions could be drawn up? What is the specific situation of the French nuclear units, in comparison with the average worldwide performance? The performance of a unit or group of facilities is measured not only in technical terms (safety, availability, load control capability), but also from an economic and financial standpoint (operating and maintenance costs, fuel costs, etc). Performance in terms of radiological protection and on-the-job safety, as well as environmental protection, is also monitored in order to give the broadest possible overview of nuclear power plant performance. The main technical results are presented on the basis of selected performance indicators. The results obtained by French units are benchmarked against those of other PWR facilities in operation around the world, in accordance with comparisons made by the World Association of Nuclear Operators (WANO). (author)

  15. The performance trends of nuclear power plants worldwide

    International Nuclear Information System (INIS)

    Glorian, D.

    2001-01-01

    Looking back to the worldwide operating experience feedback, which performance trends and conclusions could be drawn up? What is the specific situation of the French nuclear units, in comparison with the average worldwide performance? The performance of a unit or group of facilities is measured not only in technical terms (safety, availability, load control capability), but also from an economic and financial standpoint (operating and maintenance costs, fuel costs, etc). Performance in terms of radiological protection and on-the-job safety, as well as environmental protection, is also monitored in order to give the broadest possible overview of nuclear power plant performance. The main technical results are presented on the basis of selected performance indicators. The results obtained by French units are benchmarked against those of other PWR facilities in operation around the world, in accordance with comparisons made by the World Association of Nuclear Operators (WANO). (author)

  16. Evaluation of the feasibility, economic impact, and effectiveness of underground nuclear power plants. Final technical report

    International Nuclear Information System (INIS)

    1978-05-01

    Information on underground nuclear power plants is presented concerning underground nuclear power plant concepts; public health impacts; technical feasibility of underground concepts; economic impacts of underground construction; and evaluation of related issues

  17. An analysis of factors that influence the technical efficiency of Malaysian thermal power plants

    International Nuclear Information System (INIS)

    See, Kok Fong; Coelli, Tim

    2012-01-01

    The main objectives of this paper are to measure the technical efficiency levels of Malaysian thermal power plants and to investigate the degree to which various factors influence efficiency levels in these plants. Stochastic frontier analysis (SFA) methods are applied to plant-level data over an eight year period from 1998 to 2005. This is the first comprehensive analysis (to our knowledge) of technical efficiency in the Malaysian electricity generation industry using parametric method. Our empirical results indicate that ownership, plant size and fuel type have a significant influence on technical efficiency levels. We find that publicly-owned power plants obtain average technical efficiencies of 0.68, which is lower than privately-owned power plants, which achieve average technical efficiencies of 0.88. We also observe that larger power plants with more capacity and gas-fired power plants tend to be more technically efficient than other power plants. Finally, we find that plant age and peaking plant type have no statistically significant influence on the technical efficiencies of Malaysian thermal power plants. - Highlights: ► We examine the technical efficiency (TE) levels of Malaysian thermal power plants. ► We also investigate the degree to which various factors influence efficiency levels in these plants. ► Stochastic frontier analysis methods are used. ► Average plant would have to increase their TE level by 21% to reach the efficient frontier. ► Ownership, plant size and fuel type have a significant influence on the TE levels.

  18. Nuclear design and technical development required for ISER plant

    International Nuclear Information System (INIS)

    Yokoyama, Takashi; Yamano, Naoki.

    1987-01-01

    The report outlines some results of a study carried out by the ISER (intrinsically safe and economical reactor) Investigation Group. In particular, nuclear design concepts are examined in relation to the fuel cycle. Discussion is also made on technical development efforts to be made for realizing an ISER. Calculation of some basic nuclear design parameters is performed and results are used to examine the reactor core and fuel for ISER. As a result, it is indicated that a high-burnup type reactor core should be used on a 4.5-batch replacement, 15 EFPM (effective full power month) scheme to optimize an ISER. For technical development, consideration is made on various tests to be performed with an experimental reactor, called ISER-E, as well as other tests to provide basic data required for demonstrating the inherent safety of ISER. The study also deals with the possibility of the application of currently available light water reactor techniques to experiments with a critical assembly, non-nuclear test loop, and the experimental reactor ISER-E. It is revealed that many of the required experiments can be carried out by using test facilities and light water reactor techniques which are currently, or will be readily, available. It is stressed that international cooperation is necessary to accomplish these tests. (Nogami, K.)

  19. Restructuring of technical standards for regulation of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Takehiko Nakamura; Masahiro Aoki; Kiyoshi Takasaka; Yukio Hirano; Eiji Hiraoka; Mikio Kurihara; Junichi Morita; Zenichi Ogiso; Yoshihiko Nishiwaki

    2005-01-01

    Regulatory requirements for nuclear power plants (NPPs) have been reviewed and restructured in Japan, in order to accommodate recent technical progress in a timely manner. In this new regulatory process, the governmental technical requirements are modified to performance specifications and the consensus codes and standards established by academic and public societies are being used as prescriptive specifications to realize the performance. As a first step, a fitness-rule to evaluate structural integrity of the components having cracks was introduced into the Japanese regulatory rules in Oct. 2003. 'Rules on Fitness-for-Service for Nuclear Power Plants' by the Japan Society of Mechanical Engineers (JSME) was utilized as a prescriptive specification for in-service-inspections and for the integrity evaluation of the components with stress corrosion cracks and fatigue cracks. The process is being extended to other requirements for structural design and construction of mechanical components and concrete containments, as well as requirements for welding. Prescriptive specifications for the requirements by the JSME and other consensus codes have been technically reviewed by a regulatory body, the Nuclear and Industrial Safety Agency, and specified as regulatory standards for the licensing procedure. In the course of the review, consistency and coverage of the requirements were examined against the Safety Design Guidelines by the Nuclear Safety Commission and the safety requirements for design of nuclear power plant by the International Atomic Energy Agency, NS-R-1. Additional requirements against the stress corrosion cracking, hydrogen accumulation, high-cycle thermal fatigue, etc. are being specified in the requirements to prevent troubles experienced in NPPs in Japan and overseas. This paper describes outlines of the on-going activities restructuring the technical standards for regulation of NPPs in Japan. (authors)

  20. Qualification and actuation of the independent technical supervision organisms in nuclear power plants and others facilities

    International Nuclear Information System (INIS)

    1999-09-01

    This norm presents the following objectives: establishment of the Brazilian National Nuclear Energy Commission requirements for qualifying an institution as independent technical supervision organization, in a specific area of activity related to nuclear power plants and others nuclear or radioactive facilities as appropriated; regulation of the independent technical supervision and others complementary activities to be executed by an independent technical supervision organism

  1. Technical specifications review of nuclear power plants: a risk-informed evaluation

    International Nuclear Information System (INIS)

    Saldanha, Pedro Luiz da Cruz; Sousa, Anna Leticia; Frutuoso e Melo, Paulo Fernando Ferreira; Duarte, Juliana Pacheco

    2012-01-01

    The use of risk information by a regulatory body as part of an integrated decision making process addresses the way in which risk information is being used as part of an integrated process in making decisions about safety issues at nuclear plants – commonly referred to as risk-informed decision making. The risk-informed approach aims to integrate in a systematic manner quantitative and qualitative, deterministic and probabilistic safety considerations to obtain a balanced decision. Probabilistic Safety Assessment (PSA) is a methodology that can be applied to provide a structured analysis process to evaluate the frequency and consequences of accidents scenarios in nuclear power plants. Technical Specifications (TS) are specifications regarding the characteristics of nuclear power plants (variables, systems or components) of overriding importance to nuclear safety and radiation protection, which is an integral part of plant operation authorization. Limiting Conditions of Operation (LCO) are the minimum levels of performance or capacity or operating system components required for the safe operation of nuclear plants, as defined in technical specifications. The Maintenance Rule (MR) is a requirement established by the U. S. Nuclear Regulatory Commission (NRC) to check the effectiveness of maintenance carried out in nuclear plants, and plant configuration control. The control of plant configuration is necessary to verify the impact of the maintenance of a safety device out of service on plant safety. The Electric Power Research Institute (EPRI) has assessed the role of probabilistic safety analysis in the regulation of nuclear power plants with the following objectives: a) to provide utilities with an approach for developing and implementing nuclear power station risk-managed technical specification programs; and b) to complement and supplement existing successful configuration risk management applications such as MR. This paper focuses on the evaluation of EPRI

  2. Technical performance of percutaneous and laminectomy leads analyzed by modeling

    NARCIS (Netherlands)

    Manola, L.; Holsheimer, J.

    2004-01-01

    The objective of this study was to compare the technical performance of laminectomy and percutaneous spinal cord stimulation leads with similar contact spacing by computer modeling. Monopolar and tripolar (guarded cathode) stimulation with both lead types in a low-thoracic spine model was simulated

  3. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  4. Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Rubiolo, Pablo R. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Conway, Lawarence E. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Oriani, Luca [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Lahoda, Edward J. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; DeSilva, Greg [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Hu, Min H. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Hartz, Josh [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Bachrach, Uriel [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Smith, Larry [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Dudek, Daniel F. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Toman, Gary J. [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Feng, Dandong [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Hejzlar, Pavel [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Kazimi, Mujid S. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2006-03-31

    This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a standard 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (~600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output.

  5. Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

    International Nuclear Information System (INIS)

    Rubiolo, Pablo R.; Conway, Lawarence E.; Oriani, Luca; Lahoda, Edward J.; DeSilva, Greg; Hu, Min H.; Hartz, Josh; Bachrach, Uriel; Smith, Larry; Dudek, Daniel F.; Toman, Gary J.; Feng, Dandong; Hejzlar, Pavel; Kazimi, Mujid S.

    2006-01-01

    This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a ''standard'' 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (∼600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output

  6. Conceptual design of small-sized HTGR system (4). Plant design and technical feasibility

    International Nuclear Information System (INIS)

    Ohashi, Hirofumi; Sato, Hiroyuki; Yan, Xing L.; Sumita, Junya; Nomoto, Yasunobu; Tazawa, Yujiro; Noguchi, Hiroki; Imai, Yoshiyuki; Tachibana, Yukio

    2013-09-01

    Japan Atomic Energy Agency (JAEA) has started a conceptual design of a 50MWt small-sized high temperature gas cooled reactor (HTGR) for steam supply and electricity generation (HTR50S), which is a first-of-kind of the commercial plant or a demonstration plant of a small-sized HTGR system for steam supply to the industries and district heating and electricity generation by a steam turbine, to deploy in developing countries in the 2020s. HTR50S was designed for steam supply and electricity generation by the steam turbine with the reactor outlet temperature of 750degC as a reference plant configuration. On the other hand, the intermediate heat exchanger (IHX) will be installed in the primary loop to demonstrate the electricity generation by the helium gas turbine and hydrogen production by thermochemical water splitting by utilizing the secondary helium loop with the reactor outlet temperature of 900degC as a future plant configuration. The plant design of HTR50S for the steam supply and electricity generation was performed based on the plant specification and the requirements for each system taking into account for the increase of the reactor outlet coolant temperature from 750degC to 900degC and the installation of IHX. The technical feasibility of HTR50S was confirmed because the designed systems (i.e., reactor internal components, reactor pressure vessel, vessel cooling system, shutdown cooling system, steam generator (SG), gas circulator, SG isolation and drainage system, reactor containment vessel, steam turbine and heat supply system) satisfies the design requirements. The conceptual plant layout was also determined. This paper provides the summary of the plan design and technical feasibility of HTR50S. (author)

  7. 2011 PERFORMANCE ASSESSMENT COMMUNITY OF PRACTICE TECHNICAL EXCHANGE - SUMMARY

    Energy Technology Data Exchange (ETDEWEB)

    Seitz, R.

    2011-12-30

    The Performance Assessment Community of Practice (PA CoP) was developed in 2008 to improve consistency and quality in the preparation of performance assessments (PAs) and risk assessments across the Department of Energy (DOE) Complex. The term, PA, is used to represent all of these modeling applications in this report. The PA CoP goals are to foster the exchange of information among PA practitioners and to share lessons learned from PAs conducted for DOE, commercial disposal facilities, and international entities. Technical exchanges and workshops are a cornerstone of PA CoP activities. Previous technical exchanges have addressed Engineered Barriers (2009 - http://www.cresp.org/education/workshops/pacop/), the Advanced Simulation Capability for Environmental Management and the Cementitious Barriers Partnership (2010 - http://srnl.doe.gov/copexchange/links.htm). Each technical exchange also includes summary presentations regarding activities at DOE, the Nuclear Regulatory Commission (NRC) and other organizations (e.g., International Atomic Energy Agency (IAEA)) as well as a number of presentations from selected sites to provide insight and perspective from on-going modeling activities. Through the deployment of PA Assistance Teams, the PA CoP has also been engaged in the development of new PAs across the DOE Complex. As a way of improving consistency in the preparation of new PAs, the teams provide technical advice and share experiences, noteworthy practices, and lessons learned from previous Low-Level Waste Disposal Facility Federal Review Group (LFRG) reviews. Teams have provided support for PAs at Hanford, Idaho, Paducah and Portsmouth. The third annual PA CoP Technical Exchange was held on May 25-26, 2011 in Atlanta, GA. The PA CoP Steering Committee Meeting held its first meeting on May 24 prior to the Technical Exchange. Decision making using models and software quality assurance were the topical emphasis for the exchange. A new feature at the 2011 technical

  8. Gasification Plant Cost and Performance Optimization

    Energy Technology Data Exchange (ETDEWEB)

    Samuel Tam; Alan Nizamoff; Sheldon Kramer; Scott Olson; Francis Lau; Mike Roberts; David Stopek; Robert Zabransky; Jeffrey Hoffmann; Erik Shuster; Nelson Zhan

    2005-05-01

    As part of an ongoing effort of the U.S. Department of Energy (DOE) to investigate the feasibility of gasification on a broader level, Nexant, Inc. was contracted to perform a comprehensive study to provide a set of gasification alternatives for consideration by the DOE. Nexant completed the first two tasks (Tasks 1 and 2) of the ''Gasification Plant Cost and Performance Optimization Study'' for the DOE's National Energy Technology Laboratory (NETL) in 2003. These tasks evaluated the use of the E-GAS{trademark} gasification technology (now owned by ConocoPhillips) for the production of power either alone or with polygeneration of industrial grade steam, fuel gas, hydrocarbon liquids, or hydrogen. NETL expanded this effort in Task 3 to evaluate Gas Technology Institute's (GTI) fluidized bed U-GAS{reg_sign} gasifier. The Task 3 study had three main objectives. The first was to examine the application of the gasifier at an industrial application in upstate New York using a Southeastern Ohio coal. The second was to investigate the GTI gasifier in a stand-alone lignite-fueled IGCC power plant application, sited in North Dakota. The final goal was to train NETL personnel in the methods of process design and systems analysis. These objectives were divided into five subtasks. Subtasks 3.2 through 3.4 covered the technical analyses for the different design cases. Subtask 3.1 covered management activities, and Subtask 3.5 covered reporting. Conceptual designs were developed for several coal gasification facilities based on the fluidized bed U-GAS{reg_sign} gasifier. Subtask 3.2 developed two base case designs for industrial combined heat and power facilities using Southeastern Ohio coal that will be located at an upstate New York location. One base case design used an air-blown gasifier, and the other used an oxygen-blown gasifier in order to evaluate their relative economics. Subtask 3.3 developed an advanced design for an air

  9. Audits and their effectiveness in improving plant performance

    International Nuclear Information System (INIS)

    Callen, L.J.

    1986-01-01

    For several years, the NRC's performance appraisal teams (PATs) have been assessing the effectiveness of the various audit programs established by operating nuclear power plants. A major focus of the PAT assessments is on the audit programs mandated by 10 CFR, technical specifications, industry codes and standards, and NRC operating license conditions. These audits are typically performed by a plant's quality assurance organization, and program oversight is often provided at the corporate level by a safety review committee. The scope of these audit programs is broad, typically including such functional areas as maintenance, operations, health physics, emergency preparedness, training, procurement, and security. For an audit program to be truly effective in improving plant performance beyond the minimum level established by regulatory requirements, the audits must first be effective in identifying deficiencies that go beyond minimum regulatory requirements. The PAT experience to date is that typical industry audit programs are not designed to identify these types of deficiencies

  10. Relationship between non-technical skills and technical performance during cardiopulmonary resuscitation: does stress have an influence?

    Science.gov (United States)

    Krage, Ralf; Zwaan, Laura; Tjon Soei Len, Lian; Kolenbrander, Mark W; van Groeningen, Dick; Loer, Stephan A; Wagner, Cordula; Schober, Patrick

    2017-11-01

    Non-technical skills, such as task management, leadership, situational awareness, communication and decision-making refer to cognitive, behavioural and social skills that contribute to safe and efficient team performance. The importance of these skills during cardiopulmonary resuscitation (CPR) is increasingly emphasised. Nonetheless, the relationship between non-technical skills and technical performance is poorly understood. We hypothesise that non-technical skills become increasingly important under stressful conditions when individuals are distracted from their tasks, and investigated the relationship between non-technical and technical skills under control conditions and when external stressors are present. In this simulator-based randomised cross-over study, 30 anaesthesiologists and anaesthesia residents from the VU University Medical Center, Amsterdam, the Netherlands, participated in two different CPR scenarios in random order. In one scenario, external stressors (radio noise and a distractive scripted family member) were added, while the other scenario without stressors served as control condition. Non-technical performance of the team leader and technical performance of the team were measured using the 'Anaesthetists' Non-technical Skill' score and a recently developed technical skills score. Analysis of variance and Pearson correlation coefficients were used for statistical analyses. Non-technical performance declined when external stressors were present (adjusted mean difference 3.9 points, 95% CI 2.4 to 5.5 points). A significant correlation between non-technical and technical performance scores was observed when external stressors were present (r=0.67, 95% CI 0.40 to 0.83, ptechnical performance score (task management, team working, situation awareness, decision-making). During CPR with external stressors, the team's technical performance is related to the non-technical skills of the team leader. This may have important implications for training of

  11. Have U.S. power plants become less technically efficient? The impact of carbon emission regulation

    International Nuclear Information System (INIS)

    Zhou, Yishu; Huang, Ling

    2016-01-01

    We estimate directional distance functions to measure the impact of carbon emission regulation, the Regional Greenhouse Gas Initiative (RGGI) in particular, on U.S. power plants' technical efficiency. The model shows that the average technical efficiency scores for coal and natural gas plants are 88.70% and 83.14% respectively, indicating a very technically efficient industry. We find no evidence of technical efficiency changes due to the RGGI regime in the RGGI area. In the same area, relatively less efficient coal plants exited the market and slightly more efficient natural gas plants entered, compared to the incumbent plants. In addition, some evidence of a spillover effect is found. Using a counterfactual analysis, the RGGI regulation leads to a 1.48% decline in the average technical efficiency for coal plants within neighboring states of RGGI during 2009–2013. - Highlights: • RGGI does not lead to a change in the technical efficiency of RGGI power plants. • Less efficient coal plants exit. • Entering natural gas plants are more efficient. • RGGI has a spillover effect on neighboring coal plants.

  12. Guideline for the seismic technical evaluation of replacement items for nuclear power plants

    International Nuclear Information System (INIS)

    Harris, S.P.; Cushing, R.W.; Johnson, H.W.; Abeles, J.M.

    1993-02-01

    Seismic qualification for equipment originally installed in nuclear power plants was typically performed by the original equipment suppliers or manufactures (OES/OEM). Many of the OES/OEM no longer maintain quality assurance programs with adequate controls for supplying nuclear equipment. Utilities themselves must provide reasonable assurance in the continued seismic adequacy of such replacement items. This guideline provides practical, cost-effective techniques which can be used to provide reasonable assurance that replacement items will meet seismic performance requirements necessary to maintain the seismic design basis of commercial nuclear power plants. It also provides a method for determining when a seismic technical evaluation of replacement items (STERI) is required as part of the procurement process for spare and replacement items. Guidance on supplier program requirements necessary to maintain continued seismic adequacy and on documentation of maintaining required seismic adequacy is also included

  13. The impact of technical specification surveillance requirements and allowable outage times on plant availability

    International Nuclear Information System (INIS)

    Webster, S.A.; Finnicum, D.J.

    1985-01-01

    Surveillances required to be conducted by a plant's Technical Specifications have resulted in plant shutdowns and lost availability. This paper looks at shutdowns which have occurred due to required surveillance testing and insufficient repair time allowed by Technical Specifications. A loss of plant availability of almost 3% per plant year was found for U.S. pressurized water reactors during the five year period, 1979 to 1984. This figure excludes major problems which required plant shutdown whether or not mandated by the Technical Specifications. In addition to their affect on availability, such shutdowns can add to the challenges to plant safety systems and can affect plant aging by increasing the thermal cycles on plant components

  14. The Vehicle Integrated Performance Analysis Experience: Reconnecting With Technical Integration

    Science.gov (United States)

    McGhee, D. S.

    2006-01-01

    Very early in the Space Launch Initiative program, a small team of engineers at MSFC proposed a process for performing system-level assessments of a launch vehicle. Aimed primarily at providing insight and making NASA a smart buyer, the Vehicle Integrated Performance Analysis (VIPA) team was created. The difference between the VIPA effort and previous integration attempts is that VIPA a process using experienced people from various disciplines, which focuses them on a technically integrated assessment. The foundations of VIPA s process are described. The VIPA team also recognized the need to target early detailed analysis toward identifying significant systems issues. This process is driven by the T-model for technical integration. VIPA s approach to performing system-level technical integration is discussed in detail. The VIPA process significantly enhances the development and monitoring of realizable project requirements. VIPA s assessment validates the concept s stated performance, identifies significant issues either with the concept or the requirements, and then reintegrates these issues to determine impacts. This process is discussed along with a description of how it may be integrated into a program s insight and review process. The VIPA process has gained favor with both engineering and project organizations for being responsive and insightful

  15. Mental Fatigue Impairs Soccer-Specific Physical and Technical Performance.

    Science.gov (United States)

    Smith, Mitchell R; Coutts, Aaron J; Merlini, Michele; Deprez, Dieter; Lenoir, Matthieu; Marcora, Samuele M

    2016-02-01

    To investigate the effects of mental fatigue on soccer-specific physical and technical performance. This investigation consisted of two separate studies. Study 1 assessed the soccer-specific physical performance of 12 moderately trained soccer players using the Yo-Yo Intermittent Recovery Test, Level 1 (Yo-Yo IR1). Study 2 assessed the soccer-specific technical performance of 14 experienced soccer players using the Loughborough Soccer Passing and Shooting Tests (LSPT, LSST). Each test was performed on two occasions and preceded, in a randomized, counterbalanced order, by 30 min of the Stroop task (mentally fatiguing treatment) or 30 min of reading magazines (control treatment). Subjective ratings of mental fatigue were measured before and after treatment, and mental effort and motivation were measured after treatment. Distance run, heart rate, and ratings of perceived exertion were recorded during the Yo-Yo IR1. LSPT performance time was calculated as original time plus penalty time. LSST performance was assessed using shot speed, shot accuracy, and shot sequence time. Subjective ratings of mental fatigue and effort were higher after the Stroop task in both studies (P motivation was similar between conditions. This mental fatigue significantly reduced running distance in the Yo-Yo IR1 (P performance time were not different between conditions; however, penalty time significantly increased in the mental fatigue condition (P = 0.015). Mental fatigue also impaired shot speed (P = 0.024) and accuracy (P performance.

  16. Performance parameters of a standalone PV plant

    International Nuclear Information System (INIS)

    El Fathi, Amine; Nkhaili, Lahcen; Bennouna, Amin; Outzourhit, Abdelkader

    2014-01-01

    Highlights: • We described in details a photovoltaic power plant installed in the remote rural village Elkaria (Essaouira Morocco – 7.2 kWp). • We presented the results of monitoring and some performance parameters of the plant such as load curve. • We discussed the energy management of the plant which is based on the droop mode control. • We presented and discussed the yields and the performance ratio of the plant. - Abstract: In this work we present a detailed description of a 7.2 kWp photovoltaic power plant installed in the remote rural village Elkaria (province of Essaouira in Morocco). This plant supplies 16 households with electricity through a local grid that was installed for this purpose. The results of monitoring some performance parameters of the plant such as load curve, the yields and the performance ratio are presented and discussed. The performance ratio of the PV plant varied between 33% and 70.2%. The low values of this parameter are mainly attributed to the way the battery inverter manages the energy flow

  17. Technical evaluation of RETS-required reports for Crystal River Nuclear Generating Plant, Unit 3, for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Florida Power Corporation's Crystal River Nuclear Plant, Unit 3, during 1983. The three periodic reports reviewed were (1) the Effluent and Waste Disposal Semiannual Report, January 1-June 30, 1983, (2) the Effluent and Waste Disposal Semiannual Report, July 1-December 31, 1983, and (3) the Annual Environmental Operating Report, Radiological, 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  18. Application of solar energy to the supply of industrial process hot water: preliminary design and performance report. Volume I. Technical report. Aerotherm report TR-76-219. [For can washing at Campbell Soup Plant in Sacramento

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-10-14

    The design and performance of a solar hot water system for can washing at the Campbell Soup Plant in Sacramento, California, are presented. The collector field is located on the roof of the finished products warehouse of the Campbell Soup Sacramento plant. Water is supplied from a 3.8 cm (1/sup 1///sub 2/ in.) supply line which is located directly below an existing roof access hatch. A supply pipe will be brought up through that hatch. The water flow will then be split into two manifold lines which supply the dual rows of flat plate collectors. The preheated water from the flat plates is then passed into six sets of parallel connected concentrators. Each set consist of eight 1.83 x 3.05 m (6 x 10 foot) modules connected in series. The water from these units is gathered in a 3.8 cm (1/sup 1///sub 2/ in.) insulated pipe which transports it to the storage tank. This pipe will be attached to an existing pipe run until it reaches the can washing building. From there the pipe will follow the can washing building around to the storage tank. The storage tank is a 75,200 1 (20,000 gal) steel tank which is coated internally with a USDA approved phenolic liner. The outside of the tank is insulated. A 2.2 kw (3 hp) motor is used to pump the stored water for the tank into the can washing line. Detail drawings and descriptions of the collector field, installation, piping, controls, data acquisition equipment, and roof structure are included. Furthermore, a program schedule with equipment and manpower costs for successfully completing Phase II of this contract is included. Also included is an organization chart of the Phase II program personnel. (WHK)

  19. Branch technical position for performance assessment of low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Campbell, A.C.; Abramson, L.; Byrne, R.M.

    1994-01-01

    The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

  20. Numerical indicators of nuclear power plant safety performance

    International Nuclear Information System (INIS)

    1991-04-01

    The workshop was attended by representatives from twenty-two Member States operating nuclear power plants (NPP). The current status of the development and use of numerical indicators of NPP safety performance was presented. A consensus on the benefits of use of numerical indicators was reached. The Technical Committee Meeting reviewed the progress in the development and use of performance indicators and identified them as the most appropriate ones for international use. The purpose of this document is to summarize the discussions held and conclusions reached in both meetings. Lists of participants and all the papers of both meetings are presented

  1. Next Generation Nuclear Plant Methods Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-09-01

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

  3. Technical evaluation on high aging, and performance conditions on long-term conservation program

    International Nuclear Information System (INIS)

    Yamashita, Atsushi

    2001-01-01

    In order to secure safety and safe operation of power plants, in every nuclear power plants, conservation actions based on preventive conservation are performed. They contain operative condition monitoring, patrolling inspection, and periodical tests on important systems and apparatus by operators under plant operation and condition monitoring by maintenance workers, and so on, and when finding out their abnormal conditions, their detailed survey is performed to adopt adequate countermeasures such as recovery, exchange, and so on. And, to equipments for nuclear power generation periodical conditions were obliged by legal examinations and by independent inspections. As a result of these conservation actions, even on a plant elapsed about 30 years since beginning of its operation it was thought that the plant was aged with elapsing time even if not recognizing any indication on its aged deterioration at that time. Therefore, for its concrete countermeasure, by supposing long-term operation of a plant with longer operation history, some technical evaluation on aged phenomena were carried out, to investigate on reflection of the obtained results to present conservation actions. Here were described on efforts on the high aging countermeasures, and performing conditions of long-term conservation in the Tsuruga Unit No. 1 Nuclear Power Station. (G.K.)

  4. Catalogue and classification of technical safety rules for light-water reactors and reprocessing plants

    International Nuclear Information System (INIS)

    Bloser, M.; Fichtner, N.; Neider, R.

    1975-08-01

    This report on the cataloguing and classification of technical rules for land-based light-water reactors and reprocessing plants contains a list of classified rules. The reasons for the classification system used are given and discussed

  5. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    John Collins

    2009-01-01

    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.

  6. Comparison of methods applicable to evaluation of nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    Cho, N.Z.; Bozoki, G.E.; Youngblood, R.W.

    1986-01-01

    This study compares three probabilistic methods based on the static fault tree analysis, time-dependent unavailability analysis, and Markov analysis, which can be used to evaluate technical specifications in nuclear power plants. They are tested on a sample problem which was devised to closely represent the important and essential characteristics that should be addressed in determination and evaluation of the technical specifications

  7. XML: Solution for the integration of nuclear power plant data and technical documents

    International Nuclear Information System (INIS)

    Gordillo, F.

    2000-01-01

    Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

  8. KWL Lingen nuclear plant. Technical annual report 2016; KWL Kernkraftwerk Lingen. Technischer Jahresbericht 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-07-01

    The technical annual report 2016 for KWL (Lingen nuclear plant) covers the following sections: dismantling project management and operation, monitoring and clearance; waste management, technical qualification, security and safety, central tasks; licensing and supervision procedures, operational data, radiation monitoring, radioactive materials, in-service inspections.

  9. Performance of Generating Plant: Managing the Changes. Part 1: International availability data exchange for thermal generating plant

    Energy Technology Data Exchange (ETDEWEB)

    Stallard, G.S.; Deschaine, R. [Black and Veatch (United States)

    2008-05-15

    The WEC Committee on the Performance of Generating Plant (PGP) has been collecting and analysing power plant performance statistics worldwide for more than 30 years and has produced regular reports, which include examples of advanced techniques and methods for improving power plant performance through benchmarking. A series of reports from the various working groups was issued in 2008. This reference presents the results of Working Group 1 (WG1). WG1's primary focus is to analyse the best ways to measure, evaluate, and apply power plant performance and availability data to promote plant performance improvements worldwide. The paper explores the specific work activities of 2004-2007 to extend traditional analysis and benchmarking frameworks. It is divided into two major topics: Overview of current electric supply industry issues/trends; and, Technical Methods/Tools to evaluate performance in today's ESI.

  10. GASIFICATION PLANT COST AND PERFORMANCE OPTIMIZATION

    Energy Technology Data Exchange (ETDEWEB)

    Samuel S. Tam

    2002-05-01

    The goal of this series of design and estimating efforts was to start from the as-built design and actual operating data from the DOE sponsored Wabash River Coal Gasification Repowering Project and to develop optimized designs for several coal and petroleum coke IGCC power and coproduction projects. First, the team developed a design for a grass-roots plant equivalent to the Wabash River Coal Gasification Repowering Project to provide a starting point and a detailed mid-year 2000 cost estimate based on the actual as-built plant design and subsequent modifications (Subtask 1.1). This unoptimized plant has a thermal efficiency of 38.3% (HHV) and a mid-year 2000 EPC cost of 1,681 $/kW. This design was enlarged and modified to become a Petroleum Coke IGCC Coproduction Plant (Subtask 1.2) that produces hydrogen, industrial grade steam, and fuel gas for an adjacent Gulf Coast petroleum refinery in addition to export power. A structured Value Improving Practices (VIP) approach was applied to reduce costs and improve performance. The base case (Subtask 1.3) Optimized Petroleum Coke IGCC Coproduction Plant increased the power output by 16% and reduced the plant cost by 23%. The study looked at several options for gasifier sparing to enhance availability. Subtask 1.9 produced a detailed report on this availability analyses study. The Subtask 1.3 Next Plant, which retains the preferred spare gasification train approach, only reduced the cost by about 21%, but it has the highest availability (94.6%) and produces power at 30 $/MW-hr (at a 12% ROI). Thus, such a coke-fueled IGCC coproduction plant could fill a near term niche market. In all cases, the emissions performance of these plants is superior to the Wabash River project. Subtasks 1.5A and B developed designs for single-train coal and coke-fueled power plants. This side-by-side comparison of these plants, which contain the Subtask 1.3 VIP enhancements, showed their similarity both in design and cost (1,318 $/kW for the

  11. Better plant performance through better management

    International Nuclear Information System (INIS)

    Csik, B.J.

    1985-01-01

    A forum convened by the IAEA discussed key aspects and current issues of nuclear power plant operations management in depth. Among the topics addressed were the following: the roles and responsibilities of the operating organization, operations management, and the regulatory body; performance objectives and operational procedures and practices, and potential conflict among plant safety, reliability, and economic operation; advances in day-to-day operation; maintenance and quality control; and shaping of the proper attitudes toward safety

  12. Technical Description Lillgrund Wind Power Plant. Lillgrund Pilot Project

    Energy Technology Data Exchange (ETDEWEB)

    Jeppsson, Joakim; Larsen, Poul Erik; Larsson, Aake [Vattenfall Vindkraft AB, Stockholm (Sweden)

    2008-09-15

    Lillgrund offshore wind power plant comprises 48 wind turbines, each rated at 2.3 MW, bringing the total wind farm capacity to 110 MW. The Lillgrund offshore wind power plant is located in a shallow area of Oeresund, 7 km off the coast of Sweden and 7 km south from the Oeresund Bridge connecting Sweden and Denmark. An average wind speed of around 8,5 m/s at hub height, combined with a relatively low water depth of 4 to 8 meters makes it economically feasible to build here. Vattenfall Vindkraft AB is the owner and operator of Lillgrund offshore wind power plant. Lillgrund is a Swedish pilot project supported by the Swedish Energy Agency. The bidding process was completed during 2005 and the offshore power plant was constructed in the period 2006 to 2007. The wind farm was constructed on time and has now been successfully operational since December 2007. There is, however, always potential for improvement and the aim of this report has been to determine and highlight these areas. It is worth noting out that only the electrical system and the foundations are tailor made at offshore wind power plants. The wind turbines are more or less standard products with none or very limited possibilities for project specific design changes. Geotechnical investigations are expensive and it can be difficult to balance the risks as well as the benefits of this expense in the early phases of a large infrastructure project. As a whole, the geotechnical surveys at Lillgrund proved to be useful. They identified potential issues, such as the fact that extra excavation was required for two of the foundations. It also revealed the location of a small number of boulders that would have to be removed. Vattenfall requested a complete study of the electrical system for Lillgrund to be delivered with the bids. That request was not met. Instead Siemens Wind Power began a complete electrical system study after being awarded the Contract. The electrical system study was completed during the

  13. Technical safety appraisal of buildings 9206 and 9212, Oak Ridge Y-12 plant

    International Nuclear Information System (INIS)

    1989-03-01

    This report covers the results of a Safety Performance Review of the Y-12 Plant conducted during the period July 25 through August 3, 1988. A Safety Performance Review is a followup to assess changes in performance since the 1986 Technical Safety Appraisal (TSA). This review is patterned after a TSA and covered the overall safety performance at Y-12, evaluating progress to date against standards of accepted practice. The review included coverage of actions taken in response to recommendations in the TSA conducted in July--August 1986. Remaining issues were identified through an assessment of safety program deficiencies and their root causes. For each of the 14 safety-related functional areas at the Y-12 Plant, results of this review are listed in Section V. These results include a discussion, conclusions, and any new safety concerns for each program. Appendix A contains a description of the system for categorizing concerns, and the concerns are summarily tabulated in Appendix B for all programs. Appendix C describes the contractor's response and current status of each of the 59 recommendations contained in the 1986 TSA

  14. Technical and economic analysis of integrating low-medium temperature solar energy into power plant

    International Nuclear Information System (INIS)

    Wang, Fu; Li, Hailong; Zhao, Jun; Deng, Shuai; Yan, Jinyue

    2016-01-01

    Highlights: • Seven configurations were studied regarding the integration of solar thermal energy. • Economic analysis was conducted on new built plants and retrofitted power plants. • Using solar thermal energy to preheat high pressure feedwater shows the best performance. - Abstract: In order to mitigate CO_2 emission and improve the efficiency of the utilization of solar thermal energy (STE), solar thermal energy is proposed to be integrated into a power plant. In this paper, seven configurations were studied regarding the integration of STE. A 300 MWe subcritical coal-fired plant was selected as the reference, chemical absorption using monoethanolamine solvent was employed for CO_2 ​capture, and parabolic trough collectors and evacuated tube collectors were used for STE collection. Both technical analysis and economic evaluation were conducted. Results show that integrating solar energy with post-combustion CO_2​ capture can effectively increase power generation and reduce the electrical efficiency penalty caused by CO_2 capture. Among the different configurations, Config-2 and Config-6, which use medium temperature STE to replace high pressure feedwater without and with CO_2 capture, show the highest net incremental solar efficiency. When building new plants, integrating solar energy can effectively reduce the levelized cost of electricity (LCOE). The lowest LCOE, 99.28 USD/MWh, results from Config-6, with a parabolic trough collector price of 185 USD/m"2. When retrofitting existing power plants, Config-6 also shows the highest net present value (NPV), while Config-2 has the shortest payback time at a carbon tax of 50 USD/ton CO_2. In addition, both LCOE and NPV/payback time are clearly affected by the relative solar load fraction, the price of solar thermal collectors and the carbon tax. Comparatively, the carbon tax can affect the configurations with CO_2 capture more clearly than those without CO_2 capture.

  15. Central Heating Plant Coal Use Handbook. Volume 1: Technical Reference.

    Science.gov (United States)

    1996-11-01

    CHUTES LIFT TRUCKS MONORAILS , TRAMWAYS J p WEIGHING, 0 MEASURING SCALES COAL METERS HOPPERS SAMPLERS 9 FIRING EQUIPMENT (Source: Power, February...Defense (DOD) installations employ coal- fired central energy plants, the U.S. Army Construction Engineering Research Laboratories (USACERL) was... fired central heat plant operations cost by improving coal quality specifications. The Handbook is tailored for military installation industrial

  16. Development of Molten-Salt Heat Transfer Fluid Technology for Parabolic Trough Solar Power Plants - Public Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Grogan, Dylan C. P.

    2013-08-15

    Executive Summary This Final Report for the "Development of Molten-Salt Heat Transfer Fluid (HTF) Technology for Parabolic Trough Solar Power Plants” describes the overall project accomplishments, results and conclusions. Phase 1 analyzed the feasibility, cost and performance of a parabolic trough solar power plant with a molten salt heat transfer fluid (HTF); researched and/or developed feasible component options, detailed cost estimates and workable operating procedures; and developed hourly performance models. As a result, a molten salt plant with 6 hours of storage was shown to reduce Thermal Energy Storage (TES) cost by 43.2%, solar field cost by 14.8%, and levelized cost of energy (LCOE) by 9.8% - 14.5% relative to a similar state-of-the-art baseline plant. The LCOE savings range met the project’s Go/No Go criteria of 10% LCOE reduction. Another primary focus of Phase 1 and 2 was risk mitigation. The large risk areas associated with a molten salt parabolic trough plant were addressed in both Phases, such as; HTF freeze prevention and recovery, collector components and piping connections, and complex component interactions. Phase 2 analyzed in more detail the technical and economic feasibility of a 140 MWe,gross molten-salt CSP plant with 6 hours of TES. Phase 2 accomplishments included developing technical solutions to the above mentioned risk areas, such as freeze protection/recovery, corrosion effects of applicable molten salts, collector design improvements for molten salt, and developing plant operating strategies for maximized plant performance and freeze risk mitigation. Phase 2 accomplishments also included developing and thoroughly analyzing a molten salt, Parabolic Trough power plant performance model, in order to achieve the project cost and performance targets. The plant performance model and an extensive basic Engineering, Procurement, and Construction (EPC) quote were used to calculate a real levelized cost of energy (LCOE) of 11.50

  17. On the plant operators performance during earthquake

    International Nuclear Information System (INIS)

    Kitada, Y.; Yoshimura, S.; Abe, M.; Niwa, H.; Yoneda, T.; Matsunaga, M.; Suzuki, T.

    1994-01-01

    There is little data on which to judge the performance of plant operators during and after strong earthquakes. In order to obtain such data to enhance the reliability on the plant operation, a Japanese utility and a power plant manufacturer carried out a vibration test using a shaking table. The purpose of the test was to investigate operator performance, i.e., the quickness and correctness in switch handling and panel meter read-out. The movement of chairs during earthquake as also of interest, because if the chairs moved significantly or turned over during a strong earthquake, some arresting mechanism would be required for the chair. Although there were differences between the simulated earthquake motions used and actual earthquakes mainly due to the specifications of the shaking table, the earthquake motions had almost no influence on the operators of their capability (performance) for operating the simulated console and the personal computers

  18. Hybrid Corporate Performance Prediction Model Considering Technical Capability

    Directory of Open Access Journals (Sweden)

    Joonhyuck Lee

    2016-07-01

    Full Text Available Many studies have tried to predict corporate performance and stock prices to enhance investment profitability using qualitative approaches such as the Delphi method. However, developments in data processing technology and machine-learning algorithms have resulted in efforts to develop quantitative prediction models in various managerial subject areas. We propose a quantitative corporate performance prediction model that applies the support vector regression (SVR algorithm to solve the problem of the overfitting of training data and can be applied to regression problems. The proposed model optimizes the SVR training parameters based on the training data, using the genetic algorithm to achieve sustainable predictability in changeable markets and managerial environments. Technology-intensive companies represent an increasing share of the total economy. The performance and stock prices of these companies are affected by their financial standing and their technological capabilities. Therefore, we apply both financial indicators and technical indicators to establish the proposed prediction model. Here, we use time series data, including financial, patent, and corporate performance information of 44 electronic and IT companies. Then, we predict the performance of these companies as an empirical verification of the prediction performance of the proposed model.

  19. Technical Note: Methionine, a precursor of methane in living plants

    Science.gov (United States)

    Lenhart, K.; Althoff, F.; Greule, M.; Keppler, F.

    2015-03-01

    When terrestrial plants were identified as producers of the greenhouse gas methane, much discussion and debate ensued not only about their contribution to the global methane budget but also with regard to the validity of the observation itself. Although the phenomenon has now become more accepted for both living and dead plants, the mechanism of methane formation in living plants remains to be elucidated and its precursor compounds to be identified. We made use of stable isotope techniques to verify the in vivo formation of methane, and, in order to identify the carbon precursor, 13C positionally labeled organic compounds were employed. Here we show that the amino acid L-methionine acts as a methane precursor in living plants. Employing 13C-labeled methionine clearly identified the sulfur-bound methyl group of methionine as a carbon precursor of methane released from lavender (Lavandula angustifolia). Furthermore, when lavender plants were stressed physically, methane release rates and the stable carbon isotope values of the emitted methane greatly increased. Our results provide additional support that plants possess a mechanism for methane production and suggest that methionine might play an important role in the formation of methane in living plants, particularly under stress conditions.

  20. Risk-based plant performance indicators

    International Nuclear Information System (INIS)

    Boccio, J.L.; Azarm, M.A.; Hall, R.E.

    1991-01-01

    Tasked by the 1979 President's Commission on the Accident at Three Mile Island, the U.S. nuclear power industry has put into place a performance indicator program as one means for showing a demonstrable record of achievement. Largely through the efforts of the Institute of Nuclear Power Operations (INPO), plant performance data has, since 1983, been collected and analyzed to aid utility management in measuring their plants' performance progress. The U.S. Nuclear Regulatory Commission (NRC) has also developed a set of performance indicators. This program, conducted by NRC's Office for the Analysis and Evaluation of Operational Data (AEOD), is structured to present information on plant operational performance in a manner that could enhance the staff's ability to recognize changes in the safety performance. Both organizations recognized that performance indicators have limitations and could be subject to misinterpretation and misuse with the potential for an adverse impact on safety. This paper reports on performance indicators presently in use, e.g., unplanned automatic scrams, unplanned safety system actuation, safety system failures, etc., which are logically related to safety. But, a reliability/risk-based method for evaluating either individual indicators or an aggregated set of indicators is not yet available

  1. Energy performance indicator report: fluid milk plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    In Canada, the dairy sector consumes significant amounts of energy and is looking for new ways of saving energy. The aim of this study, performed by the Competitive Analysis Centre Inc., was to find novel energy savings ideas for fluid milk plants. For this purpose, the energy consumption of 17 fluid milk plants, which accounts for over 50% of total Canadian output, was analyzed; first, at the plant level, and then by 8 categories at the sub-plant level in order to develop benchmarks that could be applied at both these levels. The paper provides background information on Canada's fluid milk sector and outlines the methodology used to develop and apply energy efficiency measures in the sector; the study findings are also presented. This report found that the energy consumption of the Canadian fluid milk sector could be lowered by applying the energy saving proposals developed herein.

  2. Technical data for concentrated solar power plants in operation, under construction and in project

    Directory of Open Access Journals (Sweden)

    Ugo Pelay

    2017-08-01

    Full Text Available This article presents technical data for concentrated solar power (CSP plants in operation, under construction and in project all over the world in the form of tables. These tables provide information about plants (e.g., name of the CSP plant, country of construction, owner of the plant, aim of the plant and their technical characteristics (e.g., CSP technology, solar power, area of the plant, presence and type of hybridization system, electricity cost, presence and type of TES, power cycle fluid, heat transfer fluid, operating temperature, operating pressure, type of turbine, type and duration of storage, etc.. Further interpretation of the data and discussions on the current state-of-the-art and future trends of CSP can be found in the associated research article (Pelay et al., 2017 [1].

  3. CSNI technical opinion papers no.10. The role of human and organisational factors in nuclear power plant modifications

    International Nuclear Information System (INIS)

    2009-01-01

    Nuclear power plant modifications may be needed for a number of different reasons. These include physical ageing of plant systems, structures and components; obsolescence in hardware and software; feedback from operating experience; and opportunities for improved plant safety, reliability or capability. However, experience has also shown that weaknesses in the design and/or implementation of modifications can present significant challenges to plant safety. They can also have a considerable impact on the commercial performance of the plant. It is therefore important that the plant modification process reflect a recognition of the potential impact of human errors and that it incorporate suitable measures to minimise the potential for such errors. In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Human and Organisational Factors organised an international workshop in 2003 to discuss the role of human and organisational performance in the nuclear plant modification process. This technical opinion paper represents the consensus of specialists in human and organisational factors (HOF) in the NEA member countries on commendable practices and approaches to dealing with nuclear plant modifications. It considers factors that should be taken into account when developing a modification process and identifies some lessons learnt from application of the process. The paper should be of particular interest of nuclear safety regulators and nuclear power plant operators. (author)

  4. A technical and financial analysis of two recuperated, reciprocating engine driven power plants. Part 2: Financial analysis

    International Nuclear Information System (INIS)

    Orbaiz, Pedro Jose; Brear, Michael J.

    2014-01-01

    Highlights: • The financial performance of two hybrid power plants is analyzed. • Biomass and solar thermal energy are used as the renewable energy inputs. • The LCOE of both power plants is estimated using reference data. • The proposed power plants are of comparable LCOE to natural gas combined cycle. • Hybrid cycles resulted in cost-effective renewable energy generation. - Abstract: This paper is the second of a two part study that analyses the technical and financial performance of particular, recuperated engine systems. This second paper examines the financial performance of two hybrid (renewable/fossil), chemically recuperated power plants. One of these plants uses the combustion of biomass as the renewable energy input. The other assumes that solar thermal energy is used. This financial analysis estimates the so-called Levelized Cost of Electricity (LCOE) of both hybrids using reference data from several sources. Using consistent financial inputs, the LCOE of both hybrid plants is found to be comparable to the LCOE of natural gas combined cycle (NGCC) power generation. Further, the LCOE of the renewable portion of the hybrid plants’ total power output is significantly cheaper than that of all the renewable plants examined in the EPRI report, and is competitive with the fossil plants. As a result, the proposed hybrids appear to be a cost-effective form of greenhouse gas mitigation

  5. Study on evaluation index system of operational performance of municipal wastewater treatment plants in China

    Science.gov (United States)

    Xiaoxin, Zhang; Jin, Huang; Ling, Lin; Yan, Li

    2018-05-01

    According to the undeveloped evaluation method for the operational performance of the municipal wastewater treatment plants, this paper analyzes the policies related to sewage treatment industry based on the investigation of the municipal wastewater treatment plants. The applicable evaluation method for the operational performance was proposed from environmental protection performance, resources and energy consumption, technical and economic performance, production management and main equipment, providing a reliable basis for scientific evaluation of the operation as well as improving the operational performance of municipal wastewater treatment plant.

  6. Technical comparison between Integrated Gasification Combined Cycle (IGCC) and Natural Gas Combined Cycle (NGCC) power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz, Pablo Andres Silva; Venturini, Osvaldo Jose; Lora, Electo Eduardo Silva [Federal University of Itajuba - UNIFEI, MG (Brazil). Excellence Group in Thermal Power and Distributed Generation - NEST], e-mails: osvaldo@unifei.edu.br, electo@unifei.edu.br

    2010-07-01

    Among the emerging clean coal technologies for power generation, Integrated Gasification Combined Cycle (IGCC) and Natural Gas Combined Cycle (NGCC) systems are receiving considerable attention as a potentially attractive option to reduce the emissions of greenhouse gases (GHG). The main reason is because these systems has high efficiency and low emissions in comparison with traditional power generation plants. Currently in IGCC and NGCC systems at demonstration stage is been considered to implement CCS technology. CO{sub 2} emissions can be avoided in a gasification-based power plant because by transferring almost all carbon compounds to CO{sub 2} through the water gas shift (WGS) reaction, then removing the CO{sub 2} before it is diluted in the combustion stage. The aim of this study is to compare the technical performance of an IGCC system that uses Brazilian coal and petroleum coke as fuel with a NGCC system, with the same fixed output power of 450 MW. The first section of this paper presents the plant configurations of IGCC systems. The following section presents an analysis of NGCC technology. (author)

  7. Performance of a Grid Connected Photovoltaic Plant

    Directory of Open Access Journals (Sweden)

    Cristian Paul Chioncel

    2009-01-01

    Full Text Available The paper presents an overwiev of the performances of the grid connectedphotovoltaik plant at the University ”Eftimie Murgu��� Resita, Romaniarealised on the monitoriesed wheather and installations datastored in a on-line data base during one year.

  8. Performance evaluations of a geothermal power plant

    International Nuclear Information System (INIS)

    Coskun, C.; Oktay, Z.; Dincer, I.

    2011-01-01

    Thermodynamic analysis of an operational 7.5 MWe binary geothermal power plant in Tuzla-Turkey is performed, through energy and exergy, using actual plant data to assess its energetic and exergetic performances. Eight performance-related parameters, namely total exergy destruction ratio, component exergy destruction ratio, dimensionless exergy destruction, energetic renewability ratio, exergetic renewability ratio, energetic reinjection ratio, exergetic reinjection ratio and improvement potential are investigated. Energy and exergy losses/destructions for the plant and its units are determined and illustrated using energy and exergy flow diagrams. The largest energy and exergy losses occur in brine reinjection unit. The variation of the plant energy efficiency is found between 6% and 12%. Exergy efficiency values change between 35 and 49%. The annual average energy and exergy efficiencies are found as 9.47% and 45.2%, respectively. - Highlights: → Investigation of a geothermal system energetically and exergetically. → Performance assessment of the system through energy and exergy efficiencies. → Utilization of temperature distribution in exergy calculations. → Evaluation of eight energetic and exergetic parameters for the system.

  9. Human performance improvement for nuclear power plants

    International Nuclear Information System (INIS)

    2005-01-01

    The IAEA assists NPP operating organizations to improve plant performance through a focus on human performance improvement in areas like organizational and leadership development, senior management decision making, organization and management of HPI programmes including tools needed for effective HPI implementation, safety culture enhancement, knowledge management, personnel selection and staffing, career development, training and development, work design, scheduling and conditions, procedure and other job-aid development and use, effective communications, human performance monitoring, motivation. Many NPP operating organizations in Member States, are not yet achieving the full potential of their NPP technology/equipment regarding safety, operational or economic performance due to human performance weaknesses. The IAEA's HPI (Human Performance Improvement) services provide a means for these organizations to efficiently and effectively learn from international experts and the experiences of others in improving plant performance through human performance improvements. NPP operating organizations can benefit from these services in a number of ways, including requesting a national project, participating in a regional project, or requesting an assist visit. The types of activities provided through these services include assistance in benchmarking practices of successful organizations, providing information exchange and reviews of current practices through assist missions, conducting workshops on focused human performance topics, evaluating current human performance methods, including assistance in implementing self assessment programmes and providing support to safety culture enhancement programmes based on self-assessment

  10. Waste Treatment Plant LAW Evaporation: Antifoam Performance

    International Nuclear Information System (INIS)

    BAICH, MARKA

    2004-01-01

    This report describes the work performed to determine the performance and fate of several commercial antifoams during evaporation of various simulants of Envelope A, B, and C mixed with simulated River Protection Project Waste Treatment Plant (RPP-WTP) recycle streams. Chemical and radiation stability of selected antifoams was also investigated.Contributors to this effort include: Illinois Institute of Technology (IIT), DOW Corning Analytical, and Savannah River Technology Center (SRTC)

  11. [Carbon isotope fractionation in plants]: Annual technical progress report

    International Nuclear Information System (INIS)

    O'Leary, M.H.

    1988-01-01

    Plants fractionate carbon isotopes during photosynthesis in ways which reflect photosynthetic pathway and environment. The fractionation is product of contributions from diffusion, carboxylation and other factors which can be understood using models which have been developed in our work. The object of our work is to use this fractionation to learn about the factors which control the efficiency of photosynthesis. Unlike previous studies, we do not rely principally on combustion methods, but instead develop more specific methods with substantially higher resolving power. We have recently developed a new short-term method for studying carbon isotope fractionation which promises to provide a level of detail about temperature, species, and light intensity effects on photosynthesis which has not been available until now. We are studying the isotopic compositions of metabolites (particularly aspartic acid) in C 3 plants in order to determine the role of phosphoenolpyruvate carboxylase in C 3 photosynthesis. We are studying the relative roles of diffusion and carboxylation in nocturnal CO 2 fixation in CAM plants. We are studying the use of isotopic content as an index of water-use efficiency in C 3 plants. We are developing new methods for studying carbon metabolism in plants. 3 refs

  12. Relationship between non-technical skills and technical performance during cardiopulmonary resuscitation: does stress have an influence?

    NARCIS (Netherlands)

    Krage, R.; Zwaan, L.; Tjon Soei Len, L.; Kolenbrander, M.; Groeningen, D. van; Loer, S.A.; Wagner, C.; Schober, P.

    2017-01-01

    Background: Non-technical skills, such as task management, leadership, situational awareness, communication and decision-making refer to cognitive, behavioural and social skills that contribute to safe and efficient team performance. The importance of these skills during cardiopulmonary

  13. Technical report on dc power supplies in nuclear power plants

    International Nuclear Information System (INIS)

    1977-06-01

    Emergency electrical power supplies, both a.c. and d.c. for nuclear power plants are important to safety. For this reason, the electric power systems for operating nuclear plants and those plants under licensing review have been required to provide a high degree of reliability. It is this high reliability that provides confidence that sufficient safety margin exists against loss of all d.c. power for extended periods of time to allow an orderly examination of safety issues, such as this. However, because of the importance of the a.c. and d.c. power systems, the staff has been expending effort to review the reliability of these systems and shall continue to do so in the future

  14. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Karino, Motonobu; Uryu, Mitsuru; Matsui, N.; Nakazawa, Fumio; Imanishi, Makoto; Koizumi; Kazuhiko; Sugawara, Junichi; Tanaka, Hideo

    1999-04-01

    The past specifications SGN of the welding in JNC was reexamined for the reprocessing plants in order to further promote the quality control. The specification first concerns the quality of raw materials, items of the quality tests, material management, and qualification standards of the welders. It extends over details of the welding techniques, welding design, welding testings, inspection and the judgment standards. (H. Baba)

  15. A Study on Establishment of Nuclear Power Plant Technical Support System and Activation Plan

    International Nuclear Information System (INIS)

    Wi, M. H.; Park, W. S.; Lee, H. S.; Kim, J. H.; Won, B. C.; Kim, Y. H.; Goo, D. S.; Choi, H. B.

    2009-11-01

    This report includes activities related to establishment of 'BaroBaro nuclear plant technical support center', 'selection of nuclear plant applicable technology', and 'various information interchange between KAERI and nuclear power plant'. 'BaraBaro center was newly organized to support on resolving the technical difficulties in operation of nuclear power plant'. The center consists of 10 technical parts and a leading expert is assigned to each part to support more efficiently. This center is always served for 24 hour. The plant operators can register their problem to the center by a call, e-mail, or internet and they can receive the answer about what they issued from KAERI experts. To make a brochure, we selected 32 technologies which are applicable in nuclear plant without additional R and D activity. The brochure was distributed to the officer in charge of nuclear plant operations. Various meetings were held to increase interchange of experience and technology between KAERI and nuclear power plant and we discussed many different issues at that meeting

  16. Performance management for nuclear power plant operators

    International Nuclear Information System (INIS)

    Fan Pengfei

    2014-01-01

    Fuel was loaded to Unit 3 of the second power plant in May 2010. The Second Operation Division stepped in the operation stage from production preparation and commissioning and exploration of performance management was started. By means of performance evaluation, a closed loop of performance management was formed, staff enthusiasm improved, and potential capability inspired through evaluation, analysis and improvement. The performance evaluation covers attitude, skill, efficiency, performance, teamwork sense, cooperation, etc. Quantitative appraisal was carried out through 31 objective indicators of the working process and results. According to the evaluation results and personal interviews, indicators were modified. Through the performance evaluation, positive guidance is provided to the employees to promote the development of employees, departments and the enterprise. (authors)

  17. Availability Performance Analysis of Thermal Power Plants

    Science.gov (United States)

    Bhangu, Navneet Singh; Singh, Rupinder; Pahuja, G. L.

    2018-03-01

    This case study presents the availability evaluation method of thermal power plants for conducting performance analysis in Indian environment. A generic availability model has been proposed for a maintained system (thermal plants) using reliability block diagrams and fault tree analysis. The availability indices have been evaluated under realistic working environment using inclusion exclusion principle. Four year failure database has been used to compute availability for different combinatory of plant capacity, that is, full working state, reduced capacity or failure state. Availability is found to be very less even at full rated capacity (440 MW) which is not acceptable especially in prevailing energy scenario. One of the probable reason for this may be the difference in the age/health of existing thermal power plants which requires special attention of each unit from case to case basis. The maintenance techniques being used are conventional (50 years old) and improper in context of the modern equipment, which further aggravate the problem of low availability. This study highlights procedure for finding critical plants/units/subsystems and helps in deciding preventive maintenance program.

  18. ENSI's technical view on the periodic safety review 2008 of the nuclear power plant Goesgen

    International Nuclear Information System (INIS)

    2012-08-01

    The owner of a license for a nuclear power plant operation in Switzerland has to undergo every 10 years a comprehensive safety check called 'periodic safety review' (PSR). The regulatory authority, the Swiss Federal Nuclear Safety Inspectorate (ENSI), reviews the documents supplied by the licensee. The Goesgen power plant (KKG) obtained its operation license and started operation in 1978. A first PSR was performed in the years 1996 to 1998 (PSR 1998) and reported. KKG delivered an analysis of the safety status, an evaluation of subsystems as well as test reports. The new PSR covers the period 1998 to 2007. The basis of the evaluation by ENSI is the new nuclear energy law in force since 1 February 2005. In comparison to PSR 1998, new aspects have to be considered like the description of the safety concept, including the technical safety classification of buildings, systems and components, or consideration of the protection objective 'limitation of the radiation exposure'. The PSR 2008 is focussed on the estimate of the nuclear safety of KKG. Basically, for the operation of a nuclear power plant, a sufficient protection has to be guaranteed against the release of radioactive materials to the environment as well as the irradiation of persons, during normal operation as well as in the case of accidents. The licensee of a nuclear power plant in operation must retrofit his plant according to the experience already gained and the state-of-the-art. The purpose of the PSR is to check the quality of the plant in the domain of safety. A probabilistic safety assessment (PSA) study must prove that the probability of damages to the reactor core is smaller than 10 -5 /year. In Switzerland the life time of a nuclear power plant is not limited by a fixed maximum time of operation. On the contrary, the limitation proceeds from safety criteria. Insufficiencies in the plant design are often recognized only through the evolution of the technique or some unexpected events. Ageing

  19. [Health & safety in a steel plant: technical and managerial action].

    Science.gov (United States)

    Fusato, M

    2012-01-01

    The report presents the experience in a steel company to improve the management of issues relating to health and safety of workers. The first part of the work focuses on the description of the interventions made by the company in recent years, which can be divided into technical interventions on production facilities, training and information, organizational activities and specific projects in collaboration with the health service. The second part presents the certification project according to OHSAS 18001, with particular focus on the efforts for a lean management of the documentation required by the management systems and for the automation of internal processes. The last part finally describes in detail the manner in which it was decided to address some issues that significantly affect the factory doctor: the recording and analysis of accidents and medications, management of hazardous substances and personal protective equipment.

  20. Technical considerations for flexible piping design in nuclear power plants

    International Nuclear Information System (INIS)

    Lu, S.C.; Chou, C.K.

    1985-01-01

    The overall objective of this research project is to develop a technical basis for flexible piping designs which will improve piping reliability and minimize the use of pipe supports, snubbers, and pipe whip restraints. The current study was conducted to establish the necessary groundwork based on the piping reliability analysis. A confirmatory piping reliability assessment indicated that removing rigid supports and snubbers tends to either improve or affect very little the piping reliability. A couple of changes to be implemented in Regulatory Guide (RG) 1.61 and RG 1.122 aimed at more flexible piping design were investigated. It was concluded that these changes substantially reduce calculated piping responses and allows piping redesigns with significant reduction in number of supports and snubbers without violating ASME code requirements

  1. An empirical analysis of nuclear power plant organization and its effect on safety performance

    International Nuclear Information System (INIS)

    Thurber, J.A.

    1985-01-01

    The paper documents work performed on three tasks. The first task concerned the creation of measures of organizational structure. An earlier review of the literature supported the position that organizational structure (e.g., the way the work of the organization is divided, administered, and coordinated) is a likely determinant of plant safety performance. While data were not available on some salient dimensions of organizational structure, Final Safety Analysis Reports (FSARs), Technical Specifications, and a survey of plant technical resources allowed for measurement on three primary dimensions. These are the vertical structure of the plant (e.g., the number of ranks and the ratio of supervisors to subordinates), the horizontal structure of the plant (e.g., the way the organization is divided into administrative and work units), and the coordinative structure of the plant (e.g., the ways that work units are linked)

  2. Standard technical specifications General Electric plants, BWR/6. Volume 1, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  3. Standard technical specifications: General Electric plants, BWR/4. Volume 1, Revision 1: Specifications

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  4. Standard technical specifications: Combustion engineering plants. Volume 1, Revision 1: Specifications

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  5. A technical system to improve the operational monitoring of the Zaporozh'ye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.

    1997-01-01

    As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)

  6. Development of standard technical report on using and selecting wireless device in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.

    2011-11-01

    1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

  7. Improving chemistry performance in CANDU plants

    International Nuclear Information System (INIS)

    Turner, C.; Guzonas, D.

    2010-01-01

    system to facilitate improved chemistry control and to help staff to proactively identify and address emerging issues before they result in a loss of performance. This paper will outline AECL's chemistry control philosophy, and provide specific examples to illustrate how changes to plant design, materials, operational procedures, and chemistry specifications are being implemented to support improved chemistry performance in existing and new-build CANDU® plants. (author)

  8. Nuclear Power Plant Performance: Ascending The Summit

    International Nuclear Information System (INIS)

    Anderson, T. M.

    1986-01-01

    When we look back over the years and consider the progress we have made in improving nuclear plant performance, I'm sure that many of you must feel the same mixture of elation and apprehension the mountain climber feels when he finally confronts his summit. In the curse of the last 10 years, many of US have watched availability averages rise from 50% to 60%, to 65% -- and recently, to 70%, 80% and beyond. Yet, as impressive an accomplishment as that is, there comes, I think, a growing realization that the steady increases we have achieved up to now may, in fact, have been the easy part of the journey, the trek from base camp -- and that within a very small handful of years, we may find ourselves pushing plant performance right to the limit, only to discover that it is pushing back

  9. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

    2004-07-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  10. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    International Nuclear Information System (INIS)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

    2004-01-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  11. Nuclear power plant performance. Status and trends

    International Nuclear Information System (INIS)

    Glorian, D.

    1995-01-01

    The performance of nuclear power plants can be assessed in several different fields: operating costs, safety, reliability of electricity generation, impact on the environment and personnel protection (industrial safety, radiation protection, etc.). Comparing national and international performance levels involves the use of performance indicators, together with a terminology, precise definitions and computerized data collection and processing facilities. The paper gives a brief review of the different actions undertaken during the last ten years to achieve international harmonization in the use of indicators. The main international indicators in use today by virtually all nuclear operators around the world are examined. Figures are given for each of these main indicators. In particularly, the levels of 'excellence' achieved throughout the world are discussed, together with the difficulties encountered in trying to match them or indeed maintain them. Future prospects regarding both the efforts made towards achieving international harmonization and the optimum use of this system of international performance indicators are examined, in order to achieve mutual enhancement through this approach to feedback of experience. Considering the overall performance indicators in use, it must be clearly recognized that, over the last ten years, the nuclear industry has made a tremendous effort to improve performance; the challenge for the future is to maintain a very high level of quality in the area of safety by keeping the operating costs (and investment costs for future plants) within a reasonable range

  12. Performance objectives and criteria for plant evaluations

    International Nuclear Information System (INIS)

    1983-04-01

    Maintenance organization and administration should ensure effective implementation and control of maintenance activities. The criteria are: A. The organizational structure is clearly defined. B. Staffing and resources are sufficient to accomplish assigned tasks. C. Responsibilities and authority of each management, supervisory, and professional position are clearly defined. D. Personnel clearly understand their authority, responsibilities, accountabilities, and interfaces with supporting groups. E. Administrative controls are employed for maintenance activities important to plant safety and reliability. F. Performance appraisals are effectively utilized to enhance individual performance

  13. Remote repair and inspection technics in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

    1986-01-01

    Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

  14. The utilization of performance evaluation instruments by technical trainers to evaluate maintenance personnel in the nuclear power industry in the United States

    International Nuclear Information System (INIS)

    Hornberger, C.K.

    1993-01-01

    The purpose of this study was to document the utilization of performance evaluation instruments by technical trainers in the evaluation of maintenance personnel in US nuclear power plants. Performance evaluation of maintenance personnel has been identified by nuclear utilities and the Nuclear Regulatory Commission as the only acceptable method of determining worker competence. The NRC requires performance evaluation to be conducted to performance standards, but it does not specify the standards or the method to be utilized. Each plant is free to establish its own standards and methods of evaluation. This was a descriptive study utilizing descriptive statistics for the analysis of the data. The subjects included 655 maintenance trainers in 72 US nuclear plants. Conclusions of the study include: (1) Technical trainers are in compliance with NRC regulations. (2) Evaluation materials developed by the Institute of Nuclear Power Operations are used by technical trainers in every one of the 62 plants that responded. (3) In-plant or self-developed Performance Evaluation Instruments are utilized by 419 or 95.2% of the technical trainers. (4) Technical trainers incorporate nine common components into their Performance Evaluation Instruments. (5) Technical trainers evaluate maintenance processes and the product produced by workers when following procedures and specifications are critical and when safety hazards are involved. (6) Technical trainers believe that utilizing Performance Evaluation Instruments makes their job easier by providing documentation about the quality and standards of maintenance skills. (7) Technical trainers believe that maintenance workers benefit when their skills are assessed through the use of Performance Evaluation Instruments

  15. On the technical superiority of domestic power plant equipment and its development

    International Nuclear Information System (INIS)

    Zhao Zhiyi

    1993-01-01

    Under the Presumption of affirmed superiority of domestic power plant equipment, some existing deficiencies are pointed out. The scientific and technical development of domestic power equipment can be impelled through catching up with advanced technologies. The necessity of optimal matching of plant equipment from the engineering point of view is emphasized by the authors in association with a prospective outlook of key power equipment and development suggestions

  16. Technical aspects of coupling a 6300 m3/day MSF-RO desalination plant to a PHWR nuclear power plant

    International Nuclear Information System (INIS)

    Verma, R.K.

    1998-01-01

    Presently, eight pressurised Heavy Water Reactors (PHWRs) each of 235 MWe capacity are operational in India. Four more units of similar capacity are expected to be commissioned soon. Work on two units each of 500 MWe capacity is also initiated. Extensive engineering development work has also been carried out in India, both on the MSF process and the membrane process. Based on the experience obtained from the presently operating 425 m 3 /d MSF plant and from the R and D work on the RO process, a 6300 m 3 /d MSF-RO plant (4500 m 3 /d MSF and 1800 m 3 /d RO) has been designed and the work for setting up this plant is undertaken. The steam for the heating duty in the brine heater as well as the steam for the evacuation purpose for the MSF plant is proposed to be obtained from the nuclear plant steam cycle. Sea water feed for the MSF plant as well as for the RO plant will be derived from the sea water discharge system of the nuclear power plant. Provision is made for supply of electrical power also from the power plant. The details of the heating steam supply circuit starting from the steam tapping point on the nuclear plant side to the MSF plant brine heater inlet and the arrangement for the return of condensate to the nuclear plant has been described with component requirement and various technical considerations. All the liquid streams and the steam supplied from the nuclear plant to the desalination plant as well as the product water will be monitored to ensure that there is no radioactive contamination. (author)

  17. Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

    Energy Technology Data Exchange (ETDEWEB)

    Field, H C

    1988-03-01

    Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted.

  18. Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

    International Nuclear Information System (INIS)

    Field, H.C.

    1988-03-01

    Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted

  19. ``Recycling'' Nuclear Power Plant Waste: Technical Difficulties and Proliferation Concerns

    Science.gov (United States)

    Lyman, Edwin

    2007-04-01

    One of the most vexing problems associated with nuclear energy is the inability to find a technically and politically viable solution for the disposal of long-lived radioactive waste. The U.S. plan to develop a geologic repository for spent nuclear fuel at Yucca Mountain in Nevada is in jeopardy, as a result of managerial incompetence, political opposition and regulatory standards that may be impossible to meet. As a result, there is growing interest in technologies that are claimed to have the potential to drastically reduce the amount of waste that would require geologic burial and the length of time that the waste would require containment. A scenario for such a vision was presented in the December 2005 Scientific American. While details differ, these technologies share a common approach: they require chemical processing of spent fuel to extract plutonium and other long-lived actinide elements, which would then be ``recycled'' into fresh fuel for advanced reactors and ``transmuted'' into shorter-lived fission products. Such a scheme is the basis for the ``Global Nuclear Energy Partnership,'' a major program unveiled by the Department of Energy (DOE) in early 2006. This concept is not new, but has been studied for decades. Major obstacles include fundamental safety issues, engineering feasibility and cost. Perhaps the most important consideration in the post-9/11 era is that these technologies involve the separation of plutonium and other nuclear weapon-usable materials from highly radioactive fission products, providing opportunities for terrorists seeking to obtain nuclear weapons. While DOE claims that it will only utilize processes that do not produce ``separated plutonium,'' it has offered no evidence that such technologies would effectively deter theft. It is doubtful that DOE's scheme can be implemented without an unacceptable increase in the risk of nuclear terrorism.

  20. Performance analysis of photovoltaic plants installed in dairy cattle farms

    Directory of Open Access Journals (Sweden)

    Remo Alessio Malagnino

    2015-06-01

    Full Text Available Electric production from renewable resources, such as solar photovoltaic (PV, is playing an increasingly essential role in the agricultural industry because of the progressive increase in the energy price from fossil fuels and the simultaneous decrease in the income deriving from farming activities. A central issue in the sustainable diffusion of PV technologies is represented by the actual energy efficiency of a PV system. For these reasons, a performance analysis has been carried out in order to assess the potentials offered by different PV plants within a defined geographical context with the aim of investigating the impact of each component has on the PV generator global efficiency and defining the main technical parameters that allow to maximise the annual specific electric energy yield of an architectonically integrated plant, installed in a dairy house, compared to a ground-mounted plant. The annual performances of three grid connected PV plants installed in the same dairy cattle farm have been analysed: two are architectonically integrated plants - i.e., a rooftop unidirectional and a multi-field systems (both 99 kWp - and the other is a ground-mounted plant (480 kWp. Furthermore, the electrical performances, estimated by the photovoltaic geographical information system (PVGIS, developed by the EU Joint Research Centre, and by an analytical estimation procedure (AEP, developed on the basis of a meteo-climatic database related to the records of the nearest weather station and integrated by the components’ technical specifications, have been compared with the actual yields. The best annual performance has been given by the ground-mounted PV system, with an actual increase of 26% and in the range of 6÷12% according to different estimations, compared to the integrated systems, which were globally less efficient (average total loss of 26÷27% compared to 24% of the ground-mounted system. The AEP and PVGIS software estimates showed a good

  1. Containment Emergency Sump Performance. Technical findings related to Unresolved Safety Issue A-43. Revision 1

    International Nuclear Information System (INIS)

    1985-10-01

    This report summarizes key technical findings related to Unresolved Safety Issue (USI) A-43, Containment Emergency Sump Performance. Both BWRs and PWRs are considered in this report. Emergency core cooling systems require a clean, reliable water source to maintain long-term recirculation following a loss-of-coolant accident (LOCA). PWRs rely on the containment emergency sump to provide such a water supply to residual heat removal pumps and containment spray pumps. BWRs rely on pump suction intakes in the suppression pool or wet well to provide water to residual heat removal and core spray systems. Thus, the technical findings in this report provide information on post-LOCA recirculation. These findings have been derived from extensive experimental studies, generic plant studies, and assessments of sumps used for long-term cooling. Results of hydraulic tests have shown that the potential for air ingestion is less severe than previously hypothesized. The effects of debris blockage on NPSH margin must be dealt with on a plant-specific basis. These findings have been used to develop revisions to Regulatory Guide 1.82 and Standard Review Plan Section 6.2.2 (NUREG-0800)

  2. Standard technical specifications, Westinghouse Plants: Bases (Sections 3.4--3.9). Volume 3, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

  3. Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

  4. Risk-based analysis methods applied to nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

    1989-01-01

    A computer-aided methodology and practical applications of risk-based evaluation of technical specifications are described. The methodology, developed for use by the utility industry, is a part of the overall process of improving nuclear power plant technical specifications. The SOCRATES computer program uses the results of a probabilistic risk assessment or a system-level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at the plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns and decreasing labor requirements for test and maintenance activities, with no adverse impacts on risk. The methodology and the SOCRATES computer program have been used extensively toe valuate several actual technical specifications in case studies demonstrating the methods. Summaries of these applications demonstrate the types of results achieved and the usefulness of the risk-based evaluation in improving the technical specifications

  5. technical guidelines for the design and construction of the next generation of nuclear power plants with pressurized water reactors

    International Nuclear Information System (INIS)

    2009-01-01

    These technical guidelines present the opinion of the French 'Groupe Permanent charge des Reacteurs nucleaires' (GPR) concerning the safety philosophy and approach as well as the general safety requirements to be applied for the design and construction of the next generation of nuclear power plants of the PWR (pressurized water reactor) type, assuming the construction of the first units of this generation would start at the beginning of the 21. century. These technical guidelines are based on common work of the French Institut de Protection et de Surete Nucleaire (IPSN) and of the German Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). Moreover, these technical guidelines were extensively discussed with members of the German Reaktor Sicherheitskommission (RSK) until the end of 1998 and further with German experts. The context of these technical guidelines must be clearly understood. Faced with the current situation of nuclear energy in the world, the various nuclear steam supply system designers are developing new products, all of them claiming their intention of obtaining a higher safety level, by various ways. GPR believes that, for the operation of a new series of nuclear power plants at the beginning of the next century, the adequate way is to derive the design of these plants in an 'evolutionary' way from the design of existing plants, taking into account the operating experience and the in-depth studies conducted for such plants. Nevertheless, introduction of innovative features must also be considered in the frame of the design of the new generation of plants, especially in preventing and mitigating severe accidents. GPR underlines here that a significant improvement of the safety of the next generation of nuclear power plants at the design stage is necessary, compared to existing plants. If the search for improvement is a permanent concern in the field of safety, the necessity of a significant step at the design stage clearly derives from better

  6. Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.

    1979-12-01

    The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

  7. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    2017-01-01

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

  8. Technical and institutional safety features of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1986-01-01

    This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.)

  9. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire range of software life-cycle activities; the assessment of the technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary, includes an overview of the framework and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; Volume 2 is the main report

  10. Technical and regulatory challenges for digital instrumentation and control and control room systems in nuclear plants

    International Nuclear Information System (INIS)

    Torok, R.; Naser, J.; Harris, T.; Keithline, K.

    2006-01-01

    There are several unsettled technical and licensing issues in the areas of instrumentation and control (I and C), human factors, and updated control room designs that need coordinated, proactive industry attention. Some of these issues are already causing protracted regulatory reviews for existing plants, and left untreated, may cause substantial delays and increased costs for new plant combined construction and operating license approvals. Both industry and the NRC will have roles in resolving the key issues and addressing them in future design efforts and regulatory reviews. Where action is needed, the industry will want to minimize costs and risks by defining industry consensus solutions with corresponding technical bases. NEI has formed a working group to coordinate industry efforts and communications with NRC staff. The working group will also help determine priorities and coordinate both new and existing plant resources. EPRI will provide technical input and guidance for the working group. In order to be able to conduct reviews in a timely fashion, the NRC will likely need to enhance and expand staff resources as existing plants are upgraded and new plant reviews become more active. The industry initiative began with a workshop sponsored by EPRI and NEI on March 28-29, 2006, which led to the creation of the NEI working group. The working group has now identified and prioritized important generic issues, established resolution paths and schedules, and identified the roles of various stakeholders including utility companies, EPRI, NEI, vendors and the NRC. Through the course of this initiative I and C issues for both existing and new plants are being addressed. This paper describes the key I and C related technical and regulatory issues and their implications for new and operating plants, and provides a status report on the efforts to resolve them. (authors)

  11. Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors

    Directory of Open Access Journals (Sweden)

    Sylva Brabencová

    2017-12-01

    Full Text Available Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0 and Wassilewskija (Ws homogenized by two techniques (grinding in a cryomill or with a mortar and pestle. We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants. Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

  12. Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors.

    Science.gov (United States)

    Brabencová, Sylva; Ihnatová, Ivana; Potěšil, David; Fojtová, Miloslava; Fajkus, Jiří; Zdráhal, Zbyněk; Lochmanová, Gabriela

    2017-01-01

    Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation) among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0) and Wassilewskija (Ws) homogenized by two techniques (grinding in a cryomill or with a mortar and pestle). We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants). Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

  13. Investigative study on the technical code requirements of natural events hazards for nuclear power plants

    International Nuclear Information System (INIS)

    Ito, Kunio; Aoki, Takayuki

    2012-01-01

    Technical codes and standards on natural phenomena, in particular, earthquake and tsunami for nuclear power plants in the other developed countries including IAEA safety standards were investigated. Then, the results were compared with the corresponding Japanese technical codes and standards. As a results, it was found that: (1) technical codes and standards on natural phenomena, especially those for earthquakes and tsunami/flooding in those foreign countries and their requirements are all included in the Japanese technical codes and standards. (2) Nevertheless, the actual measures against tsunami/flooding in those foreign countries are more advanced than those in Japan which had been taken before Fukushima accident. Therefore, further investigation is needed to clarify the reason why there are such differences by investigating the details of the basic ideas and evaluation methods for the protection of tsunami/flooding. (author)

  14. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods - mothballing, entombing, or dismantling, or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which requires surveillance and maintenance for a significant period to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for an 1100-MW(e) light-water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as US $200,000. Although some tooling development will be needed for removing highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g. the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund, or annual depreciation type operating allowance, will have little effect on construction or on operating costs. (author)

  15. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods, namely, mothballing, entombing, or dismantling or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which require surveillance and maintenance for a significant period of time to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for a 1100 MW(e) light water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as $200,000. Although some tooling development will be needed for the removal of the highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g., the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund or annual depreciation type operating allowance will have little impact on either construction or operating costs

  16. Environmental Impact Report from Santa Rita Hydroelectric Power Plant (Minas Gerais State - Brazil): technical strategic for its elaboration

    International Nuclear Information System (INIS)

    Souza, J.A. de; Marques Neto, F.P.

    1989-01-01

    The steps for developing the technical strategies used on the elaboration of Environmental Impact Report from Santa Rita Hydroelectric Power Plant, Minas Gerais State, are described, including the influence area, technical requirements, impact identification, technical selection of mitigative measures, impact meaning and strategy for evaluating the identified impacts. (C.G.C.)

  17. River Protection Project waste feed delivery program technical performance measurement assessment plan

    International Nuclear Information System (INIS)

    O'TOOLE, S.M.

    1999-01-01

    This plan establishes a formal technical performance-monitoring program. Technical performance is assessed by establishing requirements based performance goals at the beginning of a program and routinely evaluating progress in meeting these goals at predetermined milestones throughout the project life cycle

  18. Plant corrosion: prediction of materials performance

    International Nuclear Information System (INIS)

    Strutt, J.E.; Nicholls, J.R.

    1987-01-01

    Seventeen papers have been compiled forming a book on computer-based approaches to corrosion prediction in a wide range of industrial sectors, including the chemical, petrochemical and power generation industries. Two papers have been selected and indexed separately. The first describes a system operating within BNFL's Reprocessing Division to predict materials performance in corrosive conditions to aid future plant design. The second describes the truncation of the distribution function of pit depths during high temperature oxidation of a 20Cr austenitic steel in the fuel cladding in AGR systems. (U.K.)

  19. Approaches to the safety of future nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-09-01

    The Technical Committee Meeting on Approaches to Safety of Future Nuclear Power Plants in Different Countries, held from 29 May to 2 June 1995, contributed to this process. Experts from 14 different countries and two international organizations participated in the meeting, which provided the opportunity to exchange information and to review the answers developed to date to these issues (primarily form the IAEA's technical document ''Development of Safety Principles for the Design of Future Nuclear Power Plants'' IAEA-TECDOC-801) and the report of the International Nuclear Safety Advisory Group ''Basic Safety Principles for Nuclear Power Plants'' (INSAG-3). These references were then used as a starting point for answering the question ''to what degree does general agreement (or harmonization) exist on these desired safety approaches for future reactors, and what opportunities remain for further harmonization? 11 refs, 1 tab

  20. Cycle water chemistry based on film forming amines at power plants: evaluation of technical guidance documents

    Science.gov (United States)

    Dyachenko, F. V.; Petrova, T. I.

    2017-11-01

    Efficiency and reliability of the equipment in fossil power plants as well as in combined cycle power plants depend on the corrosion processes and deposit formation in steam/water circuit. In order to decrease these processes different water chemistries are used. Today the great attention is being attracted to the application of film forming amines and film forming amine products. The International Association for the Properties of Water and Steam (IAPWS) consolidated the information from all over the World, and based on the research studies and operating experience of researchers and engineers from 21 countries, developed and authorized the Technical Guidance Document: “Application of Film Forming Amines in Fossil, Combined Cycle, and Biomass Power Plants” in 2016. This article describe Russian and International technical guidance documents for the cycle water chemistries based on film forming amines at fossil and combined cycle power plants.

  1. Analysis and evaluation of the ASTEC model basis on plant simulations. 2. Technical report

    International Nuclear Information System (INIS)

    Koppers, Vera; Braehler, Thimo; Koch, Marco K.

    2015-06-01

    The present report is the 2 nd Technical Report of the research project ''Analysis and Evaluation of the ASTEC model basis'' funded by the Federal Ministry for Economic Affairs and Energy (BMWi 1501433) and conducted at the Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics (LEE) at Ruhr-Universitaet Bochum. Within this report, the quality of a nuclear power plant simulation with ASTEC is investigated. Different parameters are varied to analyze the simulation stability within the dataset, which describes a generic German Konvoi power plant and is deposit in the program set of ASTEC. Firstly, plant specifications in the data set are checked for plausibility. In addition, the compliance of the data set with the nodalization rules is verified. After that, the stationary phase, in which no accident is calculated, is analyzed and parametric studies are performed in the transient phase, focusing on the primary and secondary circuit as well as on the containment behavior. The performed calculations focusing the primary and secondary circuit indicate a high dependency of the simulation results on the user's input in the data set. There are significant deviations between each simulations results, for example in the different calculated point of time of the reactor pressure vessel failure. Already changes in the stationary phase cause a significantly earlier reactor pressure vessel failure compared to the simulation with the original data. Beyond that, the location of the leakage of the reactor pressure vessel lower head varied and therefore cannot be clearly determined, although there have been no changes by the user on the accident course. A reliable indication of the plant behavior under severe accident conditions is therefore difficult using ASTEC. The results of the parametric studies within the Containment show the same significant influence of certain parameter changes on the simulation results. By using the

  2. Performance of Generating Plant: Managing the Changes. Executive Summary and Table of Contents

    Energy Technology Data Exchange (ETDEWEB)

    Curley, G. Michael [North American Electric Reliability Corporation (United States); Mandula, Jiri [International Atomic Energy Agency (IAEA)

    2008-05-15

    The WEC Committee on the Performance of Generating Plant (PGP) has been collecting and analysing power plant performance statistics worldwide for more than 30 years and has produced regular reports, which include examples of advanced techniques and methods for improving power plant performance through benchmarking. A series of reports from the various working groups was issued in 2008. This document serves as a supporting paper. Sections include: features of Italian energy and electricity; the evolution of liberalisation; support mechanism for renewables; connection to wind farm transmission network; wind source integration into power system; and, final comments. The WEC Committee on the Performance of Generating Plant (PGP) has been collecting and analysing power plant performance statistics worldwide for more than 30 years and has produced regular reports, which include examples of advanced techniques and methods for improving power plant performance through benchmarking. A series of reports from the various working groups was issued in 2008. This reference presents the results of Working Group 1 (WG1). WG1's primary focus is to analyse the best ways to measure, evaluate, and apply power plant performance and availability data to promote plant performance improvements worldwide. The paper explores the specific work activities of 2004-2007 to extend traditional analysis and benchmarking frameworks. It is divided into two major topics: Overview of current electric supply industry issues/trends; and, Technical Methods/Tools to evaluate performance in today's ESI.

  3. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, J.; Suezono, N.; Higuchi, T. [Toshiba Corp., Isogo Nuclear Engineering Center, Isogo-ku, Yokohama (Japan); Katayama, H. [Toshiba Corp., Power and Industrial Systems Research and Development Center, Isogo-ku, Yokohama (Japan)

    2014-07-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

  4. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    International Nuclear Information System (INIS)

    Nakajima, J.; Suezono, N.; Higuchi, T.; Katayama, H.

    2014-01-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

  5. Risk based optimization of technical specifications for operation of nuclear power plants

    International Nuclear Information System (INIS)

    1993-12-01

    The objective of the report is to present an overview of the risk and reliability based approaches (using a probabilistic safety assessment (PSA)) for improving nuclear power plant technical specifications (TS). In that case, it will provide an information base to the Member States in seeking PSA based applications to enhance the effectiveness of their technical specifications. To achieve this objective, the report discusses the basic objectives and reasons for seeking TS changes, the methods, data requirements and uses of different types of applications, and an overview of different applications that have been completed, including detailed descriptions of selected applications. Refs, figs and tabs

  6. Technical requirements on knowledge base and instrumentation system for decision making in plant operation and maintenance

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

    1998-03-01

    A series of technical surveys and studies are described in this report to examine and identify technical requirements to be posed on knowledge base and instrumentation system as the fundamental in high reliability computational decision making in operation and maintenance of nuclear power plants. Monitoring and diagnosis are focused as the important tasks among the operation/maintenance-related tasks. A concrete monitoring and diagnosis system configuration has been proposed consisting of distributed symptom database and of on-demand measurement subsystem. An prototype of the proposed system configuration has been successfully verified. (author)

  7. Nuclear power plant diagnostics - Safety aspects and licensing. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1997-01-01

    The aim of the Technical Committee Meeting (TCM) was to review developed systems and methods in diagnostics in the scope of their impacts and importance to the safety of Nuclear Power Plants. Papers presented on TCM came from different sources, from developers, from manufacturers, from licensing authorities and from NPP personal. They reflect up to date status in the given subject. Participants of TCM formulated three working groups to elaborate different questions which were raised during the discussions. Their results are reflected in the three chapter titles of the given material. Annex 1 to this document contains presentations made at the Technical Committee Meeting. Refs, figs, tabs

  8. Relationship between non-technical skills and technical performance during cardiopulmonary resuscitation: Does stress have an influence?

    NARCIS (Netherlands)

    Krage, R. (Ralf); L. Zwaan (Laura); Tjon Soei Len, L. (Lian); Kolenbrander, M.W. (Mark W); Van Groeningen, D. (DIck); S.A. Loer (Stephan A.); C. Wagner (Cordula); P. Schober (P.)

    2017-01-01

    textabstractBackground Non-technical skills, such as task management, leadership, situational awareness, communication and decision-making refer to cognitive, behavioural and social skills that contribute to safe and efficient team performance. The importance of these skills during cardiopulmonary

  9. Variation in plant defense suppresses herbivore performance

    Science.gov (United States)

    Pearse, Ian; Paul, Ryan; Ode, Paul J.

    2018-01-01

    Defensive variability of crops and natural systems can alter herbivore communities and reduce herbivory. However, it is still unknown how defense variability translates into herbivore suppression. Nonlinear averaging and constraints in physiological tracking (also more generally called time-dependent effects) are the two mechanisms by which defense variability might impact herbivores. We conducted a set of experiments manipulating the mean and variability of a plant defense, showing that defense variability does suppress herbivore performance and that it does so through physiological tracking effects that cannot be explained by nonlinear averaging. While nonlinear averaging predicted higher or the same herbivore performance on a variable defense than on an invariable defense, we show that variability actually decreased herbivore performance and population growth rate. Defense variability reduces herbivore performance in a way that is more than the average of its parts. This is consistent with constraints in physiological matching of detoxification systems for herbivores experiencing variable toxin levels in their diet and represents a more generalizable way of understanding the impacts of variability on herbivory. Increasing defense variability in croplands at a scale encountered by individual herbivores can suppress herbivory, even if that is not anticipated by nonlinear averaging.

  10. Analysis of technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla'

    OpenAIRE

    Grbić, Maja; Antić, Radoslav; Ponoćko, Jelena; Mikulović, Jovan; Đurišić, Željko

    2014-01-01

    This paper presents an analysis of the technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla' in Belgrade. Calculation of solar irradiation is performed and the conceptual design of the disposition of solar panels on the roof of the building is shown as well as their connections to the inverters. Conditions for connecting the plant to the distribution network are checked and an eco...

  11. The atmospheric corrosion: an important technical-economic and nuclear safety factor during storage in the construction of nuclear power plants

    International Nuclear Information System (INIS)

    Rodriguez, R.; Rodriguez, J.; Diaz, J.; Gomez, J.; Galeano, N.

    1993-01-01

    The purpose of this work is to show the results of the research performed to determine the atmospheric corrosion in the region of Juragua nuclear power plant and to offer some practical recommendations to increase the efficiency during the storage of materials, considering technical-economic and nuclear safety aspects

  12. Technical Feasibility Study of Thermal Energy Storage Integration into the Conventional Power Plant Cycle

    Directory of Open Access Journals (Sweden)

    Jacek D. Wojcik

    2017-02-01

    Full Text Available The current load balance in the grid is managed mainly through peaking fossil-fuelled power plants that respond passively to the load changes. Intermittency, which comes from renewable energy sources, imposes additional requirements for even more flexible and faster responses from conventional power plants. A major challenge is to keep conventional generation running closest to the design condition with higher load factors and to avoid switching off periods if possible. Thermal energy storage (TES integration into the power plant process cycle is considered as a possible solution for this issue. In this article, a technical feasibility study of TES integration into a 375-MW subcritical oil-fired conventional power plant is presented. Retrofitting is considered in order to avoid major changes in the power plant process cycle. The concept is tested based on the complete power plant model implemented in the ProTRAX software environment. Steam and water parameters are assessed for different TES integration scenarios as a function of the plant load level. The best candidate points for heat extraction in the TES charging and discharging processes are evaluated. The results demonstrate that the integration of TES with power plant cycle is feasible and provide a provisional guidance for the design of the TES system that will result in the minimal influence on the power plant cycle.

  13. 16 CFR 1401.5 - Providing performance and technical data to purchasers by labeling.

    Science.gov (United States)

    2010-01-01

    ... POINT OF PURCHASE OF PERFORMANCE AND TECHNICAL DATA § 1401.5 Providing performance and technical data to... the time of original purchase and to the first purchaser for purposes other than resale. The data... to be read and understood by ordinary individuals under normal conditions of purchase. This...

  14. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

    1997-01-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

  15. Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1984-01-01

    The panel has evaluated the scientific and technical adequacy of work being done on the Waste Isolation Pilot Plant (WIPP) project to satisfy the charge to the panel set out in Chapter 1. The panel concluded that the scientific work has been carried out with a high degree of professional competence. The panel notes that the geology revealed by shaft sinking and excavation of drifts and the preliminary measurements generally confirm the geologic expectations derived from surface explorations and boreholes. The purity and volume of the salt, the absence of brine pockets at the repository horizon in the areas excavated, the absence of breccia pipes and of toxic gases, and the nearly horizontal bedding of the salt indicate that a repository can be constructed that will meet the geologic criteria for site selection. Thus, the important issues about the geology at the site have been resolved, but there remain some issues about the hydrology and design of the facility that should be resolved before large-scale transuranic (TRU) waste emplacement begins. The panel's conclusions and recommendations regarding the following studies are presented: site selection and characterization; in-situ tests and experiments; waste acceptance criteria; design and construction of underground facilities; and performance assessment. 65 references, 17 figures, 3 tables

  16. An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon

    2013-01-01

    Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system

  17. An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

  18. Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Bradley, E.W.; Wu, C.F.; Goff, T.E.

    1993-01-01

    The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

  19. Team performance measures for abnormal plant operations

    International Nuclear Information System (INIS)

    Montgomery, J.C.; Seaver, D.A.; Holmes, C.W.; Gaddy, C.D.; Toquam, J.L.

    1990-01-01

    In order to work effectively, control room crews need to possess well-developed team skills. Extensive research supports the notion that improved quality and effectiveness are possible when a group works together, rather than as individuals. The Nuclear Regulatory Commission (NRC) has recognized the role of team performance in plant safety and has attempted to evaluate licensee performance as part of audits, inspections, and reviews. However, reliable and valid criteria for team performance have not yet been adequately developed. The purpose of the present research was to develop such reliable and valid measures of team skills. Seven dimensions of team skill performance were developed on the basis of input from NRC operator licensing examiners and from the results of previous research and experience in the area. These dimensions included two-way communications, resource management, inquiry, advocacy, conflict resolution/decision-making, stress management, and team spirit. Several different types of rating formats were developed for use with these dimensions, including a modified Behaviorally Anchored Rating Scale (BARS) format and a Behavioral Frequency format. Following pilot-testing and revision, observer and control room crew ratings of team performance were obtained using 14 control room crews responding to simulator scenarios at a BWR and a PWR reactor. It is concluded, overall, that the Behavioral Frequency ratings appeared quite promising as a measure of team skills but that additional statistical analyses and other follow-up research are needed to refine several of the team skills dimensions and to make the scales fully functional in an applied setting

  20. Standard technical specifications combustion engineering plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes

  1. The use of a checklist improves anaesthesiologists' technical and non-technical performance for simulated malignant hyperthermia management.

    Science.gov (United States)

    Hardy, Jean-Baptiste; Gouin, Antoine; Damm, Cédric; Compère, Vincent; Veber, Benoît; Dureuil, Bertrand

    2018-02-01

    Anaesthesiologists may occasionally manage life-threatening operating room (OR) emergencies. Managing OR emergencies implies real-time analysis of often complicated situations, prompt medical knowledge retrieval, coordinated teamwork and effective decision making in stressful settings. Checklists are recommended to improve performance and reduce the risk of medical errors. This study aimed to assess the usefulness of the French Society of Anaesthesia and Intensive Care's (SFAR) "Malignant Hyperthermia" (MH) checklist on a simulated episode of MH crisis and management thereof by registered anesthesiologists. Twenty-four anaesthesiologists were allocated to 2 groups (checklist and control). Their technical performance in adherence with the SFAR guidelines was assessed by a 30-point score and their non-technical performance was assessed by the Anaesthetists' Non-Technical Skills (ANTS) score. Every task completion was assessed independently. Data are shown as median (first-third quartiles). Anaesthesiologists in the checklist group had higher technical performance scores (24/30 (21.5-25) vs 18/30 (15.5-19.5), P=0.002) and ANTS scores (56.5/60 (47.5-58) vs 48.5/60 (41-50.5), P=0.024). They administered the complete initial dose of dantrolene (2mg/kg) more quickly (15.7 minutes [13.9-18.3] vs 22.4 minutes [18.6-25]) than the control group (P=0.017). However, anaesthesiologists deemed the usability of the checklist to be perfectible. Registered anaesthesiologists' use of the MH checklist during a simulation session widely improved their adherence to guidelines and non-technical skills. This study strongly suggests the benefit of checklist tools for emergency management. Notwithstanding, better awareness and training for anaesthesiologists could further improve the use of this tool. Copyright © 2017 Société française d'anesthésie et de réanimation (Sfar). Published by Elsevier Masson SAS. All rights reserved.

  2. Human System Simulation in Support of Human Performance Technical Basis at NPPs

    Energy Technology Data Exchange (ETDEWEB)

    David Gertman; Katya Le Blanc; alan mecham; william phoenix; Magdy Tawfik; Jeffrey Joe

    2010-06-01

    This paper focuses on strategies and progress toward establishing the Idaho National Laboratory’s (INL’s) Human Systems Simulator Laboratory at the Center for Advanced Energy Studies (CAES), a consortium of Idaho State Universities. The INL is one of the National Laboratories of the US Department of Energy. One of the first planned applications for the Human Systems Simulator Laboratory is implementation of a dynamic nuclear power plant simulation (NPP) where studies of operator workload, situation awareness, performance and preference will be carried out in simulated control rooms including nuclear power plant control rooms. Simulation offers a means by which to review operational concepts, improve design practices and provide a technical basis for licensing decisions. In preparation for the next generation power plant and current government and industry efforts in support of light water reactor sustainability, human operators will be attached to a suite of physiological measurement instruments and, in combination with traditional Human Factors Measurement techniques, carry out control room tasks in simulated advanced digital and hybrid analog/digital control rooms. The current focus of the Human Systems Simulator Laboratory is building core competence in quantitative and qualitative measurements of situation awareness and workload. Of particular interest is whether introduction of digital systems including automated procedures has the potential to reduce workload and enhance safety while improving situation awareness or whether workload is merely shifted and situation awareness is modified in yet to be determined ways. Data analysis is carried out by engineers and scientists and includes measures of the physical and neurological correlates of human performance. The current approach supports a user-centered design philosophy (see ISO 13407 “Human Centered Design Process for Interactive Systems, 1999) wherein the context for task performance along with the

  3. A technical learning on the Pressurized Water Nuclear Power Plants using animation

    International Nuclear Information System (INIS)

    Ito, Hajime; Tomohara, Yasutaka; Kubo, Setsuo; Ninomiya, Toshiaki

    2002-01-01

    The pressurized water nuclear power generation plants tends to reduce construction of its new plant from viewpoints of recent stabilization in power demand/supply balance, development of new siting points, and so on. And, together with reducing any opportunity to experience at site, generation alternation to younger engineers without such experiences is progressing. In order to carry out technical tradition with high quality , as it is important to understand experiences of troubles and so on as valuable inheritance to apply them to actual use, it can be thought, in doubt, to be one of solving measures to prepare some learning tools applying the newest technology. The Kansai Electric Co., Ltd. Developed a CAD software using animation and 3D pictures using a personal computer which is edited some processes of technical transition on nuclear energy as a reference on a shape of CD ROM as an object from initial period of nuclear power station to present APWR. (G.K.)

  4. Technical dictionary power plant engineering. Vol. 1. 4. rev. and enlarged ed.

    International Nuclear Information System (INIS)

    1987-01-01

    This dictionary is a compilation of German and English technical terms of power plant engineering as far as power plants, turbine-generators and assembly engineering are concerned. It is the result of a joint effort by the Kraftwerk Union AG (KWU) and Utility Power Corp. (UPC). The entire content has been revised and approx. 6000 new terms have been added. The dictionary is meant to form a basis for uniform terminology on technical documents as well as correspondence between KWU, UPC and licensees. This computer aided dictionary is printed in capital/low case letters. Only nouns, terms with an article and proper names are capitalized in German. Some terms are written differently in American and British English and are marked with (US) or (GB). (orig./HP) [de

  5. Nuclear power plant shift technical advisor. Recommendations for position description, qualifications, education and training

    International Nuclear Information System (INIS)

    1981-01-01

    The purpose of this document is to describe the position and identify specific areas of formal education, plant-specific training and experience necessary to assure an advanced level of analytical ability on shift. These recommendations will provide a level of technical ability that is essential to improved operational safety and are consistent with regulatory requirements. This position was developed in conjunction with representatives of utilities, equipment vendors and engineering educators, giving consideration to specific contributions the function must make to shift operations

  6. Application of data-processing to the technical and economical management of the plants of Simo

    International Nuclear Information System (INIS)

    Chastagner, F.

    1988-01-01

    The firm Simo is entrusted with the processing of the uranium ores extracted from the mines of Cogema in France, in its three plants. The paper describes the conception and the functioning of the information system. Among the advantages contributed by the system, the coherence between the technical follow-up and the economical follow-up constitutes one of the principal progressive features [fr

  7. Manufacturing plant performance evaluation by discrete event simulation

    International Nuclear Information System (INIS)

    Rosli Darmawan; Mohd Rasid Osman; Rosnah Mohd Yusuff; Napsiah Ismail; Zulkiflie Leman

    2002-01-01

    A case study was conducted to evaluate the performance of a manufacturing plant using discrete event simulation technique. The study was carried out on animal feed production plant. Sterifeed plant at Malaysian Institute for Nuclear Technology Research (MINT), Selangor, Malaysia. The plant was modelled base on the actual manufacturing activities recorded by the operators. The simulation was carried out using a discrete event simulation software. The model was validated by comparing the simulation results with the actual operational data of the plant. The simulation results show some weaknesses with the current plant design and proposals were made to improve the plant performance. (Author)

  8. 30 CFR 827.12 - Coal preparation plants: Performance standards.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal preparation plants: Performance standards...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.12 Coal preparation plants..., modification, reclamation, and removal activities at coal preparation plants shall comply with the following...

  9. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, M; Carl, H; Nowak, K [Technischer Ueberwachungsverein Rheinland, Koeln (Germany). Inst. for Nuclear Engineering and Radiation Protection; Schumann, P; Seidel, A; Weiss, F P; Zschau, J

    1998-10-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  10. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Nowak, K.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.

    1998-01-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  11. Safety technical considerations on the 2012 periodic safety verification of the Beznau nuclear power plant

    International Nuclear Information System (INIS)

    2016-12-01

    According to nuclear legislation, the owner of an operational license for a nuclear power plant has to provide a periodic safety verification (PSU) every 10 years. The 'North Eastern Power Plants' company (NOK), today AXPO Power AG already performed such a PSU for the Beznau-2 nuclear reactor block (KKB2) in 2002. The Beznau-1 nuclear reactor block (KKB1) received its definitive operational license in October 1970, after test operation during 7 months. After the license for test operation received on July 16 th , 1971, the operational license of KKB2 was renewed several times, each time for a certain period of validity. In 1991, NOK requested a definitive operational license for KKB2, but in 1994 the Swiss Federal Council lengthened the license for only 10 years. Moreover, it laid down that NOK has to periodically report on the safety of the facility. With its letter of August 23 rd , 1998, the Federal Office of Energy defined the documents to be produced for the PSU. The extent of the PSU was defined in such a way that many documents concern the whole power plant, i.e. both nuclear reactor blocks. On December 3 rd , 2004, the Swiss Federal Council granted KKB2 an operational license of limited validity. The present report reviews the 2012 PSU, which covers the time interval from January 1 st , 2002, to December 31 st , 2011, from the point of view of safety. It contains documents for the evaluation of both reactor blocks at KKB. The Beznau interim storage pool was also taken into consideration; it is situated on the KKB site, but, according to a decision of the Swiss Federal Council of May 23 rd , 1991, it has an independent operational license. The evaluation of ageing surveillance takes the whole operational period of the facility into account, i.e. the ageing mechanisms acting as from the beginning of the operation. Moreover, important developments that occurred after the surveillance time interval have been taken into account, especially the status

  12. Factors that influence the non-technical skills performance of scrub nurses: a prospective study.

    Science.gov (United States)

    Kang, Evelyn; Massey, Debbie; Gillespie, Brigid M

    2015-12-01

    To identify and describe the factors that impact on the performance of scrub nurses' non-technical skills performance during the intra-operative phase of surgery. Non-technical skills have been identified as important precursors to errors in the operating room. However, few studies have investigated factors influencing non-technical skills of scrub nurses. Prospective observational study. Structured observations were performed on a sample of 182 surgical procedures across eight specialities by two trained observers from August 2012-April 2013 at two hospital sites. Participants were purposively selected scrub nurses. Bivariate correlations and a multiple linear regression model were used to identify associations among length of surgery, patients' acuity using the American Society of Anesthesiologists classification system, team familiarity, number of occasions scout nurses leave the operating room, change of scout nurse and the outcome, the non-technical skills performance of scrub nurses. Patient acuity and team familiarity were the strongest predictors of scrub nurses' non-technical skills performance at hospital site A. There were no correlations between the predictors and the performance of scrub nurses at hospital site B. A dedicated surgical team and patient acuity potentially influence the performance of scrub nurses' non-technical skills. Familiarity with team members foster advanced planning, thus minimizing distractions and interruptions that impact on scrub nurses' performance. Development of interventions aimed at improving non-technical skills has the potential to make a substantial difference and enhance patient care. © 2015 John Wiley & Sons Ltd.

  13. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Groom, S.H.

    1994-01-01

    The workshop which was intended to present operating experiences from utilities with a wide range of numbers of operating nuclear units. The speaker, S.H. Groom, presented N.B. Power's experience with a single nuclear unit, and intended to: Present the objectives, organization, and scope of work of the central and site Technical Service groups within N.B. Power which support the operation of the Point Lepreau NGS; Define responsibilities of, and interfaces between the on-site and the central technical service staff; Recommend methods for the establishment and maintenance of an efficient technical support group for the operation of any nuclear power plant

  14. Technical analysis of advanced wastewater-treatment systems for coal-gasification plants

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-31

    This analysis of advanced wastewater treatment systems for coal gasification plants highlights the three coal gasification demonstration plants proposed by the US Department of Energy: The Memphis Light, Gas and Water Division Industrial Fuel Gas Demonstration Plant, the Illinois Coal Gasification Group Pipeline Gas Demonstration Plant, and the CONOCO Pipeline Gas Demonstration Plant. Technical risks exist for coal gasification wastewater treatment systems, in general, and for the three DOE demonstration plants (as designed), in particular, because of key data gaps. The quantities and compositions of coal gasification wastewaters are not well known; the treatability of coal gasification wastewaters by various technologies has not been adequately studied; the dynamic interactions of sequential wastewater treatment processes and upstream wastewater sources has not been tested at demonstration scale. This report identifies key data gaps and recommends that demonstration-size and commercial-size plants be used for coal gasification wastewater treatment data base development. While certain advanced treatment technologies can benefit from additional bench-scale studies, bench-scale and pilot plant scale operations are not representative of commercial-size facility operation. It is recommended that coal gasification demonstration plants, and other commercial-size facilities that generate similar wastewaters, be used to test advanced wastewater treatment technologies during operation by using sidestreams or collected wastewater samples in addition to the plant's own primary treatment system. Advanced wastewater treatment processes are needed to degrade refractory organics and to concentrate and remove dissolved solids to allow for wastewater reuse. Further study of reverse osmosis, evaporation, electrodialysis, ozonation, activated carbon, and ultrafiltration should take place at bench-scale.

  15. Technical basis for the internal dosimetry program at the Y-12 Plant

    International Nuclear Information System (INIS)

    Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

    1992-01-01

    Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document

  16. Writing Performance Goals: Strategy and Prototypes. A Manual for Vocational and Technical Educators.

    Science.gov (United States)

    McGraw-Hill Book Co., New York, NY. Gregg Div.

    The result of a cooperative project of the Center for Vocational and Technical Education at the Ohio State University and the McGraw-Hill Book Company, this manual was prepared to develop prototypes of performance goals for use by curriculum specialists and developers of instructional materials in vocational and technical education and to provide…

  17. Nuclear heat generating plants - technical concepts and market potentials. Chapter 11

    International Nuclear Information System (INIS)

    Hasenkopf, O.; Erhard, W.D.; Nonnenmacher, A.; Hanselmann, M.

    1988-01-01

    Within the framework of a case study under the Federal Ministry of Research and Technology project 'Nuclear heat generating plants - technological concepts and market potentials', the possible applications of such plants were studied giving the district heat supply network of the Technische Werke der Stadt Stuttgart AG (Technical Works of the City of Stuttgart, Inc.) as an example. The use of district heating systems concentrated specifically on areas identified for economical supply because of their topographical position, existing heat density, distance from power plants, and a reasonable delimination from the available gas network. Based on the results of optimization calculations made by the Stuttgart Institute for Nuclear Technology and Energy Conversion, the required investment capital can be estimated as a function of the amount of fuel savings under the Stuttgart case study. (orig./UA) [de

  18. A Performance Measurement Tool Leading Wastewater Treatment Plants toward Economic Efficiency and Sustainability

    Directory of Open Access Journals (Sweden)

    Andrea Guerrini

    2016-11-01

    Full Text Available Wastewater treatment is an important link in the water cycle that allows for water sanitation and reuse, facilitates energy generation, and allows for the recovery of products from waste. The scientific community has paid significant attention to wastewater treatment, especially from a technical point of view. Extensive literature is available on new technologies, processes, and materials to improve wastewater treatment. However, scant studies have been conducted in the management field focusing on the development of a performance measurement tool that supports plant managers. The current article addresses this literature gap, developing a reporting tool that integrates technical and cost measures and implements it in a large wastewater utility. The tool successfully identifies cause and effect linkages among key plant performance drivers and supports management in finding activities with poor performance and allows them to delay non-relevant measures of control.

  19. Method for assessment of the technical potential of the plant agricultural waste suitable for energy purposes in Bulgaria

    International Nuclear Information System (INIS)

    Georgiev, V.

    2004-01-01

    A method for assessment of technical potential of quantitatively important plant agriculture waste; straw from wheat and barley; corn stalks; sunflower stalks and heads; tobacco stalks; orchard prunings and vineyard prunings suitable for energy purposes for Bulgarian conditions is developed. Data for assessment of the technical potential for 2002 using this method are presented. A comparison between technical potential of mentioned wastes, final energy consumption in agriculture and all branches of Bulgarian economy for 2002 is made. (author)

  20. Application of Advanced Technology to Improve Plant Performance in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2011-01-01

    Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

  1. Technical performance and match-to-match variation in elite football teams.

    Science.gov (United States)

    Liu, Hongyou; Gómez, Miguel-Angel; Gonçalves, Bruno; Sampaio, Jaime

    2016-01-01

    Recent research suggests that match-to-match variation adds important information to performance descriptors in team sports, as it helps measure how players fine-tune their tactical behaviours and technical actions to the extreme dynamical environments. The current study aims to identify the differences in technical performance of players from strong and weak teams and to explore match-to-match variation of players' technical match performance. Performance data of all the 380 matches of season 2012-2013 in the Spanish First Division Professional Football League were analysed. Twenty-one performance-related match actions and events were chosen as variables in the analyses. Players' technical performance profiles were established by unifying count values of each action or event of each player per match into the same scale. Means of these count values of players from Top3 and Bottom3 teams were compared and plotted into radar charts. Coefficient of variation of each match action or event within a player was calculated to represent his match-to-match variation of technical performance. Differences in the variation of technical performances of players across different match contexts (team and opposition strength, match outcome and match location) were compared. All the comparisons were achieved by the magnitude-based inferences. Results showed that technical performances differed between players of strong and weak teams from different perspectives across different field positions. Furthermore, the variation of the players' technical performance is affected by the match context, with effects from team and opposition strength greater than effects from match location and match outcome.

  2. Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

    International Nuclear Information System (INIS)

    Galkin, A.V.; Baldov, A.N.

    2001-01-01

    In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

  3. Technical activity profile and influence of body anthropometry on playing performance in female elite team handball

    DEFF Research Database (Denmark)

    Michalsik, Lars B; Aagaard, Per; Madsen, Klavs

    2015-01-01

    regular tournament match seasons. Technical match activities were distributed in 6 major types of playing actions (shots, breakthroughs, fast breaks, technical errors, defensive errors, and tackles) and further divided into various subcategories (e.g., type of shot, hard or light tackles, claspings......, screenings, and blockings). Furthermore, anthropometric measurements were performed. Each player had 28.3 ± 11.0 (group means ± SD) high-intense playing actions per match with a total effective playing time of 50.70 ± 5.83 minutes. On average, each player made 2.8 ± 2.6 fast breaks, gave 7.9 ± 14...... that female elite TH players during competitive games intermittently perform a high number of short-term, high-intense technical playing actions making modern female elite TH a physically demanding team sport. No sign of technical fatigue were observed, since the amount of intense technical playing actions...

  4. Technical match characteristics and influence of body anthropometry on playing performance in male elite team handball

    DEFF Research Database (Denmark)

    Michalsik, Lars Bojsen; Madsen, Klavs; Aagaard, Per

    2015-01-01

    ). In conclusion, modern male elite team handball match-play is characterized by a high number of short-term, high-intense intermittent technical playing actions. Indications of technical fatigue were observed. Physical demands differed between playing positions with wing players performing more fast breaks...... players along with anthropometric measurements over a 6 season time span. Technical match activities were distributed in 6 major types of playing actions (shots, breakthroughs, fast breaks, tackles, technical errors, and defense errors) and further divided into various subcategories (e.g., hard or light...... tackles, type of shot, claspings, screenings, and blockings). Players showed 36.9 ± 13.1 (group mean ± SD) high-intense technical playing actions per match with a mean total effective playing time of 53.85 ± 5.87 minutes. In offense, each player performed 6.0 ± 5.2 fast breaks, received 34.5 ± 21...

  5. Technologies for improving the availability and reliability of current and future water cooled nuclear power plants. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    One of the activities of the IAEA is to provide all Member States with an international source of balanced, objective information on advanced in technology for water cooled reactors. Since the global nuclear industry has a common interest in improving plant availability and reliability to assure specific individual plant and country perspective as well as to have an image of well managed competitive industry, the IAEA held a Technical Committee Meeting on Technologies for Improving the Availability and Reliability of Current and Future Water Cooled Nuclear Power Plants in September 1997. The basic aim to was to identify, review and exchange information on international developments in technologies for achieving high availability and reliability and to suggest areas where further technical advances could contribute to improvement of performance. Designs for future plants were presented in the context of how they can accommodate both the organizational and technical means for reaching even higher levels of performance. This proceedings contains the contributed papers presented at this Meeting each with a separate abstract. Four sessions were concerned with: policies, practices and procedures for achieving high reliability and availability; improving availability and reliability through better use of today`s technologies; recent advances in technologies for improving availability and reliability; achieving high availability for new plants Refs, figs, tabs

  6. Technologies for improving the availability and reliability of current and future water cooled nuclear power plants. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-11-01

    One of the activities of the IAEA is to provide all Member States with an international source of balanced, objective information on advanced in technology for water cooled reactors. Since the global nuclear industry has a common interest in improving plant availability and reliability to assure specific individual plant and country perspective as well as to have an image of well managed competitive industry, the IAEA held a Technical Committee Meeting on Technologies for Improving the Availability and Reliability of Current and Future Water Cooled Nuclear Power Plants in September 1997. The basic aim to was to identify, review and exchange information on international developments in technologies for achieving high availability and reliability and to suggest areas where further technical advances could contribute to improvement of performance. Designs for future plants were presented in the context of how they can accommodate both the organizational and technical means for reaching even higher levels of performance. This proceedings contains the contributed papers presented at this Meeting each with a separate abstract. Four sessions were concerned with: policies, practices and procedures for achieving high reliability and availability; improving availability and reliability through better use of today's technologies; recent advances in technologies for improving availability and reliability; achieving high availability for new plants

  7. Effect of obstetric team training on team performance and medical technical skills: a randomised controlled trial

    NARCIS (Netherlands)

    Fransen, A.F.; Ven, van de J.; Merién, A.E.R.; Wit-Zuurendonk, de L.D.; Houterman, S.; Mol, B.W.J.; Oei, S.G.

    2012-01-01

    Objective To determine whether obstetric team training in a medical simulation centre improves the team performance and utilisation of appropriate medical technical skills of healthcare professionals. Design Cluster randomised controlled trial. Setting The Netherlands. Sample The obstetric

  8. Integrated Technical Information for the Air Logistics Center: Enhancing Maintenance Technician Task Performance

    National Research Council Canada - National Science Library

    Mitta, Deborah

    1998-01-01

    This technical paper documents the final results of an analysis of the task environment under which depot maintenance technicians perform their jobs--specifically, programmed depot maintenance (PDM) for F-15 aircraft...

  9. Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3

    International Nuclear Information System (INIS)

    Ulm, Franz-Josef

    2000-01-01

    OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3(NOTE: Part II A item 1 indicates ''PAPER'', but a report is attached electronically)

  10. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, Garth M. [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States); Saunders, Scott A. [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)

    2013-07-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

  11. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    International Nuclear Information System (INIS)

    Duncan, Garth M.; Saunders, Scott A.

    2013-01-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

  12. New technical knowledge to be implemented to the revision of rules on pipe wall thinning management for PWR plants

    International Nuclear Information System (INIS)

    Hirai, Junya; Nakamura, Takao; Amano, Yoichi

    2013-01-01

    Rules for PWR plant pipe wall thinning management were formulated by the Japan Society of Mechanical Engineers in 2006. Since then thinning management of Japanese PWR plants has been carried out based on this rule. Pipe wall thinning phenomena to be dealt with in this rule have been identified in many piping components of power plants. New technical knowledge has been accumulated since the issuance of 2006 edition. We have formulated these knowledge and information about the thinning phenomena in PWR power plants. Given the history of application of this rule, we have to make our best effort to carry out a study of latest technical knowledge and implement them to the revision of rule and improve pipe wall thinning management. This paper summarizes the new technical knowledge and basis to be implemented to the revision of rules on pipe wall thinning management for PWR plants in Japan. (author)

  13. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Kofron, K.L.

    1994-01-01

    The seminar was held in Wuhan PRC from 01.10/94 - 01/14/94. It revolved about the role of the Technical Support Groups, both onsite and offsite, of the Nuclear Power Plant. This was to assist the Chinese in deciding their best course of action for the establishment and operation of this group

  14. Corrosion performance tests for reinforcing steel in concrete : technical report.

    Science.gov (United States)

    2009-10-01

    The existing test method used to assess the corrosion performance of reinforcing steel embedded in : concrete, mainly ASTM G 109, is labor intensive, time consuming, slow to provide comparative results, : and can be expensive. However, with corrosion...

  15. Long-term performance of GFRP reinforcement : technical report.

    Science.gov (United States)

    2009-12-01

    Significant research has been performed on glass fiber-reinforced polymer (GFRP) concrete reinforcement. : This research has shown that GFRP reinforcement exhibits high strengths, is lightweight, can decrease time of : construction, and is corrosion ...

  16. Is the technical performance of young soccer players influenced by hormonal status, sexual maturity, anthropometric profile, and physical performance?

    Science.gov (United States)

    Moreira, Alexandre; Massa, Marcelo; Thiengo, Carlos R; Rodrigues Lopes, Rafael Alan; Lima, Marcelo R; Vaeyens, Roel; Barbosa, Wesley P; Aoki, Marcelo S

    2017-12-01

    The aim of this study was to examine the influence of hormonal status, anthropometric profile, sexual maturity level, and physical performance on the technical abilities of 40 young male soccer players during small-sided games (SSGs). Anthropometric profiling, saliva sampling, sexual maturity assessment (Tanner scale), and physical performance tests (Yo-Yo and vertical jumps) were conducted two weeks prior to the SSGs. Salivary testosterone was determined by the enzyme-linked immunosorbent assay method. Technical performance was determined by the frequency of actions during SSGs. Principal component analyses identified four technical actions of importance: total number of passes, effectiveness, goal attempts, and total tackles. A multivariate canonical correlation analysis was then employed to verify the prediction of a multiple dependent variables set (composed of four technical actions) from an independent set of variables, composed of testosterone concentration, stage of pubic hair and genitalia development, vertical jumps and Yo-Yo performance. A moderate-to-large relationship between the technical performance set and the independent set was observed. The canonical correlation was 0.75 with a canonical R 2 of 0.45. The highest structure coefficient in the technical performance set was observed for tackles (0.77), while testosterone presented the highest structure coefficient (0.75) for the variables of the independent set. The current data suggest that the selected independent set of variables might be useful in predicting SSG performance in young soccer players. Coaches should be aware that physical development plays a key role in technical performance to avoid decision-making mistakes during the selection of young players.

  17. Technical considerations in repowering a nuclear plant for fossil fueled operation

    International Nuclear Information System (INIS)

    Patti, F.J.

    1996-01-01

    Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today's world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal

  18. Analysis of technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla'

    Directory of Open Access Journals (Sweden)

    Grbić Maja

    2014-01-01

    Full Text Available This paper presents an analysis of the technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla' in Belgrade. Calculation of solar irradiation is performed and the conceptual design of the disposition of solar panels on the roof of the building is shown as well as their connections to the inverters. Conditions for connecting the plant to the distribution network are checked and an economic analysis of the project is performed.

  19. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum and course development and evaluation research. First, the context of, and impetus for, what was formerly called vocational education, now referred to as technical or workforce education, is provided. Second, the research that was undertaken to design and evaluate an associate degree-level STEM workforce education program is described. Third, the adaptation of a student self-assessment of learning gains instrument is reviewed, and an analysis of the resulting data using an adapted logic model is provided, to evaluate the extent to which instructional approaches, in two process control/improvement-focused courses, were effective in meeting course-level intended learning outcomes. Finally, eight integrative multiscale exercises were designed from two example process systems, wastewater treatment and fast pyrolysis. The integrative exercises are intended for use as tools to accelerate the formation of an operator-technician's multiscale vision of systems, unit operations, underlying processes, and fundamental reactions relevant to multiple industries. Community and technical colleges serve a vital function in STEM education by training workers for medium- and high-skilled technical careers and providing employers the labor necessary to operate and maintain thriving business ventures. Through development of the curricular, course, and assessment-related instruments and tools, this research helps ensure associate degree-level technical education programs can engage in a continual process of program evaluation and improvement.

  20. Thermal performance analysis of a solar heating plant

    DEFF Research Database (Denmark)

    Fan, Jianhua; Huang, Junpeng; Andersen, Ola Lie

    was developed to calculate thermal performances of the plant. In the Trnsys model, three solar collector fields with a total solar collector area of 33,300 m2, a seasonal water pit heat storage of 75,000 m3, a simplified CO2 HP, a simplified ORC unit and a simplified wood chip boiler were included. The energy......Detailed measurements were carried out on a large scale solar heating plant located in southern Denmark in order to evaluate thermal performances of the plant. Based on the measurements, energy flows of the plant were evaluated. A modified Trnsys model of the Marstal solar heating plant...... consumption of the district heating net was modeled by volume flow rate and given forward and return temperatures of the district heating net. Weather data from a weather station at the site of the plant were used in the calculations. The Trnsys calculated yearly thermal performance of the solar heating plant...

  1. 48 CFR 1816.402-270 - NASA technical performance incentives.

    Science.gov (United States)

    2010-10-01

    ... under procedures other than FAR part 12 at the discretion of the procurement officer upon consideration of the guidelines in 1816.402. Performance incentives, which are objective and measure hardware... negative, and its associated unit of measurement should reflect the value to the Government of that level...

  2. Operation of a semi-technical pilot plant for nuclear aided steam gasification of coal

    International Nuclear Information System (INIS)

    Kirchhoff, R.; Heek, K.H. van; Juentgen, H.; Peters, W.

    1984-01-01

    After intensive investigations on a small scale, the principle of the process has been tested in a semi-technical pilot plant. In its gasifier a fluidized bed of approx. 1 m 2 cross-section and of up to 4 m height is operated at 40 bar. Heat is supplied to the bed from an immersed heat exchanger with helium flowing through it, which is heated electrically. The plant was commissioned in 1976 and has been in hot operation for approx. 23000 h, over 13000 h whereof account for coal gasification. Roughly 1600 t of coal have been put through. During recent years the processing of German caking long-flame gas coal and the marked improvement of the process by the use of catalysts have been demonstrated successfully. (orig.)

  3. Floating nuclear energy plants for seawater desalination. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    Floating nuclear desalination facilities are one of the alternatives being considered. They may offer a particularly suitable choice for remote locations and small island or coastal communities where the necessary manpower and infrastructure to support desalination plants are not available. In the interest of focusing specific attention on the technology of floating nuclear desalination, the IAEA sponsored a Technical Committee Meeting on Floating Nuclear Plants for Seawater Desalination from 29 to 31 May 1995 in Obninsk, Russian Federation. This publication documents the papers and presentations given by experts from several countries at that meeting. It is hoped that the information contained in this report will be a valuable resource for those interested in nuclear desalination, and that it will stimulate further interest in the potential for floating nuclear desalination facilities. Refs, figs, tabs

  4. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Saurwein, John

    2011-07-15

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  5. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    International Nuclear Information System (INIS)

    Saurwein, J.

    2011-01-01

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  6. Technical improvement of ATE system of Ling'ao Nuclear Power Plant Phase II

    International Nuclear Information System (INIS)

    Zhu Xingbao; Xiong Jingchuan; Liang Qiaohong

    2009-01-01

    In order to solve the problem that the content of SO 4 2- in Steam Generator significantly increased beyond the criteria after the use of the condensate treatment (ATE) system in Daya Bay Nuclear Power Plant and Ling'ao Nuclear Power Plant Phase I, technical improvement have been conducted on the sizes of the fore cation bed and the mixed bed, water distributing devices, ion exchange resins and separation facility. The effectiveness for the ion exchange of the mixed bed is improved, the resolved substance of cation resin is decreased; it is more impossible for fragments and powder which would lead high SO 4 2- content in Steam Generator. Finally, the quality of the steam-water could be improved and ensured. (authors)

  7. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force

  8. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force Refs, figs, tabs

  9. Wind Plant Performance Prediction (WP3) Project

    Energy Technology Data Exchange (ETDEWEB)

    Craig, Anna [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-01-26

    The methods for analysis of operational wind plant data are highly variable across the wind industry, leading to high uncertainties in the validation and bias-correction of preconstruction energy estimation methods. Lack of credibility in the preconstruction energy estimates leads to significant impacts on project financing and therefore the final levelized cost of energy for the plant. In this work, the variation in the evaluation of a wind plant's operational energy production as a result of variations in the processing methods applied to the operational data is examined. Preliminary results indicate that selection of the filters applied to the data and the filter parameters can have significant impacts in the final computed assessment metrics.

  10. AN ANALYSIS OF TECHNICAL SECURITY CONTROL REQUIREMENTS FOR DIGITAL I&C SYSTEMS IN NUCLEAR POWER PLANTS

    Directory of Open Access Journals (Sweden)

    JAE-GU SONG

    2013-10-01

    Full Text Available Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

  11. The performance of nuclear power plants

    International Nuclear Information System (INIS)

    1989-07-01

    A survey is presented of failures in the Dutch nuclear power plants Borssele (10) and Dodewaard (5) reported during the year 1988. This reporting takes place, since 1987, on the basis of the international failure-reporting system. This system is based on the 'Incident Reporting System' of the IAEA. During 1988 no failures did occur which made particular safety measurements necessary. Also these failures did not have any consequence for the environment. During all failures the reactor safety system of both power plants did operate well. (H.W.)

  12. Assessment of materials selection and performance for direct-coal- liquefaction plants in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, A.R.; Judkins, R.R.; Keiser, J.R.

    1996-09-01

    Several direct coal liquefaction processes have been demonstrated at the pilot plant level in the United States. Presently only one plant remains operational, namely, the Hydrocarbon Technologies, Inc., 4.0- ton-per-day process development unit in Lawrenceville, New Jersey. The period from 1974 to 1982 saw the greatest amount of development of direct coal liquefaction in the United States with four major pilot plants being devoted to variants of this technology. The plants included the SRC-I plant at Wilsonville, Alabama, which operated from 1974 to 1992; the SRC-I/II plant at Fort Lewis, Washington, which operated from 1974 to 1981; the H-Coal plant at Catlettsburg, Kentucky, which operated from 1980 to 1982; and the Exxon Coal Liquefaction Pilot Plant at Baytown, Texas, which operated from 1980 to 1982. Oak Ridge National Laboratory scientists and engineers were actively involved in many phases and technical disciplines at all four of these plants, especially in materials testing, evaluation, and failure analyses. In addition, ORNL materials scientists and engineers conducted reviews of the demonstration and commercial plant designs for materials selections. The ORNL staff members worked closely with materials engineers at the pilot plants in identifying causes of materials degradation and failures, and in identifying solutions to these problems. This report provides a comprehensive summary of those materials activities. Materials performance data from laboratory and coal liquefaction pilot plant tests, failure analyses, and analyses of components after use in pilot plants were reviewed and assessed to determine the extent and causes of materials degradation in direct coal liquefaction process environments. Reviews of demonstration and commercial plant design documents for materials selections were conducted. These reviews and assessments are presented to capture the knowledge base on the most likely materials of construction for direct coal liquefaction plants.

  13. Technical specifications, Callaway Plant, Unit No. 1. Appendix A to license No. NPF-25 (Docket No. STN 50-483)

    International Nuclear Information System (INIS)

    Anderson, F.D.

    1984-06-01

    Technical specifications are presented for the limiting conditions for operation and surveillance requirements for the reactor core, reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, radiological environmental monitoring; design features of the site, containment, core, coolant system, and fuel storage; and plant staff organization

  14. The impact of nontechnical skills on technical performance in surgery: a systematic review.

    Science.gov (United States)

    Hull, Louise; Arora, Sonal; Aggarwal, Rajesh; Darzi, Ara; Vincent, Charles; Sevdalis, Nick

    2012-02-01

    Failures in nontechnical and teamwork skills frequently lie at the heart of harm and near-misses in the operating room (OR). The purpose of this systematic review was to assess the impact of nontechnical skills on technical performance in surgery. MEDLINE, EMBASE, PsycINFO databases were searched, and 2,041 articles were identified. After limits were applied, 341 articles were retrieved for evaluation. Of these, 28 articles were accepted for this review. Data were extracted from the articles regarding sample population, study design and setting, measures of nontechnical skills and technical performance, study findings, and limitations. Of the 28 articles that met inclusion criteria, 21 articles assessed the impact of surgeons' nontechnical skills on their technical performance. The evidence suggests that receiving feedback and effectively coping with stressful events in the OR has a beneficial impact on certain aspects of technical performance. Conversely, increased levels of fatigue are associated with detriments to surgical skill. One article assessed the impact of anesthesiologists' nontechnical skills on anesthetic technical performance, finding a strong positive correlation between the 2 skill sets. Finally, 6 articles assessed the impact of multiple nontechnical skills of the entire OR team on surgical performance. A strong relationship between teamwork failure and technical error was empirically demonstrated in these studies. Evidence suggests that certain nontechnical aspects of performance can enhance or, if lacking, contribute to deterioration of surgeons' technical performance. The precise extent of this effect remains to be elucidated. Copyright © 2012 American College of Surgeons. Published by Elsevier Inc. All rights reserved.

  15. Human Performance in Continuous Operations. Volume 3. Technical Documentation

    Science.gov (United States)

    1980-03-01

    completed for the U. S. Commander, V Corps. Artillery, by Manning (1978). Manning collected information which bears on the following three questions: 0 Can...performance data were not collected in these pre- liminary studies. Field Studies of Continuous Tank OperationsLI __ _ _ __ _ _ _ To simulate a combat...on routine, monotonous tasks tends A show rapid and severe decrement after peri- odk of more than 24 hours without sleep. I Increasing task complexity

  16. Spatial abilities and technical skills performance in health care: a systematic review.

    Science.gov (United States)

    Langlois, Jean; Bellemare, Christian; Toulouse, Josée; Wells, George A

    2015-11-01

    The aim of this study was to conduct a systematic review and meta-analysis of the relationship between spatial abilities and technical skills performance in health care in beginners and to compare this relationship with those in intermediate and autonomous learners. Search criteria included 'spatial abilities' and 'technical skills'. Keywords related to these criteria were defined. A literature search was conducted to 20 December, 2013 in Scopus (including MEDLINE) and in several databases on EBSCOhost platforms (CINAHL Plus with Full Text, ERIC, Education Source and PsycINFO). Citations were obtained and reviewed by two independent reviewers. Articles related to retained citations were reviewed and a final list of eligible articles was determined. Articles were assessed for quality using the Scottish Intercollegiate Guidelines Network-50 assessment instrument. Data were extracted from articles in a systematic way. Correlations between spatial abilities test scores and technical skills performance were identified. A series of 8289 citations was obtained. Eighty articles were retained and fully reviewed, yielding 36 eligible articles. The systematic review found a tendency for spatial abilities to be negatively correlated with the duration of technical skills and positively correlated with the quality of technical skills performance in beginners and intermediate learners. Pooled correlations of studies were -0.46 (p = 0.03) and -0.38 (95% confidence interval [CI] -0.53 to -0.21) for duration and 0.33 (95% CI 0.20-0.44) and 0.41 (95% CI 0.26-0.54) for quality of technical skills performance in beginners and intermediate learners, respectively. However, correlations between spatial abilities test scores and technical skills performance were not statistically significant in autonomous learners. Spatial abilities are an important factor to consider in selecting and training individuals in technical skills in health care. © 2015 John Wiley & Sons Ltd.

  17. Application of Advanced Technology to Improve Plant Performance. Safety and Performance in Current NPPs

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2011-01-01

    Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

  18. Not just trust: factors influencing learners' attempts to perform technical skills on real patients.

    Science.gov (United States)

    Bannister, Susan L; Dolson, Mark S; Lingard, Lorelei; Keegan, David A

    2018-06-01

    As part of their training, physicians are required to learn how to perform technical skills on patients. The previous literature reveals that this learning is complex and that many opportunities to perform these skills are not converted into attempts to do so by learners. This study sought to explore and understand this phenomenon better. A multi-phased qualitative study including ethnographic observations, interviews and focus groups was conducted to explore the factors that influence technical skill learning. In a tertiary paediatric emergency department, staff physician preceptors, residents, nurses and respiratory therapists were observed in the delivery and teaching of technical skills over a 3-month period. A constant comparison methodology was used to analyse the data and to develop a constructivist grounded theory. We conducted 419 hours of observation, 18 interviews and four focus groups. We observed 287 instances of technical skills, of which 27.5% were attempted by residents. Thematic analysis identified 14 factors, grouped into three categories, which influenced whether residents attempted technical skills on real patients. Learner factors included resident initiative, perceived need for skill acquisition and competing priorities. Teacher factors consisted of competing priorities, interest in teaching, perceived need for residents to acquire skills, attributions about learners, assessments of competency, and trust. Environmental factors were competition from other learners, judgement that the patient was appropriate, buy-in from team members, consent from patient or caregivers, and physical environment constraints. Our findings suggest that neither the presence of a learner in a clinical environment nor the trust of the supervisor is sufficient to ensure the learner will attempt a technical skill. We characterise this phenomenon as representing a pool of opportunities to conduct technical skills on live patients that shrinks to a much smaller pool of

  19. Engaging Local Stakeholders on Technical Issues: Test Case at the La Hague Reprocessing Plant - 59211

    International Nuclear Information System (INIS)

    Gilli, Ludivine

    2012-01-01

    In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) lead a pilot action dealing with the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of the pilot program was to test ways for IRSN and a few local stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the local stakeholders to review the operator's decommissioning application and provide input. The pilot program confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues. Three factors influence the extent of the challenge: the knowledge gap between experts and local stakeholders, the conflict between transparency and confidentiality which is inherent with technical topics, and the difficulty for an official expertise institute to hold a dialogue with 'outsiders' during an ongoing reviewing process in which it is participating. The pilot program, given its mixed results, also provided valuable lessons for further improvement of stakeholders' involvement. (authors)

  20. Testing the performance of technical trading rules in the Chinese markets based on superior predictive test

    Science.gov (United States)

    Wang, Shan; Jiang, Zhi-Qiang; Li, Sai-Ping; Zhou, Wei-Xing

    2015-12-01

    Technical trading rules have a long history of being used by practitioners in financial markets. The profitable ability and efficiency of technical trading rules are yet controversial. In this paper, we test the performance of more than seven thousand traditional technical trading rules on the Shanghai Securities Composite Index (SSCI) from May 21, 1992 through June 30, 2013 and China Securities Index 300 (CSI 300) from April 8, 2005 through June 30, 2013 to check whether an effective trading strategy could be found by using the performance measurements based on the return and Sharpe ratio. To correct for the influence of the data-snooping effect, we adopt the Superior Predictive Ability test to evaluate if there exists a trading rule that can significantly outperform the benchmark. The result shows that for SSCI, technical trading rules offer significant profitability, while for CSI 300, this ability is lost. We further partition the SSCI into two sub-series and find that the efficiency of technical trading in sub-series, which have exactly the same spanning period as that of CSI 300, is severely weakened. By testing the trading rules on both indexes with a five-year moving window, we find that during the financial bubble from 2005 to 2007, the effectiveness of technical trading rules is greatly improved. This is consistent with the predictive ability of technical trading rules which appears when the market is less efficient.

  1. Technical and economic performance of integrated bioenergy systems

    International Nuclear Information System (INIS)

    Toft, A.J.; Bridgwater, A.V.

    1996-01-01

    A comprehensive study of biomass production, conversion and utilisation systems has been carried out to examine complete bioenergy systems from biomass in the forest to electricity delivered to the grid. Spreadsheet models have been derived for all of the key steps in an integrated process and these have been compiled into an overall BioEnergy Assessment Model (BEAM). The model has also been used to investigate both the performance of different technologies and the effect of different configurations of the same basic system by manipulating the interfaces between feed production, feed conversion and electricity generation. Some of the results of these analyses are presented here. (orig.)

  2. Technical and economic performance of integrated bioenergy systems

    Energy Technology Data Exchange (ETDEWEB)

    Toft, A.J.; Bridgwater, A.V. [Aston Univ. (United Kingdom). Energy Research Group; Mitchell, C.P.; Watters, M.P. [Aberdeen Univ. (United Kingdom). Wood Supply Research Group; Stevens, D.J. [Cascade Research, Inc. (United States)

    1996-12-31

    A comprehensive study of biomass production, conversion and utilisation systems has been carried out to examine complete bioenergy systems from biomass in the forest to electricity delivered to the grid. Spreadsheet models have been derived for all of the key steps in an integrated process and these have been compiled into an overall BioEnergy Assessment Model (BEAM). The model has also been used to investigate both the performance of different technologies and the effect of different configurations of the same basic system by manipulating the interfaces between feed production, feed conversion and electricity generation. Some of the results of these analyses are presented here. (orig.)

  3. Technical and economic performance of integrated bioenergy systems

    Energy Technology Data Exchange (ETDEWEB)

    Toft, A J; Bridgwater, A V [Aston Univ. (United Kingdom). Energy Research Group; Mitchell, C P; Watters, M P [Aberdeen Univ. (United Kingdom). Wood Supply Research Group; Stevens, D J [Cascade Research, Inc. (United States)

    1997-12-31

    A comprehensive study of biomass production, conversion and utilisation systems has been carried out to examine complete bioenergy systems from biomass in the forest to electricity delivered to the grid. Spreadsheet models have been derived for all of the key steps in an integrated process and these have been compiled into an overall BioEnergy Assessment Model (BEAM). The model has also been used to investigate both the performance of different technologies and the effect of different configurations of the same basic system by manipulating the interfaces between feed production, feed conversion and electricity generation. Some of the results of these analyses are presented here. (orig.)

  4. Human Performance at the Perry Nuclear Power Plant

    International Nuclear Information System (INIS)

    Rabe, Alan W.

    1998-01-01

    Provides a description of human performance training for plant workers as implemented at the Perry Nuclear Power Plant. Practical concepts regarding the training are presented as well as a demonstration of some of the training material. Concepts are drawn from INPO, Reason and Deming. The paper encourages the use of site-wide and individual organizational unit training in human performance management techniques. (author)

  5. Technical and economical prerequisites of special district-heating nuclear power plant development

    International Nuclear Information System (INIS)

    Baturov, B.B.; Boldyrev, V.M.; Losev, V.L.; Sigal, M.V.

    1983-01-01

    Results are presented of technical and economical analysis of advisability of constructing combined Nuclear Power and Heating Plants (NPHP) assuring the possibility of their location near the areas of heat power consumption in case of observing a given degree of radiation safety for population and personnel. Specific features determining the choice of turbine-driven units for such plants are analyzed. Conditions of competiveness of a specialized NPHP with alternative power units, NPHP based on the WWER-1000 reactor and district heating plants (NDHP), are determined. Analysis of design specifications of NPHP with two VK-500 reactor units and structures of capital investments in such a plant reveal that an increase in the total capital investments in the NPHP would not exceed 2% with account of the difference in costs for grid heaters and a corresponding change in dimensions of operation rooms as well as changes in costs of heat removal system (within one site) at the TK turbine replacement by the T turbine

  6. Technical and economic assessment of the integrated solar combined cycle power plants in Iran

    International Nuclear Information System (INIS)

    Soltani Hosseini, M.; Hosseini, R.; Valizadeh, G.H.

    2002-01-01

    Thermal efficiency, capacity factor, environmental considerations, investment cost, fuel and O and M costs are the main parameters for technical and economic assessment of solar power plants. This analysis has shown that the Integrated Solar Combined Cycle System with 67 MW e solar field(ISCCS-67) is the most suitable plan for the first solar power plant in Iran. The Levelized Energy Costs of combined cycle and ISCCS-67 power plants would be equal if 49 million dollars of ISCCS-67 capital cost supplied by the international environmental organizations such as Global Environmental Facilities and World Bank. This study shows that an ISCCS-67 saves 59 million dollars in fuel consumption and reduces about 2.4 million ton in CO 2 emission during 30 years operating period. Increasing of steam turbine capacity by 50%, and 4% improvement in overall efficiency are other advantages of iSCCS-67 power plant. The LEC of ISCCS-67 is 10% and so 33% lower than the combined cycle and gas turbine, respectively, at the same capacity factor with consideration of environmental costs

  7. Setting Performance Standards for Technical and Nontechnical Competence in General Surgery.

    Science.gov (United States)

    Szasz, Peter; Bonrath, Esther M; Louridas, Marisa; Fecso, Andras B; Howe, Brett; Fehr, Adam; Ott, Michael; Mack, Lloyd A; Harris, Kenneth A; Grantcharov, Teodor P

    2017-07-01

    The objectives of this study were to (1) create a technical and nontechnical performance standard for the laparoscopic cholecystectomy, (2) assess the classification accuracy and (3) credibility of these standards, (4) determine a trainees' ability to meet both standards concurrently, and (5) delineate factors that predict standard acquisition. Scores on performance assessments are difficult to interpret in the absence of established standards. Trained raters observed General Surgery residents performing laparoscopic cholecystectomies using the Objective Structured Assessment of Technical Skill (OSATS) and the Objective Structured Assessment of Non-Technical Skills (OSANTS) instruments, while as also providing a global competent/noncompetent decision for each performance. The global decision was used to divide the trainees into 2 contrasting groups and the OSATS or OSANTS scores were graphed per group to determine the performance standard. Parametric statistics were used to determine classification accuracy and concurrent standard acquisition, receiver operator characteristic (ROC) curves were used to delineate predictive factors. Thirty-six trainees were observed 101 times. The technical standard was an OSATS of 21.04/35.00 and the nontechnical standard an OSANTS of 22.49/35.00. Applying these standards, competent/noncompetent trainees could be discriminated in 94% of technical and 95% of nontechnical performances (P < 0.001). A 21% discordance between technically and nontechnically competent trainees was identified (P < 0.001). ROC analysis demonstrated case experience and trainee level were both able to predict achieving the standards with an area under the curve (AUC) between 0.83 and 0.96 (P < 0.001). The present study presents defensible standards for technical and nontechnical performance. Such standards are imperative to implementing summative assessments into surgical training.

  8. Development of High-Performance Cast Crankshafts. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, Mark E [General Motors, Detroit, MI (United States)

    2017-03-31

    The objective of this project was to develop technologies that would enable the production of cast crankshafts that can replace high performance forged steel crankshafts. To achieve this, the Ultimate Tensile Strength (UTS) of the new material needs to be 850 MPa with a desired minimum Yield Strength (YS; 0.2% offset) of 615 MPa and at least 10% elongation. Perhaps more challenging, the cast material needs to be able to achieve sufficient local fatigue properties to satisfy the durability requirements in today’s high performance gasoline and diesel engine applications. The project team focused on the development of cast steel alloys for application in crankshafts to take advantage of the higher stiffness over other potential material choices. The material and process developed should be able to produce high-performance crankshafts at no more than 110% of the cost of current production cast units, perhaps the most difficult objective to achieve. To minimize costs, the primary alloy design strategy was to design compositions that can achieve the required properties with minimal alloying and post-casting heat treatments. An Integrated Computational Materials Engineering (ICME) based approach was utilized, rather than relying only on traditional trial-and-error methods, which has been proven to accelerate alloy development time. Prototype melt chemistries designed using ICME were cast as test specimens and characterized iteratively to develop an alloy design within a stage-gate process. Standard characterization and material testing was done to validate the alloy performance against design targets and provide feedback to material design and manufacturing process models. Finally, the project called for Caterpillar and General Motors (GM) to develop optimized crankshaft designs using the final material and manufacturing processing path developed. A multi-disciplinary effort was to integrate finite element analyses by engine designers and geometry-specific casting

  9. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-15

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident.

  10. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    International Nuclear Information System (INIS)

    1986-11-01

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident

  11. Technical feasibility and carbon footprint of biochar co-production with tomato plant residue.

    Science.gov (United States)

    Llorach-Massana, Pere; Lopez-Capel, Elisa; Peña, Javier; Rieradevall, Joan; Montero, Juan Ignacio; Puy, Neus

    2017-09-01

    World tomato production is in the increase, generating large amounts of organic agricultural waste, which are currently incinerated or composted, releasing CO 2 into the atmosphere. Organic waste is not only produced from conventional but also urban agricultural practices due recently gained popularity. An alternative to current waste management practices and carbon sequestration opportunity is the production of biochar (thermally converted biomass) from tomato plant residues and use as a soil amendment. To address the real contribution of biochar for greenhouse gas mitigation, it is necessary to assess the whole life cycle from the production of the tomato biomass feedstock to the actual distribution and utilisation of the biochar produced in a regional context. This study is the first step to determine the technical and environmental potential of producing biochar from tomato plant (Solanum lycopersicum arawak variety) waste biomass and utilisation as a soil amendment. The study includes the characterisation of tomato plant residue as biochar feedstock (cellulose, hemicellulose, lignin and metal content); feedstock thermal stability; and the carbon footprint of biochar production under urban agriculture at pilot and small-scale plant, and conventional agriculture at large-scale plant. Tomato plant residue is a potentially suitable biochar feedstock under current European Certification based on its lignin content (19.7%) and low metal concentration. Biomass conversion yields of over 40%, 50% carbon stabilization and low pyrolysis temperature conditions (350-400°C) would be required for biochar production to sequester carbon under urban pilot scale conditions; while large-scale biochar production from conventional agricultural practices have not the potential to sequestrate carbon because its logistics, which could be improved. Therefore, the diversion of tomato biomass waste residue from incineration or composting to biochar production for use as a soil amendment

  12. Using a plant health system framework to assess plant clinic performance in Uganda

    DEFF Research Database (Denmark)

    Danielsen, Solveig; Matsiko, Frank B.

    2016-01-01

    and expand, new analytical frameworks and tools are needed to identify factors influencing performance of services and systems in specific contexts, and to guide interventions. In this paper we apply a plant health system framework to assess plant clinic performance, using Uganda as a case study...... factors, influenced by basic operational and financial concerns, inter-institutional relations and public sector policies. Overall, there was a fairly close match between the plant health system attributes and plant clinic performance, suggesting that the framework can help explain system functioning....... A comparative study of plant clinics was carried out between July 2010 and September 2011 in the 12 districts where plant clinics were operating at that time. The framework enabled us to organise multiple issues and identify key features that affected the plant clinics. Clinic performance was, among other...

  13. Thermal performance of solar district heating plants in Denmark

    DEFF Research Database (Denmark)

    Furbo, Simon; Perers, Bengt; Bava, Federico

    2014-01-01

    The market for solar heating plants connected to district heating systems is expanding rapidly in Denmark. It is expected that by the end of 2014 the 10 largest solar heating plants in Europe will be located in Denmark. Measurements from 23 Danish solar heating plants, all based on flat plate solar...... collectors mounted on the ground, shows measured yearly thermal performances of the solar heating plants placed in the interval from 313 kWh/m² collector to 493 kWh/m² collector with averages for all plants of 411 kWh/m² collector for 2012 and 450 kWh/m² collector for 2013. Theoretical calculations show...... of the cost/performance ratio for solar collector fields, both with flat plate collectors and with concentrating tracking solar collectors. It is recommended to continue monitoring and analysis of all large solar heating plants to document the reliability of the solar heating plants. It is also recommended...

  14. STEPS: source term estimation based on plant status phase 0 - the technical specifications of the containment module

    International Nuclear Information System (INIS)

    Vamanu, D.V.

    1998-01-01

    In the framework of Project RODOS (Real-Time On-Line Decision Support System for Nuclear Emergencies in Europe), the European Atomic Energy Community (EAEC) of the Commission of the European Communities has commissioned the development of a unified concept, body of knowledge, models and software package meant to assist the evaluation of the source term of severe nuclear accidents in light water reactors of the types prevailing on the Continent. Code-named STEPS, for 'Source Term Estimation based on Plant Status', the project has evolved as Contract RODOS D (FI4P-CT96-0048), between EAEC and consortium of expert European centres including Commissariat a l'Energie Atomique, Institut de Protection et de Surete Nucleaire, (CEA-DPI-SEAC) as Coordinator and Forschungszentrum Karlsruhe GmbH (FZK-INR), the Finnish Centre for Radiation and Nuclear Safety, (STUK-NSD), the Technical Research Centre of Finland, Energy, Nuclear Energy (VTT-ET-NE), and Eidgenossische Technische Hochschule - ETH Zurich, Centre of Excellence (ETH-CERS) as Contractors. For the Phase 0 of the project, an IFIN-HH expert has been assigned by ETH-CERS to develop the Technical Specifications of the delivery component of the intended STEPS package, the CONTAINMENT Module. Sponsored by ETH-CERS headquarters in Zurich, the work was done on the premises and with the logistic support of CEA D PI-SEAC at Fontenay-aux-Roses, with the feedback processing and computer code development subsequently performed in Bucharest. The Technical Specifications of the STEPS CONTAINMENT Module were guided by specific terms of reference, including: (i) the capability of the software to function as a source term interface between targeted nuclear power plants and the RODOS System; (ii) the comparable capability of the system to be operated as a stand-alone assessment and decision support tool for a comprehensive variety of plants, nuclear emergency classes. On the technical side, the specifications had to focus on the possible

  15. Intelligent Facades for High Performance Green Buildings. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Dyson, Anna [Rensselaer Polytechnic Inst., Troy, NY (United States)

    2017-03-01

    Intelligent Facades for High Performance Green Buildings: Previous research and development of intelligent facades systems has been limited in their contribution towards national goals for achieving on-site net zero buildings, because this R&D has failed to couple the many qualitative requirements of building envelopes such as the provision of daylighting, access to exterior views, satisfying aesthetic and cultural characteristics, with the quantitative metrics of energy harvesting, storage and redistribution. To achieve energy self-sufficiency from on-site solar resources, building envelopes can and must address this gamut of concerns simultaneously. With this project, we have undertaken a high-performance building- integrated combined-heat and power concentrating photovoltaic system with high temperature thermal capture, storage and transport towards multiple applications (BICPV/T). The critical contribution we are offering with the Integrated Concentrating Solar Façade (ICSF) is conceived to improve daylighting quality for improved health of occupants and mitigate solar heat gain while maximally capturing and transferring on- site solar energy. The ICSF accomplishes this multi-functionality by intercepting only the direct-normal component of solar energy (which is responsible for elevated cooling loads) thereby transforming a previously problematic source of energy into a high- quality resource that can be applied to building demands such as heating, cooling, dehumidification, domestic hot water, and possible further augmentation of electrical generation through organic Rankine cycles. With the ICSF technology, our team is addressing the global challenge in transitioning commercial and residential building stock towards on-site clean energy self-sufficiency, by fully integrating innovative environmental control systems strategies within an intelligent and responsively dynamic building envelope. The advantage of being able to use the entire solar spectrum for

  16. Coaching Non-technical Skills Improves Surgical Residents' Performance in a Simulated Operating Room.

    Science.gov (United States)

    Yule, Steven; Parker, Sarah Henrickson; Wilkinson, Jill; McKinley, Aileen; MacDonald, Jamie; Neill, Adrian; McAdam, Tim

    2015-01-01

    To investigate the effect of coaching on non-technical skills and performance during laparoscopic cholecystectomy in a simulated operating room (OR). Non-technical skills (situation awareness, decision making, teamwork, and leadership) underpin technical ability and are critical to the success of operations and the safety of patients in the OR. The rate of developing assessment tools in this area has outpaced development of workable interventions to improve non-technical skills in surgical training and beyond. A randomized trial was conducted with senior surgical residents (n = 16). Participants were randomized to receive either non-technical skills coaching (intervention) or to self-reflect (control) after each of 5 simulated operations. Coaching was based on the Non-Technical Skills For Surgeons (NOTSS) behavior observation system. Surgeon-coaches trained in this method coached participants in the intervention group for 10 minutes after each simulation. Primary outcome measure was non-technical skills, assessed from video by a surgeon using the NOTSS system. Secondary outcomes were time to call for help during bleeding, operative time, and path length of laparoscopic instruments. Non-technical skills improved in the intervention group from scenario 1 to scenario 5 compared with those in the control group (p = 0.04). The intervention group was faster to call for help when faced with unstoppable bleeding in the final scenario (no. 5; p = 0.03). Coaching improved residents' non-technical skills in the simulated OR compared with those in the control group. Important next steps are to implement non-technical skills coaching in the real OR and assess effect on clinically important process measures and patient outcomes. Copyright © 2015 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  17. Utility experience using THERMAC for plant thermal performance analysis

    International Nuclear Information System (INIS)

    Jain, P.K.; Doran, K.J.

    1993-01-01

    THERMAC is a state-of-the-art software package designed to assist those responsible for monitoring and evaluating the thermal performance of fossil and nuclear power plants. It is an integrated program, available on PCs and selected workstations, that combines strong analytical capabilities with a graphical user interface and object-oriented database. The software accurately analyses all of the components of a power plant from first principles. The graphical user interface is employed to build plant specific models; it can also be used to create custom screen displays. THERMAC is able to read plant measurements and statistically account for any missing or erroneous plant data; it does not require any additional plant instrumentation. THERMAC can be used to archive historical data, generate customized trending plots and periodic performance reports. open-quotes What-if close-quote studies can be conducted to predict the impact of corrective actions on thermal performance

  18. Current status and technical description of Chinese 2 x 250 MWth HTR-PM demonstration plant

    International Nuclear Information System (INIS)

    Zhang Zuoyi; Wu Zongxin; Wang Dazhong; Xu Yuanhui; Sun Yuliang; Li Fu; Dong Yujie

    2009-01-01

    After the nuclear accidents of Three Mile Island and Chernobyl the world nuclear community made great efforts to increase research on nuclear reactors and to develop advanced nuclear power plants with much improved safety features. Following the successful construction and a most gratifying operation of the 10 MW th high-temperature gas-cooled test reactor (HTR-10), the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University has developed and designed an HTR demonstration plant, called the HTR-PM (high-temperature-reactor pebble-bed module). The design, having jointly been carried out with industry partners from China and in collaboration of experts worldwide, closely follows the design principles of the HTR-10. Due to intensive engineering and R and D efforts since 2001, the basic design of the HTR-PM has been finished while all main technical features have been fixed. A Preliminary Safety Analysis Report (PSAR) has been compiled. The HTR-PM plant will consist of two nuclear steam supply system (NSSS), so called modules, each one comprising of a single zone 250 MW th pebble-bed modular reactor and a steam generator. The two NSSS modules feed one steam turbine and generate an electric power of 210 MW. A pilot fuel production line will be built to fabricate 300,000 pebble fuel elements per year. This line is closely based on the technology of the HTR-10 fuel production line. The main goals of the project are two-fold. Firstly, the economic competitiveness of commercial HTR-PM plants shall be demonstrated. Secondly, it shall be shown that HTR-PM plants do not need accident management procedures and will not require any need for offsite emergency measures. According to the current schedule of the project the completion date of the demonstration plant will be around 2013. The reactor site has been evaluated and approved; the procurement of long-lead components has already been started. After the successful operation of the demonstration plant

  19. Shaking table test study on seismic performance of dehydrogenation fan for nuclear power plants

    International Nuclear Information System (INIS)

    Liu Kaiyan; Shi Weixing; Cao Jialiang; Wang Yang

    2011-01-01

    Seismic performance of the dehydrogenation fan for nuclear power plants was evaluated based on the shaking table test of earthquake simulation. Dynamic characteristics including the orthogonal tri-axial fundamental frequencies and equivalent damping ratios were measured by the white noise scanning method. Artificial seismic waves were generated corresponding to the floor acceleration response spectra for nuclear power plants. Furthermore, five OBE and one SSE shaking table tests for dehydrogenation fan were performed by using the artificial seismic waves as the seismic inputs along the orthogonal axis simultaneity. Operating function of dehydrogenation fan was monitored and observed during all seismic tests, and performance indexes of dehydrogenation fan were compared before and after seismic tests. The results show that the structural integrity and operating function of the dehydrogenation fan are perfect during all seismic tests; and the performance indexes of the dehydrogenation fan can remain consistent before and after seismic tests; the seismic performance of the dehydrogenation fan can satisfy relevant technical requirements. (authors)

  20. Power system technical performance issues related to the application of long HVAC cables

    DEFF Research Database (Denmark)

    Wiechowski, on behalf of Cigre WG C4.502, W.; Sluis, L. V. der; Ohno, Teruo

    2011-01-01

    This paper reports the progress of work of Cigre Working Group C4.502 “Power system technical performance issues related to the application of long HVAC cables”. The primary goal of the WG C4.502 is to write a technical brochure that will serve as practical guide for performing studies necessary...... for assessing the technical performance of HV/EHV systems with large share of AC cable lines. This paper besides providing a background for formulation of WG C4.502 and its overall aim, describes the tasks that were accomplished before the interim report was submitted to Study Committee C4 System Technical...... Performance in August 2010. The work in the WG is ongoing and final report will be ready according to the time schedule in 2012. The focus of this paper is in particular to show all issues related to system technical performance with assigned weights in terms of their importance and/or uniqueness for cable...

  1. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    International Nuclear Information System (INIS)

    Korsah, K.

    2001-01-01

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in

  2. Longitudinal Trend Analysis of Performance Indicators for South Carolina's Technical Colleges

    Science.gov (United States)

    Hossain, Mohammad Nurul

    2010-01-01

    This study included an analysis of the trend of performance indicators for the technical college sector of higher education in South Carolina. In response to demands for accountability and transparency in higher education, the state of South Carolina developed sector specific performance indicators to measure various educational outcomes for each…

  3. Performance Evaluation of Indian Technical Institutions Using PROMETHEE-GAIA Approach

    Science.gov (United States)

    Ranjan, Rajeev; Chakraborty, Shankar

    2015-01-01

    It has now become an important issue to evaluate the performance of technical institutions to develop better research and enrich the existing teaching processes. The results of such performance appraisal would serve as a reference point for decisions to choose a particular institution, hire manpower, and provide financial support for the…

  4. Power System Technical Performance Issues Related to the Application of Long HVAC Cables

    DEFF Research Database (Denmark)

    Bak, Claus Leth

    The aim of this TB is to serve as a practical guide for preparing models and performing studies necessary during the assessment of the technical performance of HV/EHV systems with a large share of (long) AC cables. The brochure follows all phases of planning and analysis of a typical underground...

  5. Evaluating and improving nuclear power plant operating performance

    International Nuclear Information System (INIS)

    1999-07-01

    This report aims to provide the basis for improvements in the understanding of nuclear power plants operation and ideas for improving future productivity. The purpose of the project was to identify good practices of operating performance at a few of the world's most productive plants. This report was prepared through a series of consultants meetings, a specialists meeting and an Advisory Group meeting with participation of experts from 23 Member States. The report is based on self-assessment of half a dozen plants that have been chosen as representatives of different reactor types in as many different countries, and the views and assessment of the participants on good practices influencing plant performance. Three main areas that influence nuclear power plant availability and reliability were identified in the discussions: (1) management practices, (2) personnel characteristics, and (3) working practices. These areas cover causes influencing plant performance under plant management control. In each area the report describes factors or good practices that positively influence plant availability. The case studies, presented in annexes, contain the plant self-assessment of areas that influence their availability and reliability. Six plants are represented in the case studies: (1) Dukovany (WWER, 1760 MW) in the Czech Republic; (2) Blayais (PWR, 3640 MW) in France; (3) Paks (WWER, 1840 MW) in Hungary; (4) Wolsong 1 (PHWR, 600 MW) in the Republic of Korea; (5) Trillo 1 (PWR, 1066 MW) in Spain; and (6) Limerick (BWR, 2220 MW) in the United States of America

  6. Evaluating and improving nuclear power plant operating performance

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report aims to provide the basis for improvements in the understanding of nuclear power plants operation and ideas for improving future productivity. The purpose of the project was to identify good practices of operating performance at a few of the world`s most productive plants. This report was prepared through a series of consultants meetings, a specialists meeting and an Advisory Group meeting with participation of experts from 23 Member States. The report is based on self-assessment of half a dozen plants that have been chosen as representatives of different reactor types in as many different countries, and the views and assessment of the participants on good practices influencing plant performance. Three main areas that influence nuclear power plant availability and reliability were identified in the discussions: (1) management practices, (2) personnel characteristics, and (3) working practices. These areas cover causes influencing plant performance under plant management control. In each area the report describes factors or good practices that positively influence plant availability. The case studies, presented in annexes, contain the plant self-assessment of areas that influence their availability and reliability. Six plants are represented in the case studies: (1) Dukovany (WWER, 1760 MW) in the Czech Republic; (2) Blayais (PWR, 3640 MW) in France; (3) Paks (WWER, 1840 MW) in Hungary; (4) Wolsong 1 (PHWR, 600 MW) in the Republic of Korea; (5) Trillo 1 (PWR, 1066 MW) in Spain; and (6) Limerick (BWR, 2220 MW) in the United States of America Figs, tabs

  7. A technical and financial analysis of two recuperated, reciprocating engine driven power plants. Part 1: Thermodynamic analysis

    International Nuclear Information System (INIS)

    Orbaiz, Pedro Jose; Brear, Michael J.

    2014-01-01

    Highlights: • A thermodynamic analysis of two recuperated ICE plants is undertaken. • The overall plant efficiency and CO 2 emissions are analysed. • Chemical recuperation without a secondary heat source is unlikely. • Using a renewable secondary heat source reduces the CO 2 emission of the plant. - Abstract: This paper is the first of a two part study that analyses the technical and financial performance of particular, recuperated engine systems. This first paper presents a thermodynamic study of two systems. The first system involves the chemical recuperation of a reciprocating, spark ignited, internal combustion engine using only the waste heat of the engine to power a steam–methane reformer. The performance of this system is evaluated for different coolant loads and steam–methane ratios. The second system is a so-called ’hybrid’ in which not only the waste heat of the engine is used, but also a secondary heat source – the combustion of biomass. The effects of the reformer’s temperature and the steam–methane ratio on the system performance are analysed. These analyses show that the potential efficiency improvement obtained when using only the engine waste heat to power the recuperation is marginal. However, results for the hybrid show that although the overall efficiency of the plant, defined in terms of the energy from both the methane and biomass, is similar to that of the conventional, methane fuelled engine, the efficiency of the conversion of the biomass fuel energy to work output appears to be higher than for other biomass fuelled technologies currently in use. Further, in the ideal limit of a fully renewable biomass fuel, the burning of biomass does not contribute to the net CO 2 emissions, and the CO 2 emission reduction for this second plant can be considerable. Indeed, its implementation on larger internal combustion engine power plants, which have efficiencies of around 45–50%, could result in CO 2 emissions that are as much as

  8. Comparative assessment of PV plant performance models considering climate effects

    DEFF Research Database (Denmark)

    Tina, Giuseppe; Ventura, Cristina; Sera, Dezso

    2017-01-01

    . The methodological approach is based on comparative tests of the analyzed models applied to two PV plants installed respectively in north of Denmark (Aalborg) and in the south of Italy (Agrigento). The different ambient, operating and installation conditions allow to understand how these factors impact the precision...... the performance of the studied PV plants with others, the efficiency of the systems has been estimated by both conventional Performance Ratio and Corrected Performance Ratio...

  9. PSA-based optimization of technical specifications for the Borssele nuclear power plant

    International Nuclear Information System (INIS)

    Seebregts, A.J.; Schoonakker, H.A.

    1996-01-01

    The Borssele Nuclear Power Plant (NPP) is a Siemens/KWU 472 MWe Pressurized Water Reactor which has been in operation since 1973. In 1989, a Probabilistic Safety Assessment (PSA) program was initiated to complement deterministic safety studies and operational experience in forming a plant safety concept. In 1993, the PSA-MER model was completed and used to determine the effects a package of proposed modifications would have on plant safety and risks to the environment. This model was used to start retrospective risks profile and allowed outage times (AOTs) analyses, which both concerned the calculation of the change in total core damage frequency (TCDF) given a change in configuration. The main problems identified and reported in this paper are: (i) How to calculate the change in TCDF (ΔTCDF)? (section 3); and (ii) How to set practical decision criteria and how to use the PSA as extension to Technical Specifications (TS) AOTs? (section 4). Finally, a pilot study was conducted in order to optimize surveillance test intervals (STIs) which are also part of the TS (section 5). (orig.)

  10. Technical and tactical skills related to performance levels in tennis: A systematic review.

    Science.gov (United States)

    Kolman, Nikki S; Kramer, Tamara; Elferink-Gemser, Marije T; Huijgen, Barbara C H; Visscher, Chris

    2018-06-11

    The aim of this systematic review is to provide an overview of outcome measures and instruments identified in the literature for examining technical and tactical skills in tennis related to performance levels. Such instruments can be used to identify talent or the specific skill development training needs of particular players. Searches for this review were conducted using the PubMed, Web of Science, and PsycInfo databases. Out of 733 publications identified through these searches, 40 articles were considered relevant and included in this study. They were divided into three categories: (1) technical skills, (2) tactical skills and (3) integrated technical and tactical skills. There was strong evidence that technical skills (ball velocity and to a lesser extent ball accuracy) and tactical skills (decision making, anticipation, tactical knowledge and visual search strategies) differed among players according to their performance levels. However, integrated measurement of these skills is required, because winning a point largely hinges on a tactical decision to perform a particular stroke (i.e., technical execution). Therefore, future research should focus on examining the relationship between these skills and tennis performance and on the development of integrated methods for measuring these skills.

  11. Morphological and maturational predictors of technical performance in young soccer players

    Directory of Open Access Journals (Sweden)

    Marcelo de Oliveira Matta

    2014-09-01

    Full Text Available The purpose of the present study is to describe the association between chronological age, morphology, biological maturation and sport experience in relation to technical performance in young Brazilian soccer players. Technical, maturation and anthropometric variables were assessed in 119 soccer players, 74 and 45 in the under-15 and under-17 categories, respectively. Data were analyzed using a multiple linear regression model. Adiposity was negatively associated with technical performance regardless the age-category. Weight was negatively associated with technical performance in under-15 and positively with the under-17 category, respectively. In under-17 biological maturation was negatively related to the dribbling test and positively associated with the ball control test. Years of experience proved to be positively associated with technique taught to soccer player in the under-17 category. The explained variance was different between categories. The technical performance of Brazilian soccer players aged 14-to-17 seems to be related to biological maturation, adiposity, weight and years of experience.

  12. Using international experience to improve performance of nuclear power plants

    International Nuclear Information System (INIS)

    Calori, F.; Csik, B.J.; Strickert, R.J.

    1989-01-01

    Information on performance achievements will assist nuclear power plant operating organizations to develop initiatives for improved or continued high performance of their plants. The paper describes the activities of the IAEA in reviewing and analysing the reasons for good performance by contacting operating organizations identified by its Power Reactor Information System as showing continued good performance. Discussions with operations personnel of utilities have indicated practices which have a major positive impact on good performance and which are generally common to all well performing organizations contacted. The IAEA also promotes further activities directed primarily to the achievement of standards of excellence in nuclear power operation. These are briefly commented

  13. Revisiting the utility of technical performance scores following tetralogy of Fallot repair.

    Science.gov (United States)

    Lodin, Daud; Mavrothalassitis, Orestes; Haberer, Kim; Sunderji, Sherzana; Quek, Ruben G W; Peyvandi, Shabnam; Moon-Grady, Anita; Karamlou, Tara

    2017-08-01

    Although an important quality metric, current technical performance scores may not be generalizable and may omit operative factors that influence outcomes. We examined factors not included in current technical performance scores that may contribute to increased postoperative length of stay, major complications, and cost after primary repair of tetralogy of Fallot. This is a retrospective single site study of patients younger than age 2 years with tetralogy of Fallot undergoing complete repair between 2007 and 2015. Medical record data and discharge echocardiograms were reviewed to ascertain component and composite technical performance scores. Primary outcomes included postoperative length of stay, major complications, and total hospital costs. Multivariable logistic and linear regression identified determinants of each outcome. Patient population (n = 115) had a median postoperative length of stay of 8 days (interquartile range, 6-10 days), and a median total cost of $71,147. Major complications occurred in 33 patients (29%) with 1 death. Technical performance scores assigned were optimum in 28 patients (25%), adequate in 59 patients (52%), and inadequate in 26 patients (23%). Neither technical performance score components nor composite scores were associated with increased postoperative length of stay. Optimum or adequate repairs versus inadequate had equal risk of a complication (P = .79), and equivalent mean total cost ($100,000 vs $187,000; P = .25). Longer cardiopulmonary bypass time per 1-minute increase (P technical performance scores were not associated with selected outcomes in our postoperative population. Although returning to bypass and bypass length are not included as components in the current score, these are important factors influencing complications and resource use in our population. Revisions anticipated from a prospective trial should consider including these variables. Copyright © 2017 The American Association for Thoracic Surgery

  14. Combined effects of arthropod herbivores and phytopathogens on plant performance

    DEFF Research Database (Denmark)

    Hauser, Thure Pavlo; Christensen, Stina; Heimes, Christine

    2013-01-01

    1. Many plants are simultaneously attacked by arthropod herbivores and phytopathogens. These may affect each other directly and indirectly, enhancing or reducing the amount of plant resources they each consume. Ultimately, this may reduce or enhance plant performance relative to what should...... be expected from the added impacts of herbivore and pathogen when they attack alone. 2. Previous studies have suggested synergistic and antagonistic impacts on plant performance from certain combinations of arthropods and pathogens, for example, synergistic impacts from necrotrophic pathogens together...... with wounding arthropods because of facilitated infection and antagonistic impacts from induction of pathogen resistance by sucking herbivores. 3. We compiled published studies on the impact of plant–herbivore–pathogen interactions on plant performance and used meta-analysis to search for consistent patterns...

  15. Test of job performance aids for power plants. Final report

    International Nuclear Information System (INIS)

    Shriver, E.L.; Zach, S.E.; Foley, J.P. Jr.

    1982-10-01

    The objective of EPRI Research Project 1396-1 was to evaluate the applicability and effectiveness of Job Performance Aids (JPAs) in nuclear power plant situations. For over twenty years, JPAs have been developed in military situations to meet the problems of confusing, incomplete, and inaccurate procedures on maintenance jobs. Kinton, Incorporated of Alexandria, Virginia applied the military experience with JPAs to nuclear power plant situations and identified potential benefits in terms of cost reductions and improved performance. Sample JPAs were developed for Control Room Operations, Maintenance, Plant Operations, Instrumentation and Control, Health Physics, and Quality Assurance tasks (procedures) in selected nuclear plants. JPAs were also developed for a prototype condenser tube leak detection system in the design stage, as well as for generic classes of circuit breaker equipment. Based on the results of the study, the use of JPAs is recommended for plant procedures of medium to high difficulty and for those tasks performed infrequently, even if fairly simple

  16. Safe Operation of Nuclear Power Plants. Code of Practice and Technical Appendices

    International Nuclear Information System (INIS)

    1969-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Nuclear Power Plants and the second part is a compilation of technical appendices. Its object is to give information and illustrative examples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. Safe operation of a nuclear power plant postulates suitable siting and proper design, construction and management of the plant. Under the present Code of Practice for the Safe Operation of Nuclear Power Plants, those intending to operate the plant are recommended to prepare documentation which would deal with its operation and include safety analyses. The documentation in question would be reviewed by a regulatory body independent of the operating organization; operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code may be subject to revision in the light of experience. The Appendices provide additional information together with some examples relating to certain topics dealt with in the Code; it must be emphasized that they are included as examples for information only and are not part of any recommendation. Purpose and scope: The recommendations in the Code are designed to protect the general public and the operating personnel from radiation hazards, and the Code forms part of the Agency's Safety Standards. The Code, which should be used in conjunction with the Agency's other Safety Standards, provides guidance and information to persons and authorities responsible for the operation of stationary nuclear power plants whose main function is the generation of thermal, mechanical or electrical power; it is not intended to apply to reactors used solely for experimental or research purposes. It sets forth minimum requirements which, it is believed, in the light of experience, must be met in order to achieve safe operation of a

  17. Performance of technical trading rules: evidence from Southeast Asian stock markets.

    Science.gov (United States)

    Tharavanij, Piyapas; Siraprapasiri, Vasan; Rajchamaha, Kittichai

    2015-01-01

    This paper examines the profitability of technical trading rules in the five Southeast Asian stock markets. The data cover a period of 14 years from January 2000 to December 2013. The instruments investigated are five Southeast Asian stock market indices: SET index (Thailand), FTSE Bursa Malaysia KLC index (Malaysia), FTSE Straits Times index (Singapore), JSX Composite index (Indonesia), and PSE composite index (the Philippines). Trading strategies investigated include Relative Strength Index, Stochastic oscillator, Moving Average Convergence-Divergence, Directional Movement Indicator and On Balance Volume. Performances are compared to a simple Buy-and-Hold. Statistical tests are also performed. Our empirical results show a strong performance of technical trading rules in an emerging stock market of Thailand but not in a more mature stock market of Singapore. The technical trading rules also generate statistical significant returns in the Malaysian, Indonesian and the Philippine markets. However, after taking transaction costs into account, most technical trading rules do not generate net returns. This fact suggests different levels of market efficiency among Southeast Asian stock markets. This paper finds three new insights. Firstly, technical indicators does not help much in terms of market timing. Basically, traders cannot expect to buy at a relative low price and sell at a relative high price by just using technical trading rules. Secondly, technical trading rules can be beneficial to individual investors as they help them to counter the behavioral bias called disposition effects which is the tendency to sell winning stocks too soon and holding on to losing stocks too long. Thirdly, even profitable strategies could not reliably predict subsequent market directions. They make money from having a higher average profit from profitable trades than an average loss from unprofitable ones.

  18. EFFECT OF DATE OF PLANTING ON THE PERFORMANCE OF ...

    African Journals Online (AJOL)

    BSN

    KEY WORDS: Date of Planting, Performance, Groundnut, haulm, yield, grain yield. ... Adamawa State, groundnuts have the highest tonnage among the legumes cultivated and ranks ... germination because of moisture stress) and such planting continues till the ..... variations in temperature and solar radiation intercepted.

  19. Performance of PWR Nuclear power plants, up to 1985

    International Nuclear Information System (INIS)

    Muniz, A.A.

    1987-01-01

    The performance of PWR nuclear power plants is studied, based on operational data up to 1985. The availability analysis was made with 793 unit-year and the reliability analysis was made with 5851 unit x month. The results were discussed and the availability of those nuclear power plants were estimated. (E.G.) [pt

  20. Standard Technical Specifications General Electric plants, BWR/4:Bases (Sections 3.4-3.10). Volume 3, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the specifications for all chapters and sections of the improved STS. Volume 2 contains he Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4-3.10 of the improved STS

  1. Standard technical specifications: Combustion engineering plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  2. Standard technical specifications: Babcock and Wilcox plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock and Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  3. Standard Technical Specifications General Electric plants, BWR/4: Bases (Sections 2.0-3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved ST or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume I contains the Specifications for all chapters and sections of the improved STS. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4-3.10 of the improved STS

  4. Operating trends and performance of nuclear power plants in IAEA member states

    International Nuclear Information System (INIS)

    Galori, F.

    1984-01-01

    The present status and short-term development of nuclear power programmes in IAEA member states is reviewed. A description of the IAEA Power Reactor Information System (PRIS) is given and the objectives for data collection and treatment are discussed. As indicated by the reports at the IAEA International Conference on Nuclear Power experience in 1982, there are considerable differences in the performances of nuclear power plants even within classes of plants which technically should be very similar and thus perform equally well. PRIS permist at least some preliminary conclusions about the reasons for differences to be drawn. It is becoming clear that reasons for good or bad performance must be sought in a number of factors including: type of plant (on-load/off-load refuelling, GCR, PHWR, LWR); age and vintage of plant; manufacturer of the main plant system; degree of standardization in plant and construction; competence of operating organization; regulatory climate. Analysis of the reported outages shows that major problems are: stress corrosion cracking in primary piping, also denting and wall thinning in tubes of steam generators; thermal fatigue cracking in the feedwater system and excessive errosion/corrosion problems in turbines. It is emphasized that international cooperation is important for creating an effective system for learning from operating experience

  5. Using plant status data for off-site emergency management: Technical and political aspects

    International Nuclear Information System (INIS)

    Govaerts, P.

    2004-01-01

    Subsequent to the TMI and Chernobyl accidents, emergency management is investigating the possibility of taking balanced decisions on interventions as early as possible. This process relies more and more on in-plant data to assess the term of releases. The paper discusses the regulatory aspects of the communication related to the source term between the utility and the national authorities, and the authorities of a host country and neighbouring countries that may be affected. The technical aspects of the assessment process are summarised, with the emphasis on the handling of uncertainties. Notwithstanding the technical progress, the main dilemma for the decision makers remains the same. Risk management and prevention measures become more familiar to authorities. Utilities and national authorities have to get rid of complexes with respect to accidents covered by the accepted residual risk. International emergency management has to look for an organisation type ensuring the continuity of countermeasures independent of the presence of administrative borders, and with respect to national autonomies. (authors)

  6. Technical and economical analysis of concepts for using the heat of biogas plants in rural areas

    International Nuclear Information System (INIS)

    Kaths, Friederike Annette

    2012-08-01

    Since the implementation of the EEG in Germany the biogas production becomes an independent branch of industry in the agriculture. At this time more than 90 percent of the biogas plants work with co-generation plant for heat and power with a thermal engine efficiencies of more than 50 percent. Because of the location in the rural area heat costumers with a continuous demand of heat over the whole year are rare. This research had a closer look how to use the heat of biogas production efficiently and also generating profit. The aim of the study was to use heat over the whole year, a profitable heat concept without counting the KWK-bonus and an added value on the farm. During the study the following concepts were analyzed: asparagus production using soil heating, drying equipment for different products, the production of fish in aquaculture, the poultry production and the heated production of tomatoes. The results showed different concepts using heat of biogas plants as efficient for farmers. However with only one concept the aims - to use the heat over the whole year, generating a profitable heat concept without counting the KWK-bonus, add an value on the farm - mostly can not be achieved. The combination of different heat concepts is necessary. In this analysis the poultry production in combination with the dryer can be considered as the most efficient concept. Bearing in mind the benefit which can be generated with a heat concept as well as the higher income and the higher technical efficiency of biogas plants operators should implement an individual concept for their heat.

  7. Cost and performance of fossil fuel power plants with CO2 capture and storage

    International Nuclear Information System (INIS)

    Rubin, Edward S.; Chen, Chao; Rao, Anand B.

    2007-01-01

    CO 2 capture and storage (CCS) is receiving considerable attention as a potential greenhouse gas (GHG) mitigation option for fossil fuel power plants. Cost and performance estimates for CCS are critical factors in energy and policy analysis. CCS cost studies necessarily employ a host of technical and economic assumptions that can dramatically affect results. Thus, particular studies often are of limited value to analysts, researchers, and industry personnel seeking results for alternative cases. In this paper, we use a generalized modeling tool to estimate and compare the emissions, efficiency, resource requirements and current costs of fossil fuel power plants with CCS on a systematic basis. This plant-level analysis explores a broader range of key assumptions than found in recent studies we reviewed for three major plant types: pulverized coal (PC) plants, natural gas combined cycle (NGCC) plants, and integrated gasification combined cycle (IGCC) systems using coal. In particular, we examine the effects of recent increases in capital costs and natural gas prices, as well as effects of differential plant utilization rates, IGCC financing and operating assumptions, variations in plant size, and differences in fuel quality, including bituminous, sub-bituminous and lignite coals. Our results show higher power plant and CCS costs than prior studies as a consequence of recent escalations in capital and operating costs. The broader range of cases also reveals differences not previously reported in the relative costs of PC, NGCC and IGCC plants with and without CCS. While CCS can significantly reduce power plant emissions of CO 2 (typically by 85-90%), the impacts of CCS energy requirements on plant-level resource requirements and multi-media environmental emissions also are found to be significant, with increases of approximately 15-30% for current CCS systems. To characterize such impacts, an alternative definition of the 'energy penalty' is proposed in lieu of the

  8. Thermal diagnostics in power plant to improve performance

    International Nuclear Information System (INIS)

    Meister, H.

    1995-01-01

    The improvement of older power plants by changing poor performing components is a cost effective method to increase the capacity of the units. The necessary information for the detection of components that are to be replaced can be obtained from heat rate and component tests with accuracy instrumentation. The discussed methods and tools provided by ABB Were used with success in several power plants in Europe. These tools are in the process of permanent improvement and can be used in almost any type of power plant. Due to the reasons discussed above, there is a high potential for improvement of a lot of power plants in the next decade. (author)

  9. The performance of plant species in removing nutrients from ...

    African Journals Online (AJOL)

    2011-10-26

    Oct 26, 2011 ... but offered no explicit guidance about how these water quality targets might be achieved. ... the limited knowledge that exists about the performance of local plant ...... reuse: designing biofiltration systems for reliable treatment.

  10. Objective indicators of organizational performance at nuclear power plants

    International Nuclear Information System (INIS)

    Olson, J.; Osborn, R.N.; Jackson, D.H.; Shikiar, R.

    1986-01-01

    This report summarizes research conducted on the development and validation of organizational performance measures at operating nuclear power plants. Publicly available data, including measures from Licensee Event Reports, operating and outage data, and violations data, are used to predict penultimate measures of plant safety. Penultimate measures of safety include potentially significant events, overexposures and near overexposures, and several radiological release measures. The 1981 and 1982 performance measures are used in correlation and regression analyses to predict performance on the penultimate safety measures in 1982 and 1983. Many of the plant performance measures are consistently predictive of the frequency of potentially significant events. No strong, consistent predictors emerge for exposures or liquid radiological releases. Several performance measures are consistent predictors of gaseous releases. The regression analyses indicate that the predictors do not tend to combine in consistent, multivariate patterns, and controls for plant age, size, type, region, and fuel cycle stage do not substantially affect the results. The analysis concludes that existing performance data do appear to be predictive of some aspects of plant safety performance. The report recommends that more reliable, summary performance measures be created by combining several of the performance measures tested in the current analysis

  11. Technical Performance as a Predictor of Clinical Outcomes in Laparoscopic Gastric Cancer Surgery.

    Science.gov (United States)

    Fecso, Andras B; Bhatti, Junaid A; Stotland, Peter K; Quereshy, Fayez A; Grantcharov, Teodor P

    2018-03-23

    The purpose of this study was to evaluate the relationship between technical performance and patient outcomes in laparoscopic gastric cancer surgery. Laparoscopic gastrectomy for cancer is an advanced procedure with high rate of postoperative morbidity and mortality. Many variables including patient, disease, and perioperative management factors have been shown to impact postoperative outcomes; however, the role of surgical performance is insufficiently investigated. A retrospective review was performed for all patients who had undergone laparoscopic gastrectomy for cancer at 3 teaching institutions between 2009 and 2015. Patients with available, unedited video-recording of their procedure were included in the study. Video files were rated for technical performance, using Objective Structured Assessments of Technical Skills (OSATS) and Generic Error Rating Tool instruments. The main outcome variable was major short-term complications. The effect of technical performance on patient outcomes was assessed using logistic regression analysis with backward selection strategy. Sixty-one patients with available video recordings were included in the study. The overall complication rate was 29.5%. The mean Charlson comorbidity index, type of procedure, and the global OSATS score were included in the final predictive model. Lower performance score (OSATS ≤29) remained an independent predictor for major short-term outcomes (odds ratio 6.49), while adjusting for comorbidities and type of procedure. Intraoperative technical performance predicts major short-term outcomes in laparoscopic gastrectomy for cancer. Ongoing assessment and enhancement of surgical skills using modern, evidence-based strategies might improve short-term patient outcomes. Future work should focus on developing and studying the effectiveness of such interventions in laparoscopic gastric cancer surgery.

  12. The performance of a Solar Aided Power Generation plant with diverse “configuration-operation” combinations

    International Nuclear Information System (INIS)

    Qin, Jiyun; Hu, Eric; Nathan, Graham J.

    2016-01-01

    Highlights: • Four configurations of solar preheaters have been proposed. • Three typical operation strategies of solar preheaters have been identified. • 12 “configuration-operation” combinations has been proposed. • There are superior combinations to achieve the highest solar thermal performance. - Abstract: Solar Aided Power Generation is an efficient way to integrate solar thermal energy into a fossil fuel fired power plant for solar power generation purposes. In this particular power plant, the solar heat is used to displace the extraction steam to preheat the feedwater to the boiler. The heat exchanger, which facilitates the heat exchange between the solar heat carried by the heat transfer fluid and the feedwater, is termed a solar preheater. Four possible configurations of the solar preheater, namely Parallel 1, Parallel 2, Series 1 and Series 2, are proposed in this paper. In this type of plant, the extraction steam flow rates must be adjusted according to the solar input. The ways to control the extraction steam flow rates are termed solar preheater operation strategies. Three typical strategies: the Constant Temperature control, Variable Temperature control with high to low temperature feedwater heater displacement and Variable Temperature control with low to high temperature feedwater heater displacement have been identified. Each configuration can be operated with one of the three strategies, resulting in twelve “configuration-operation” combinations/scenarios (shown in Table 1). Previous assessments and modelling of such a plant have only been based on a single combination. In this paper, a Solar Aided Power Generation plant, modified from a typical 300 MW power plant, is used to understand the plant’s performance for all twelve of the available combinations. The results show that the instantaneous and annual technical performances of such a plant are dependent on the combinations used. The scenario 10 (Table 1) is superior to the

  13. BALTICA IV. Plant maintenance for managing life and performance

    Energy Technology Data Exchange (ETDEWEB)

    Hietanen, S.; Auerkari, P. [eds.] [VTT Manufacturing Technology, Espoo (Finland). Operational Reliability

    1998-12-31

    BALTICA IV International Conference on Plant Maintenance Managing Life and performance held on September 7-9, 1998 on board M/S Silja Symphony on its cruise between Helsinki-Stockholm and at Aavaranta in Kirkkonummi. The BALTICA IV conference provides a forum for the transfer of technology from applied research to practice. This is one of the two volumes of the proceedings of the BALTICA IV International Conference on Plant Maintenance Managing Life and Performance. The BALTICA IV conference focuses on new technology, recent experience and applications of condition and life management, and on improvements in maintenance strategies for safe and economical operation of power plants. (orig.)

  14. BALTICA IV. Plant maintenance for managing life and performance

    Energy Technology Data Exchange (ETDEWEB)

    Hietanen, S; Auerkari, P [eds.; VTT Manufacturing Technology, Espoo (Finland). Operational Reliability

    1999-12-31

    BALTICA IV International Conference on Plant Maintenance Managing Life and performance held on September 7-9, 1998 on board M/S Silja Symphony on its cruise between Helsinki-Stockholm and at Aavaranta in Kirkkonummi. The BALTICA IV conference provides a forum for the transfer of technology from applied research to practice. This is one of the two volumes of the proceedings of the BALTICA IV International Conference on Plant Maintenance Managing Life and Performance. The BALTICA IV conference focuses on new technology, recent experience and applications of condition and life management, and on improvements in maintenance strategies for safe and economical operation of power plants. (orig.)

  15. Regulatory surveillance of safety related maintenance at nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-08-01

    The operational safety and reliability of a nuclear power plant as well as its availability for electricity generation depend on, among other things, its maintenance programme. Regulatory bodies therefore have considerable interest in maintenance activities. There are several approaches to maintenance, i.e. reliability centered maintenance or risk focused maintenance, aimed at optimizing maintenance by focusing on important components or systems. These approaches may result in significant changes to maintenance activities and therefore have to be considered for regulatory acceptance. In order to review and discuss the status of maintenance regulation in participating countries, the IAEA convened a Technical Committee Meeting on Regulatory Oversight of Maintenance Activities at Nuclear Power Plants in Vienna from 9 to 13 October 1995. The meeting was attended by 16 experts from 11 countries. In addition to the consideration of papers that were presented and which are reproduced here, extensive group and panel discussions took place during the meeting. These covered three main topics: general features and basic characteristics of maintenance regulation, regulatory acceptance of maintenance optimization and use of PSA for maintenance optimization. The discussion are summarized in Section 2. Section 3 discusses the following three additional topics: regulatory involvement in the maintenance programme, modifications to the maintenance programme and personnel related aspects of maintenance. The conclusions are presented in Section 4. Figs, tabs

  16. Reviewing PSA-based analyses to modify technical specifications at nuclear power plants

    International Nuclear Information System (INIS)

    Samanta, P.K.; Martinez-Guridi, G.; Vesely, W.E.

    1995-12-01

    Changes to Technical Specifications (TSs) at nuclear power plants (NPPs) require review and approval by the United States Nuclear Regulatory Commission (USNRC). Currently, many requests for changes to TSs use analyses that are based on a plant's probabilistic safety assessment (PSA). This report presents an approach to reviewing such PSA-based submittals for changes to TSs. We discuss the basic objectives of reviewing a PSA-based submittal to modify NPP TSs; the methodology of reviewing a TS submittal, and the differing roles of a PSA review, a PSA Computer Code review, and a review of a TS submittal. To illustrate this approach, we discuss our review of changes to allowed outage time (AOT) and surveillance test interval (STI) in the TS for the South Texas Project Nuclear Generating Station. Based on this experience gained, a check-list of items is given for future reviewers; it can be used to verify that the submittal contains sufficient information, and also that the review has addressed the relevant issues. Finally, recommended steps in the review process and the expected findings of each step are discussed

  17. Advanced Flue Gas Desulfurization (AFGD) demonstration project: Volume 2, Project performance and economics. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-30

    The project objective is to demonstrate removal of 90--95% or more of the SO{sub 2} at approximately one-half the cost of conventional scrubbing technology; and to demonstrate significant reduction of space requirements. In this project, Pure Air has built a single SO{sub 2} absorber for a 528-MWe power plant. The absorber performs three functions in a single vessel: prequencher, absorber, and oxidation of sludge to gypsum. Additionally, the absorber is of a co- current design, in which the flue gas and scrubbing slurry move in the same direction and at a relatively high velocity compared to conventional scrubbers. These features all combine to yield a state- of-the-art SO{sub 2} absorber that is more compact and less expensive than conventional scrubbers. The project incorporated a number of technical features including the injection of pulverized limestone directly into the absorber, a device called an air rotary sparger located within the base of the absorber, and a novel wastewater evaporation system. The air rotary sparger combines the functions of agitation and air distribution into one piece of equipment to facilitate the oxidation of calcium sulfite to gypsum. Additionally, wastewater treatment is being demonstrated to minimize water disposal problems inherent in many high-chloride coals. Bituminous coals primarily from the Indiana, Illinois coal basin containing 2--4.5% sulfur were tested during the demonstration. The Advanced Flue Gas Desulfurization (AFGD) process has demonstrated removal of 95% or more of the SO{sub 2} while providing a commercial gypsum by-product in lieu of solid waste. A portion of the commercial gypsum is being agglomerated into a product known as PowerChip{reg_sign} gypsum which exhibits improved physical properties, easier flowability and more user friendly handling characteristics to enhance its transportation and marketability to gypsum end-users.

  18. Reactor shutdown: nuclear power plant performance

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The article essentially looks at the performance of nine of Sweden's nuclear reactors. A table lists the percentage of time for the first three quarters of 1981 that the reactors were operating, and the number of hours out of service for planned or other reasons. In particular, one station - Ringhals 3 - was out of action because of a damaged tube in the associated steam generator. The same fault occurred with another reactor - Ringhals 4 - before this was brought into service. The reasons for the failure and its importance are briefly discussed. (G.P.)

  19. Performance evaluation and economic analysis of a gas turbine power plant in Nigeria

    International Nuclear Information System (INIS)

    Oyedepo, S.O.; Fagbenle, R.O.; Adefila, S.S.; Adavbiele, S.A.

    2014-01-01

    plant. From technical point of view, performance of the plant can be improved by retrofitting with a gas turbine air inlet cooling system, heat recovery system or adding modifications (inter-cooling or regeneration) to the simple gas turbine units

  20. A socio-technical system framework for risk-informed performance-based building regulation

    NARCIS (Netherlands)

    Meacham, B.J.; Straalen, IJ.J. van

    2017-01-01

    Building regulatory systems have been evolving in recent decades, first with a transition to a functional or performance basis, and more recently with the introduction of new societal objectives, including those related to sustainability and climate change resiliency. Various policy and technical

  1. Investigating Aerobic, Anaerobic Combine Technical Trainings' Effects on Performance in Tennis Players

    Science.gov (United States)

    Suna, Gürhan; Kumartasli, Mehmet

    2017-01-01

    The aim of this study is to investigate eight-week aerobic, anaerobic combine technical trainings' effects on developments of performance. 21 athletes of tennis proficiency students from Sports Sciences Department were joined to the study voluntarily. Participated in the research athletes' ages' mean was 22,2 ± 0,3 year, lengths' mean was 177,3 ±…

  2. Effect of obstetric team training on team performance and medical technical skills: a randomised controlled trial

    NARCIS (Netherlands)

    Fransen, A. F.; van de Ven, J.; Merién, A. E. R.; de Wit-Zuurendonk, L. D.; Houterman, S.; Mol, B. W.; Oei, S. G.

    2012-01-01

    Please cite this paper as: Fransen A, van de Ven J, Merien A, de Wit-Zuurendonk L, Houterman S, Mol B, Oei S. Effect of obstetric team training on team performance and medical technical skills: a randomised controlled trial. BJOG 2012;119:13871393. Objective To determine whether obstetric team

  3. Influence of Students’ Mental and Physical Performance on Development of Technical and Tactical Skills in Fencing

    Directory of Open Access Journals (Sweden)

    І. В. Кривенцова

    2016-04-01

    Full Text Available Study objective: to reveal the relations between the indicators of physical and mental performance and the development of technical and tactical skills in fencers, to determine the significant criteria and tests for selecting students for health-improving and sports fencing groups. Methods: study and analysis of literature; pedagogical observations; physiological methods (physical performance by the Harvard step test with HSTI (Harvard step test Index calculation, mental performance by the correction tables, special exercises to assess fencers’ technical and tactical skills; statistical methods. The reference group students (9 female fencers had five workouts a week, the students (13 female students of test group 1 (TG1 had 2 hours of physical training per week, the TG2 and TG3  (8 and 10 female students respectively had 4 hours of fencing workouts per week. The TG2 had 4 months of fencing experience, and TG3 had one year and 4 months thereof. Results. The reciprocal effects of the performance indicators and the correlation between the indicators of technical and tactical skills of the student fencers allowed to establish the informative value of individual indicators for quality selection of students for the fencing group. The Harvard step test index and the standardized number of errors of the correction test can serve as the prognostic criteria for developing technical and tactical skills in student fencing.

  4. Mental Health and Academic Performance among Associate Degree Nursing Students at a Technical College

    Science.gov (United States)

    Kliminski, Kerri

    2017-01-01

    The purpose of this non-experimental cross-sectional quantitative study was to examine the relationship between mental health and academic performance among associate degree nursing (ADN) students at a Midwest technical college by identifying incidence of positive mental health, mental illness symptoms/distress, and mental illness; the…

  5. Technical Performance Measurement, Earned Value, and Risk Management: An Integrated Diagnostic Tool for Program Management

    National Research Council Canada - National Science Library

    Pisano, N

    2002-01-01

    ...(A)), is known as the Navy PEO(A) Technical Performance Measurement (TPM) System. A retrospective analysis was conducted on the T45TS Cockpit-21 program and real-time test implementations are being conducted on the Federal Aviation Administration's (FAA...

  6. Performance of simulated flexible integrated gasification polygeneration facilities. Part A: A technical-energetic assessment

    NARCIS (Netherlands)

    Meerman, J.C.; Ramírez Ramírez, C.A.; Turkenburg, W.C.; Faaij, A.P.C.

    2011-01-01

    This article investigates technical possibilities and performances of flexible integrated gasification polygeneration (IG-PG) facilities equipped with CO2 capture for the near future. These facilities can produce electricity during peak hours, while switching to the production of chemicals during

  7. Annual meeting on nuclear technology '85. Technical session on nuclear power plant simulators. Jahrestagung Kerntechnik '85. Fachsitzung Simulatoren bei Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    The ten lectures read at this Technical Session deal with nuclear power plant simulators and their functions for the training of control room personnel, with test facilities for analysis and simulation of incidents and the relevant plant behaviour, and with the computer codes for fast simulation of reactor processes. The papers explain in particular the HAMMLAB project, the COSIMA fast core simulator, and the OPAL simulator for the KWU convoy process information system named PRINS.

  8. Technical basis for beta skin dose calculations at the Y-12 Plant

    International Nuclear Information System (INIS)

    Thomas, J.M.; Bogard, R.S.

    1994-03-01

    This report describes the methods for determining shallow dose equivalent to workers at the Oak Ridge Y-12 Plant from skin contamination detected by survey instrumentation. Included is a discussion of how the computer code VARSKIN is used to calculate beta skin dose and how the code input parameters affect skin dose calculation results. A summary of Y-12 Plant specific assumptions used in performing VARSKIN calculations is presented. Derivations of contamination levels that trigger the need for skin dose assessment are given for both enriched and depleted uranium with the use of Y-12 Plant site-specific survey instruments. Department of Energy recording requirements for nonuniform exposure of the skin are illustrated with sample calculations

  9. Education and research when dismantling nuclear plants at the Technical University Dresden

    International Nuclear Information System (INIS)

    Hurtado, A.; Anthofer, A.; Cloppenborg, T.; Schreier, M.

    2013-01-01

    With the decision by the German government in 2011 to revoke the operating permission from 8 of the existing 17 German nuclear power plants, the responsibility of decommissioning and dismantling these plants has moved back into the focus of public awareness. Under the current legal conditions, the last nuclear plant will be disconnected from the grid on 31.12.2022 and this will create an enormous challenge for all the involved approving authorities, expert organisations, as well as companies involved in dismantling the plants. The development of new and efficient dismantling technologies and strategies is required to perform these highly responsible tasks. On the other hand, the nuclear competence and knowhow, as well as the promotion of young talents in the relevant scientific fields must be preserved. Technological and economic solutions are in demand for the various plants due to the different specifics of nuclear power plants. This will still require e.g. in the field of radiation protection highly qualified and well trained staff in future. The training of these skilled employees will require expanding the subject matter taught at universities, colleges and polytechnics to suit the changed parameters. The chair for hydrogen and nuclear energy technology at the TU Dresden will in future offer lectures as part of a new teaching discipline with the focus on dismantling and disposal. The course 'Dismantling nuclear power plants' took place for the first time in the summer semester 2013. It is organised as a three-day block seminar with an excursion to the company NIS Ingenieurgesellschaft mbH in Alzenau. The company NIS is a subsidiary of the Siempelkamp Nukleartechnik GmbH. This article intends to provide an overview of the contents of the courses and the impressions of the participants. In this way the TU Dresden is making a further contribution to preserving nuclear competence and inter-disciplinary dialogue. (orig.)

  10. Performance of nuclear power plants in 1981

    International Nuclear Information System (INIS)

    Szeless, A.

    1982-01-01

    The performance data, such as yearly and cumulative load and operation (availability) factors for 200 reactor units worldwide and for 158 reactor units in the US and Europe, indicates that the average of the load factors of all units in 1981 was significantly higher than that of the 2 preceding years. However, it was not as high as in 1978. As in previous years, load factors continued to show an increasing trend as operating years increased. For 1981, the load factor of US reactors was 57%; that of world reactors was 60%. The operation (availability) factors were 63% for US reactors, 68% for world reactors, 76% for heavy water reactors, and 72% for gas-cooled reactors

  11. Establishment of the technical basis for applying viscous dampers to nuclear power plants

    International Nuclear Information System (INIS)

    Narahara, Yukiko; Higuchi, Tomokazu; Katayama, Hiroshi; Ito, Ryo; Hattori, Kiyoshi; Nakajima, Jun

    2017-01-01

    For the purpose of introducing viscous dampers to nuclear power plants, the damping characteristic of the viscous damper under specific conditions in nuclear power plants was examined. In particular the seismic response analysis method, the design evaluation method, and the maintenance and management guideline were studied. In the viscous dampers characteristic test, the damping characteristics under earthquake motion and the environmental condition of nuclear power plants have been examined. From the test results, if the parameters such as vibration amplitude, vibration frequency, repeated load, temperature, and radiation are considered, there is a possibility of viscous damper application to components in nuclear power plants. In order to evaluate the applicability of the complex modal analysis method using response spectrum, comparison with the time history response analysis result was performed using a PWR steam generator analysis model. The evaluation result from the complex modal analysis method was in good agreement with the time history response analysis result, and the availability of this method was confirmed. From the test results, considerations in design and maintenance in the case of applying viscous dampers to nuclear power plants were selected. The bases of the design evaluation method and the maintenance and management guideline were developed. (author)

  12. Standard technical specifications - Babcock and Wilcox Plants: Bases (Sections 2.0-3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the B ampersand W Owners Group (BWOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

  13. Risk management: A tool for improving nuclear power plant performance

    International Nuclear Information System (INIS)

    2001-04-01

    This technical document on risk management as a tool for improving nuclear power plant (NPP) operations is part of an ongoing project on management of NPP operations in a competitive environment. The overall objective of this project is to assist the management of operating organizations and NPPs in identifying and implementing appropriate measures to remain competitive in a rapidly changing business environment. Other reports developed through this project have identified overall strategies and techniques that NPP operating organization managers can use to succeed in more competitive energy markets. For example, in IAEA-TECDOC-1123, Strategies for Competitive Nuclear Power Plants, one of the most important strategies identified was integrated risk management. This publication provides a recommended structure for risk management along with examples of how NPP operating organizations are using this tool to help them integrate safety, operational and economic related risks in a changing business environment

  14. Technical tips to perform safe and effective ultrasound guided steroid joint injections in children.

    Science.gov (United States)

    Parra, Dimitri A

    2015-01-01

    The aim of this article is to describe the technique used to perform ultrasound guided steroid joint injections in children in a group of joints that can be injected using ultrasound as the only image guidance modality. The technique is described and didactic figures are provided to illustrate key technical concepts. It is very important to be familiar with the sonographic appearance of the pediatric joints and the developing bone when performing ultrasound-guided joint injections in children.

  15. Evaluation of systems interactions in nuclear power plants: Technical findings related to Unresolved Safety Issue A-17

    International Nuclear Information System (INIS)

    Thatcher, D.

    1989-05-01

    This report presents a summary of the activities related to Unresolved Safety Issue (USI)A-17, ''Systems Interactions in Nuclear Power Plants,'' and also includes the NRC staff's conclusions based on those activities. The staff's technical findings provide the framework for the final resolution of this unresolved safety issue. The final resolution will be published later as NUREG-1229. 52 refs., 4 tabs

  16. Technical Efficiency and Organ Transplant Performance: A Mixed-Method Approach

    Science.gov (United States)

    de-Pablos-Heredero, Carmen; Fernández-Renedo, Carlos; Medina-Merodio, Jose-Amelio

    2015-01-01

    Mixed methods research is interesting to understand complex processes. Organ transplants are complex processes in need of improved final performance in times of budgetary restrictions. As the main objective a mixed method approach is used in this article to quantify the technical efficiency and the excellence achieved in organ transplant systems and to prove the influence of organizational structures and internal processes in the observed technical efficiency. The results show that it is possible to implement mechanisms for the measurement of the different components by making use of quantitative and qualitative methodologies. The analysis show a positive relationship between the levels related to the Baldrige indicators and the observed technical efficiency in the donation and transplant units of the 11 analyzed hospitals. Therefore it is possible to conclude that high levels in the Baldrige indexes are a necessary condition to reach an increased level of the service offered. PMID:25950653

  17. Twelve tips for assessing surgical performance and use of technical assessment scales

    DEFF Research Database (Denmark)

    Strandbygaard, Jeanett; Scheele, Fedde; Sørensen, Jette Led

    2017-01-01

    Using validated assessment scales for technical competence can help structure and standardize assessment and feedback for both the trainee and the supervisor and thereby avoid bias and drive learning. Correct assessment of operative skills can establish learning curves and allow adequate monitoring....... However, the assessment of surgical performance is not an easy task, since it includes many proxy parameters, which are hard to measure. Although numerous technical assessment scales exist, both within laparoscopic and open surgery, the validity evidence is often sparse, and this can raise doubts about...... reliability and educational outcome. Furthermore, the implementation of technical assessment scales varies due to several obstacles and doubts about accurate use. In this 12-tips article, we aim to give the readers a critical and useful appraisal of some of the common questions and misunderstandings regarding...

  18. Technical match characteristics and influence of body anthropometry on playing performance in male elite team handball.

    Science.gov (United States)

    Michalsik, Lars Bojsen; Madsen, Klavs; Aagaard, Per

    2015-02-01

    Modern team handball match-play imposes substantial physical and technical demands on elite players. However, only limited knowledge seems to exist about the specific working requirements in elite team handball. Thus, the purpose of this study was to examine the physical demands imposed on male elite team handball players in relation to playing position and body anthropometry. Based on continuous video recording of individual players during elite team handball match-play (62 tournament games, ∼4 players per game), computerized technical match analysis was performed in male elite team handball players along with anthropometric measurements over a 6 season time span. Technical match activities were distributed in 6 major types of playing actions (shots, breakthroughs, fast breaks, tackles, technical errors, and defense errors) and further divided into various subcategories (e.g., hard or light tackles, type of shot, claspings, screenings, and blockings). Players showed 36.9 ± 13.1 (group mean ± SD) high-intense technical playing actions per match with a mean total effective playing time of 53.85 ± 5.87 minutes. In offense, each player performed 6.0 ± 5.2 fast breaks, received 34.5 ± 21.3 tackles in total, and performed in defense 3.7 ± 3.5 blockings, 3.9 ± 3.0 claspings, and 5.8 ± 3.6 hard tackles. Wing players (84.5 ± 5.8 kg, 184.9 ± 5.7 cm) were less heavy and smaller (p handball match-play is characterized by a high number of short-term, high-intense intermittent technical playing actions. Indications of technical fatigue were observed. Physical demands differed between playing positions with wing players performing more fast breaks and less physical confrontations with opponent players than backcourt players and pivots. Body anthropometry seemed to have an important influence on playing performance because it is highly related to playing positions. The present observations suggest that male elite team handball players should implement more position

  19. Draft Technical Position Subtask 1.1: waste package performance after repository closure. Volume 1

    International Nuclear Information System (INIS)

    Davis, M.S.; Schweitzer, D.G.

    1983-08-01

    This document provides guidance to the DOE on the issues and information necessary for the NRC to evaluate waste package performance after repository closure. Minimal performance objectives of the waste package are required by proposed 10 CFR 60. This Draft Technical Position describes the various options available to the DOE for compliance and discusses advantages and disadvantages of various choices. Examples are discussed dealing with demonstrability, predictability and reasonable assurance. The types of performance are considered. The document summarizes presently identified high priority issues needed to evaluate waste package performance after repository closure. 20 references, 7 tables

  20. World-class outage performance of the Olkiluoto nuclear power plant

    International Nuclear Information System (INIS)

    Paavola, M.

    1998-01-01

    The production of the Olkiluoto power plant units covered 17% of the electricity consumption in Finland in 1997; the total share of nuclear energy was 27% of the electricity consumed in the country. Based on Finnish experience, nuclear energy is a safe, environmentally friendly and economic way to produce electricity provided that the plants and their personnel are well taken care of. TVO's policy is to keep the plant units in good condition and technically modern. This requires continuous investments in the plant. In maintenance, attention is paid to monitoring the condition of the plant and to preventive maintenance aiming at avoiding disturbances in production. TVO has chosen continuous development as the operational line develops the plant by annual investments and performs the necessary modifications during planned annual outages trying to avoid long production interruptions. The load factors of the Olkiluoto nuclear power plant have been high. The average load factor during the last decade was over 93%. The most significant single factor in the production deficits is the amount or electricity, which has not been produced because of the annual outages. Due to this, special attention has been paid to the performance of the annual outages. TVO aims at continuous development of the annual outage procedure. A centralized task management system makes it possible to perform simultaneously more tasks than before. The company has also invested in equipment and systems, which ease and speed up servicing. Normal outage length varies between 10 and 16 days. By keeping the plant units as modern as possible and in good condition we facilitate reaching TVO's target, which is also stated in TVO's slogan 'always 40 years lifetime'. (author)

  1. Performance of Canadian commercial nuclear units and heavy water plants

    International Nuclear Information System (INIS)

    Woodhead, L.W.; Ingolfsrud, L.J.

    The operating history of Canadian commercial CANDU type reactors, i.e. Pickering generating station-A, is described. Capacity factors and unit energy costs are analyzed in detail. Equipment performance highlights are given. The performance of the two Canadian heavy water plants is described and five more are under construction or planned. (E.C.B.)

  2. Performance of Generating Plant: New Metrics for Industry in Transition

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-09-15

    This report is the result of the work of the Performance of Generating Plant task force of the World Energy Council. The report examines the challenges of measuring and improving performance and considers some of the issues related to this field.

  3. IMPROVEMENT OF SYSTEMS OF TECHNICAL WATER SUPPLY WITH COOLING TOWERS FOR HEAT POWER PLANTS TECHNICAL AND ECONOMIC INDICATORS PERFECTION. Part 2

    Directory of Open Access Journals (Sweden)

    Yu. A. Zenovich-Leshkevich-Olpinskiy

    2016-01-01

    Full Text Available The method of calculation of economic efficiency that can be universal and is suitable for feasibility study of modernization of irrigation and water distribution system of cooling towers has been developed. The method takes into account the effect of lower pressure exhaust steam in the condenser by lowering the temperature of the cooling water outlet of a cooling tower that aims at improvement of technical and economic indicators of heat power plants. The practical results of the modernization of irrigation and water distribution system of a cooling tower are presented. As a result, the application of new irrigation and water distribution systems of cooling towers will make it possible to increase the cooling efficiency by more than 4 оС and, therefore, to obtain the fuel savings by improving the vacuum in the turbine condensers. In addition, the available capacity of CHP in the summer period is increased. The results of the work, the experience of modernization of irrigation and water distribution systems of the Gomel CHP-2 cooling towers system, as well as the and methods of calculating of its efficiency can be disseminated for upgrading similar facilities at the power plants of the Belarusian energy system. Some measures are prosed to improve recycling systems, cooling towers and their structures; such measures might significantly improve the reliability and efficiency of technical water supply systems of heat power plants.

  4. Factors associated to performance efficacy of technical-tactical actions in volleyball

    Directory of Open Access Journals (Sweden)

    William das Neves Salles

    2017-05-01

    Full Text Available DOI: http://dx.doi.org/10.5007/1980-0037.2017v19n1p74   The aim of the study was to investigate the factors associated to performance efficacy of technical-tactical actions in volleyball. Based on the protocol of the Instrument for Technical and Tactical Performance Assessment in Volleyball (IAD-VB, 44.025 match actions performed by male and female athletes from u-15, u-16 and u-17 finalist teams of the 2010 Santa Catarina Volleyball Championship in Brazil were observed. Data were analyzed on SPPS 21 software using the logistic regression technique, adopting 5% significance level for the interpretation of results. Adjusted model explained 51.40% efficacy variance, and the factors associated with this variable were decision making, adjustment, efficiency, and competition level.

  5. Performance measures for aging of nuclear power plants

    International Nuclear Information System (INIS)

    Ross, D.F. Jr.

    1993-01-01

    The Nuclear Power Plant licenses are granted by the US Nuclear Regulatory Commission (NRC) for a 40-year term. There is at present consideration being given to extending the authorized service lifetime beyond that, perhaps for a total of 60 or 70 years total. A logical concern for such a length of operation is whether the plant ages in such a way as to be significantly less safe as it gets older. As a corollary to this, there would be the question as to how to measure a diminution in plant safety. Each operating utility has, of course, ways to observe the plant performance. It has maintenance and surveillance programs which are used for this purpose. The NRC maintains a presence at each operating plant in the form of resident inspectors. The NRC also receives utility reports which may then be used to synthesize operating performance. It also reviews plant performance directly through what is known as the Systematic Assessment of Licensee Performance (SALP). In the paper the various data management programs used by the NRC will be described. The results of each program is presented, and observations are made as to the potential effect of age on safety performance. It is also necessary to define the size of the population being examined. There are at present 109 operating reactors. The age distribution is used to normalize the data. Some of the indicators discussed in this paper are concerned more with the indirect effect of aging, such as inadvertent shutdown. The regulated industry maintains a program known as the Nuclear Power Reliability Data System (NPRDS) to which the electric utilities participate in a voluntary manner. Data from NPRDS can be accessed to observe the direct aging effect; this is not covered in this paper. To the degree that plant operating staff learns how to cope with aging equipment and operate in a safe manner nonetheless, the performance indicators would not fully reflect the aging effect

  6. Technical Performance Analysis of Iran Premier League Soccer Players in 2012-2013 Season

    Directory of Open Access Journals (Sweden)

    Javani Mohsen

    2015-10-01

    Full Text Available Background and purpose of study : analysis of IRAN premier league soccer players’ technical performance in season 2012-2013, using a computerized match analysis system (Borhan Mobin Development Management Co, IRAN. Material and methods: in this study, data were obtained from 120 players, who performed in competitions 90 minutes. The players were classified into 3 positional roles: defenders, midfielders and forwards. Technical performance variables analysis included: total passes, total successful passes, pass accuracy, total shots; total shots to target, shot accuracy, ball interception and ball losses. The data were statistically analyzed by one-way ANOVA, Kruskal-Wallis, Mann-Whitney U and Tukey post hoc test. Results : The findings of this study showed that players performed about 45 passes per competition. Midfielders and defenders had significantly higher number of passes than forwards. Pass accuracy was about 67% and there were no significant differences between positional roles. Also, the players performed about 0.8 shots per competition, forwards and midfielders had significantly higher number of shots than defenders. Shot accuracy was about 31%; midfielders and forwards had significantly higher shot accuracy than defenders. Forwards showed significantly lower ball interception and higher ball losses than other positions. Conclusion : The result of this study showed that there were significant differences between some technical actions in positional roles. Therefore, coaches can use this information for individualization of training according to playing positions and for optimization of training in the amateur game.

  7. Exploring the use of internal and externalcontrols for assessing microarray technical performance

    Directory of Open Access Journals (Sweden)

    Game Laurence

    2010-12-01

    Full Text Available Abstract Background The maturing of gene expression microarray technology and interest in the use of microarray-based applications for clinical and diagnostic applications calls for quantitative measures of quality. This manuscript presents a retrospective study characterizing several approaches to assess technical performance of microarray data measured on the Affymetrix GeneChip platform, including whole-array metrics and information from a standard mixture of external spike-in and endogenous internal controls. Spike-in controls were found to carry the same information about technical performance as whole-array metrics and endogenous "housekeeping" genes. These results support the use of spike-in controls as general tools for performance assessment across time, experimenters and array batches, suggesting that they have potential for comparison of microarray data generated across species using different technologies. Results A layered PCA modeling methodology that uses data from a number of classes of controls (spike-in hybridization, spike-in polyA+, internal RNA degradation, endogenous or "housekeeping genes" was used for the assessment of microarray data quality. The controls provide information on multiple stages of the experimental protocol (e.g., hybridization, RNA amplification. External spike-in, hybridization and RNA labeling controls provide information related to both assay and hybridization performance whereas internal endogenous controls provide quality information on the biological sample. We find that the variance of the data generated from the external and internal controls carries critical information about technical performance; the PCA dissection of this variance is consistent with whole-array quality assessment based on a number of quality assurance/quality control (QA/QC metrics. Conclusions These results provide support for the use of both external and internal RNA control data to assess the technical quality of microarray

  8. Method discussion of the performance evaluation on nuclear plant cable

    International Nuclear Information System (INIS)

    Lu Yongfang; Zhong Weixia; Sun Jiansheng; Liu Jingping

    2014-01-01

    A stock cable, which is same as the nuclear plant cable in service, was treated by thermal aging. After that, the mechanical property, the flame retardant property, the anti-oxidation were measured, and relationships between them due to the thermal aging were established. By those analysis, evaluating the in-service cable performance in nuclear plant and calculating its remaining life. Furthermore, the feasibility of this method was disscussed. (authors)

  9. Towards assuring the continued performance of safety-related concrete structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.; Mori, Y.; Arndt, E.G.

    1993-01-01

    The Structural Aging (SAG) Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. Pertinent concrete structures are described in terms of their importance, design considerations, and materials of construction. Degradation factors which can potentially impact the ability of these structures to meet their functional and performance requirements are identified. A review of the performance history of the concrete components in nuclear power plants is provided. Accomplishments of the SLAG Program are summarized, i.e., development of the structural materials information center, development of a structural aging assessment methodology, evaluation of models for predicting the remaining life of in-service concrete, review of in-service inspection methods, and development of a methodology for reliability-based condition assessment and life prediction of concrete structures. On-going activities are also described

  10. A technical pilot plant assessment of flue gas desulfurisation in a circulating fluidised bed

    Energy Technology Data Exchange (ETDEWEB)

    Gutierrez, F.J.; Ollero, P. [Universidad de Sevilla (Spain). Dept. de Ingenieria Quimica y Ambiental; Cabanillas, A.; Otero, J. [Centro de Investigaciones Energeticas y Medioambientales, (CIEMAT), Madrid (Spain)

    2002-11-01

    Flue gas desulfurisation in a circulating fluidised bed absorber (CFBA) is quite a novel dry desulfurisation technology [6th International Conference on Circulating Fluidised Beds (1999) 601] that shows significant advantages in comparison with other dry technologies and that could also be competitive with the widely-used wet FGD technology. This experimental study analyses the performance of a flue gas treatment plant comprising a CFBA and an electrostatic precipitator (ESP). The most significant aspects considered in this study are: the effect of precollecting the fly ash, the effect of the SO{sub 2} inlet concentration, the effect of power plant load changes, the contribution of the final particulate control equipment to the overall SO{sub 2} removal efficiency and the impact of the desulfurisation unit on the ESP behaviour and its final dust emissions. In addition, the behaviour of the integrated CFBA-ESP system with respect to the main operating parameters was studied by means of a fractional factorial design of experiments. All this experimental work was carried out in a 3-MWe equivalent pilot plant that processes real gases withdrawn from the Los Barrios Power Plant. Processing a flue gas with up to 2000 ppm SO{sub 2} concentration, a sulfur removal of 95-97% with a lime utilisation of 75% was achieved. A simple regression model to evaluate the efficiency of the whole system is also proposed.(author)

  11. Nuclebras' installations for performance tests of nuclear power plants components

    International Nuclear Information System (INIS)

    Vasconcelos Paiva, I.P. de; Avelar Esteves, F. de; Horta, J.A.L.; Resende, M.F.R.; Pinheiro, R.B.

    1984-01-01

    The reasons for Nuclebras' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufactures, giving to them the means for performing functional tests of industrial products, are presented. A brief description of facilities under construction: the components Test Loop and Facility for Testing N.P.P. components under Accident conditions, and other already in operation, as well as its objectives and main technical characteristics. Some test results had already obtained are also presented. (Author) [pt

  12. Technical and economical feasibility study of a sewage sludge disinfection plants by irradiation process

    International Nuclear Information System (INIS)

    Rojas Bustos, Gustavo

    1999-01-01

    This report presents a technical and economical evaluation for a disinfection plant of sewage sludge based on irradiation. The process starts after sludge stabilization which is achieved by anaerobic digestion. It includes two stages, plus an optional: the first corresponds to dewatering of sewage sludge up to a solids content between 20 and 25 %, the second stage corresponds to disinfection by gamma or electron beam irradiation, and the third, which is optional, corresponds to the drying of sewage sludge up to a water content of 50%, which allows to diminish significantly the volumes of solids to be transported. If this stage is not accomplished the final product corresponds to a sewage sludge with 25 % of dry solids, which can also be disposed in agricultural land. Process was designed to treat 60 tons per day of sewage sludge (dry matter basis). The report presents the design of process equipment, principal and auxiliary, the investment and operational cost estimations as well as the total cost of treatment per ton of sewage sludge. A sensitivity analysis is also included to determine the influence of operational process parameters in operational and investment costs. The results showed that a sewage sludge plant including dewatering and disinfection process through gamma irradiation, achieves a capital investment of about US$ 12.000.000 with a treatment cost per ton of dry sludge of US$140. Including the optional air-drying stage, the total cost of treatment is about US$148 per ton of dry matter. In the case of electron beam irradiation the capital investment achieves a value of US$ 11 millions with a total treatment cost of US$ 136 per ton of dry matter. These values resulted quite similar to the cost of alternative treatment, i.e., disposal in a dedicated landfill. (L.V.)

  13. Mental Fatigue: Impairment of Technical Performance in Small-Sided Soccer Games.

    Science.gov (United States)

    Badin, Oliver O; Smith, Mitchell R; Conte, Daniele; Coutts, Aaron J

    2016-11-01

    To assess the effects of mental fatigue on physical and technical performance in small-sided soccer games. Twenty soccer players (age 17.8 ± 1.0 y, height 179 ± 5 cm, body mass 72.4 ± 6.8 kg, playing experience 8.3 ± 1.4 y) from an Australian National Premier League soccer club volunteered to participate in this randomized crossover investigation. Participants played 15-min 5-vs-5 small-sided games (SSGs) without goalkeepers on 2 occasions separated by 1 wk. Before the SSG, 1 team watched a 30-min emotionally neutral documentary (control), while the other performed 30 min of a computer-based Stroop task (mental fatigue). Subjective ratings of mental and physical fatigue were recorded before and after treatment and after the SSG. Motivation was assessed before treatment and SSG; mental effort was assessed after treatment and SSG. Player activity profiles and heart rate (HR) were measured throughout the SSG, whereas ratings of perceived exertion (RPEs) were recorded before the SSG and immediately after each half. Video recordings of the SSG allowed for notational analysis of technical variables. Subjective ratings of mental fatigue and effort were higher after the Stroop task, whereas motivation for the upcoming SSG was similar between conditions. HR during the SSG was possibly higher in the control condition, whereas RPE was likely higher in the mental-fatigue condition. Mental fatigue had an unclear effect on most physical-performance variables but impaired most technical-performance variables. Mental fatigue impairs technical but not physical performance in small-sided soccer games.

  14. Performance and Simulation of a Stand-alone Parabolic Trough Solar Thermal Power Plant

    Science.gov (United States)

    Mohammad, S. T.; Al-Kayiem, H. H.; Assadi, M. K.; Gilani, S. I. U. H.; Khlief, A. K.

    2018-05-01

    In this paper, a Simulink® Thermolib Model has been established for simulation performance evaluation of Stand-alone Parabolic Trough Solar Thermal Power Plant in Universiti Teknologi PETRONAS, Malaysia. This paper proposes a design of 1.2 kW parabolic trough power plant. The model is capable to predict temperatures at any system outlet in the plant, as well as the power output produced. The conditions that are taken into account as input to the model are: local solar radiation and ambient temperatures, which have been measured during the year. Other parameters that have been input to the model are the collector’s sizes, location in terms of latitude and altitude. Lastly, the results are presented in graphical manner to describe the analysed variations of various outputs of the solar fields obtained, and help to predict the performance of the plant. The developed model allows an initial evaluation of the viability and technical feasibility of any similar solar thermal power plant.

  15. A systematic approach to human performance improvement in nuclear power plants: Training solutions

    International Nuclear Information System (INIS)

    2001-03-01

    In 1996, the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation: A Guidebook. This publication provides guidance with respect to development, implementation and evaluation of training programmes for all NPP personnel. The IAEA International Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared that provided further details concerning the training of NPP personnel on non-technical or soft skills. This report has been prepared in response to that recommendation. In the past, much of the focus of formal NPP training and development programmes was on the technical skills of NPP personnel, particularly those of control room operators. The environment in which NPPs operate is continually changing, placing new demands on NPP personnel to work more efficiently and effectively while continuing to maintain the high levels of safety required of NPPs. In this report, an integrated approach that considers training along with other ways to achieve desired levels of human performance is suggested

  16. A systematic approach to human performance improvement in nuclear power plants: Training solutions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    In 1996, the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation: A Guidebook. This publication provides guidance with respect to development, implementation and evaluation of training programmes for all NPP personnel. The IAEA International Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared that provided further details concerning the training of NPP personnel on non-technical or soft skills. This report has been prepared in response to that recommendation. In the past, much of the focus of formal NPP training and development programmes was on the technical skills of NPP personnel, particularly those of control room operators. The environment in which NPPs operate is continually changing, placing new demands on NPP personnel to work more efficiently and effectively while continuing to maintain the high levels of safety required of NPPs. In this report, an integrated approach that considers training along with other ways to achieve desired levels of human performance is suggested.

  17. Plant safety and performance indicators for regulatory use

    International Nuclear Information System (INIS)

    Ferjancic, M.; Nemec, T.; Cimesa, S.

    2004-01-01

    Slovenian Nuclear Safety Administration (SNSA) supervises nuclear and radiological safety of Krsko NPP. This SNSA supervision is performed through inspections, safety evaluations of plant modifications and event analyses as well as with the safety and performance indicators (SPI) which are a valuable data source for plant safety monitoring. In the past SNSA relied on the SPI provided by Krsko NPP and did not have a set of SPI which would be more appropriate for regulatory use. In 2003 SNSA started with preparation of a new set of SPI which would be more suitable for performing the regulatory oversight of the plant. New internal SNSA procedure which is under preparation will define use and evaluation of SPI and will include definitions for the proposed set of SPI. According to the evaluation of SPI values in comparison with the limiting values and/or trending, the procedure will define SNSA response and actions. (author)

  18. Bayesian calibration of power plant models for accurate performance prediction

    International Nuclear Information System (INIS)

    Boksteen, Sowande Z.; Buijtenen, Jos P. van; Pecnik, Rene; Vecht, Dick van der

    2014-01-01

    Highlights: • Bayesian calibration is applied to power plant performance prediction. • Measurements from a plant in operation are used for model calibration. • A gas turbine performance model and steam cycle model are calibrated. • An integrated plant model is derived. • Part load efficiency is accurately predicted as a function of ambient conditions. - Abstract: Gas turbine combined cycles are expected to play an increasingly important role in the balancing of supply and demand in future energy markets. Thermodynamic modeling of these energy systems is frequently applied to assist in decision making processes related to the management of plant operation and maintenance. In most cases, model inputs, parameters and outputs are treated as deterministic quantities and plant operators make decisions with limited or no regard of uncertainties. As the steady integration of wind and solar energy into the energy market induces extra uncertainties, part load operation and reliability are becoming increasingly important. In the current study, methods are proposed to not only quantify various types of uncertainties in measurements and plant model parameters using measured data, but to also assess their effect on various aspects of performance prediction. The authors aim to account for model parameter and measurement uncertainty, and for systematic discrepancy of models with respect to reality. For this purpose, the Bayesian calibration framework of Kennedy and O’Hagan is used, which is especially suitable for high-dimensional industrial problems. The article derives a calibrated model of the plant efficiency as a function of ambient conditions and operational parameters, which is also accurate in part load. The article shows that complete statistical modeling of power plants not only enhances process models, but can also increases confidence in operational decisions

  19. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  20. Three technical issues in fatigue damage assessment of nuclear power plant components

    International Nuclear Information System (INIS)

    Ware, A.G.; Shah, V.N.

    1991-01-01

    This paper addresses three technical issues that affect the fatigue damage assessment of nuclear power plant components: the effect of the environment on the fatigue life, the importance of the loading sequence in calculating the fatigue crack-initiation damage, and the adequacy of current inservice inspection requirements and methods to characterize fatigue cracks. The environmental parameters that affect the fatigue life of carbon and low alloy steel components are the sulphur content in the steel, the temperature, the amount of dissolved oxygen in the coolant, and the presence of oxidizing agents such as copper oxide. The occurrence of large-amplitude stress cycles early in a component's life followed by low-amplitude stress cycles may cause crack initiation at a cumulative usage factor less than 1.0. The current inservice inspection requirements include volumetric inspections of welds but not of some susceptible sites in the base metal. In addition, the conventional ultrasonic testing techniques need to be improved for reliable detection and accurate sizing of fatigue cracks. 28 refs., 4 figs., 1 tab

  1. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  2. Interim technical evaluation report of testing procedures for activated carbon adsorbers in ventilation filter assemblies in nuclear power plants

    International Nuclear Information System (INIS)

    Sill, C.W.; Scarpellino, C.D.; Tkachyk, J.W.; Grey, A.E.; Frank, C.W.

    1985-05-01

    Laboratory analysis of activated carbon is required by nuclear power plant technical specifications for use in Engineered Safety Feature (ESF) ventilation systems to determine the capability of those systems to remove radioiodines from air during normal operation and following a design basis accident (DBA). The lask of agreement of laboratory results from a recent round robin raised concerns regarding the adequacy of the analyses, using the ASTM D3803-79 standard, to assure compliance with plant technical specifications. EG and G Idaho was contracted by the NRC to conduct a program to provide the bases for resolving these concerns. This EG and G report serves as an interim Technical Evaluation Report (TER) of the program and presents reviews of the ASTM D3803-79 standard and the commercial testing laboratories. Results of EG and G laboratory studies and the NRC/EG and G Interlaboratory Comparison are presented with conclusions and recommendations concerning changes required to improve the standard and its application. Possible revisions to plant technical specifications required to reflect the true capability of activated carbon to remove radioiodines are also presented

  3. Technical Survey on Applications of Wireless Sensor Networks in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jiang, Jin; Bari, Ataul; Chen, Dongyi; Hashemian, Hash M.

    2014-01-01

    Even though there is no general consensus on using wireless technologies in nuclear power plants, potential applications of wireless sensor networks within nuclear power plants (NPPs) has been investigated. The topics of interests include potential interaction of wireless sensor networks with the sensitive protection equipment, radiation damage of the electronics on board sensor nodes, optimal placement of relay nodes that collect and forward data in the network, and possible applications, such as radiation dose and level monitoring, and equipment condition monitoring. Several wireless sensor networks have been deployed on site of NPPs on a trial basis to perform these tasks. Different aspects of deployment of such wireless sensor networks in NPPs have also been examined. Industrial standards or guidelines for deployment of WSNs in NPPs are also been considered. This paper examines the state of the art of wireless sensor networks in NPPs

  4. Technical Survey on Applications of Wireless Sensor Networks in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jiang, Jin; Bari, Ataul [University of Western Ontario, Ontario (Canada); Chen, Dongyi [University of Electronic Science and Technology of China, Chengdu (China); Hashemian, Hash M. [AMS Technology Center, Knoxville (United States)

    2014-08-15

    Even though there is no general consensus on using wireless technologies in nuclear power plants, potential applications of wireless sensor networks within nuclear power plants (NPPs) has been investigated. The topics of interests include potential interaction of wireless sensor networks with the sensitive protection equipment, radiation damage of the electronics on board sensor nodes, optimal placement of relay nodes that collect and forward data in the network, and possible applications, such as radiation dose and level monitoring, and equipment condition monitoring. Several wireless sensor networks have been deployed on site of NPPs on a trial basis to perform these tasks. Different aspects of deployment of such wireless sensor networks in NPPs have also been examined. Industrial standards or guidelines for deployment of WSNs in NPPs are also been considered. This paper examines the state of the art of wireless sensor networks in NPPs.

  5. Technical and tactical performance indicators based on the outcome of the set in the school volleyball

    Directory of Open Access Journals (Sweden)

    Yago Pessoa da Costa

    2017-09-01

    Full Text Available The aim of the study was to identify and compare the technical and tactical performance indicators based on the outcome of the set in the school female volleyball. The study included 110 athletes, aged between 12 and 14 years, belonging to 11 teams. Fifty-eight sets of 28 games were filmed and 7194 actions, 2830 serves, 2157 serve reception, 1358 passes and 1299 attacks were analyzed. Afterwards, the game sets were divided into winners and losers sets. Teams that won the sets had advantage at the serve reception, set and attack on error and excellence/point criteria (p< 0.05 and of serve, set and attack (p< 0.001. In conclusion, the winner’s sets were those with a better technical-tactical performance quantitatively and qualitatively.

  6. Development of a quantitative evaluation method for non-technical skills preparedness of operation teams in nuclear power plants to deal with emergency conditions

    International Nuclear Information System (INIS)

    Yim, Ho Bin; Kim, Ar Ryum; Seong, Poong Hyun

    2013-01-01

    Highlights: ► We selected important non-technical skills for emergency conditions in NPPs. ► We proposed an evaluation method for the selected non-technical skills. ► We conducted two sets of training, 9 experiments each, with real plant operators. ► Teams showed consistent non-technical skills preparedness with changing scenarios. ► Non-technical skills preparedness gives plausible explanations why teams fail tasks. -- Abstract: Many statistical results from safety reports tell that human related errors are the dominant influencing factor on the safe operation of power plants. Fortunately, training operators for the technical and non-technical skills can prevent many types of human errors. In this study, four important non-technical skills in safety critical industries – medical, aviation, and nuclear – were selected to describe behaviors of operation teams in emergency conditions of nuclear power plants (NPPs): communication, leadership, situation awareness, and decision-making skills. Also, preparedness of the non-technical skills was defined, and a quantification method of those skills called NoT-SkiP (Non-Technical Skills Preparedness) was developed to represent ‘how well operation teams are prepared to deal with emergency conditions’ in the non-technical skills aspect by analyzing monitoring-control patterns and a verbal protocol. Two case studies were conducted to validate the method. The first case was applied to Loss of Coolant Accident (LOCA) and Steam Generator Tube Rupture (SGTR) training. Independent variables were scenario, training repetition, and members. Relative values of the NoT-SkiP showed a consistent trend with changing scenarios. However, when training was repeated with the same scenario, NoT-SkiP values of some team were changed. It was supposed that leaders of some teams exerted their knowledge acquired from the previous training and gave up thoroughness of using procedures. When members especially who play a dominant role

  7. Development of a quantitative evaluation method for non-technical skills preparedness of operation teams in nuclear power plants to deal with emergency conditions

    Energy Technology Data Exchange (ETDEWEB)

    Yim, Ho Bin; Kim, Ar Ryum [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Seong, Poong Hyun, E-mail: phseong@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

    2013-02-15

    Highlights: ► We selected important non-technical skills for emergency conditions in NPPs. ► We proposed an evaluation method for the selected non-technical skills. ► We conducted two sets of training, 9 experiments each, with real plant operators. ► Teams showed consistent non-technical skills preparedness with changing scenarios. ► Non-technical skills preparedness gives plausible explanations why teams fail tasks. -- Abstract: Many statistical results from safety reports tell that human related errors are the dominant influencing factor on the safe operation of power plants. Fortunately, training operators for the technical and non-technical skills can prevent many types of human errors. In this study, four important non-technical skills in safety critical industries – medical, aviation, and nuclear – were selected to describe behaviors of operation teams in emergency conditions of nuclear power plants (NPPs): communication, leadership, situation awareness, and decision-making skills. Also, preparedness of the non-technical skills was defined, and a quantification method of those skills called NoT-SkiP (Non-Technical Skills Preparedness) was developed to represent ‘how well operation teams are prepared to deal with emergency conditions’ in the non-technical skills aspect by analyzing monitoring-control patterns and a verbal protocol. Two case studies were conducted to validate the method. The first case was applied to Loss of Coolant Accident (LOCA) and Steam Generator Tube Rupture (SGTR) training. Independent variables were scenario, training repetition, and members. Relative values of the NoT-SkiP showed a consistent trend with changing scenarios. However, when training was repeated with the same scenario, NoT-SkiP values of some team were changed. It was supposed that leaders of some teams exerted their knowledge acquired from the previous training and gave up thoroughness of using procedures. When members especially who play a dominant role

  8. The estimation of the correlation between technical-tactical and special physical performance in qualified women volleyball players

    OpenAIRE

    Wnorowski, Krzysztof; Smulskij, Walerij

    2007-01-01

    The article deals with the correlation between technical-tactical and special physical performance in qualified women volleyball players. The experts estimation of technical-tactical performance and seven indices of special physical capacities of athletes were correlated. Most correlation (r = 0,68; p

  9. Application of objective clinical human reliability analysis (OCHRA) in assessment of technical performance in laparoscopic rectal cancer surgery.

    Science.gov (United States)

    Foster, J D; Miskovic, D; Allison, A S; Conti, J A; Ockrim, J; Cooper, E J; Hanna, G B; Francis, N K

    2016-06-01

    Laparoscopic rectal resection is technically challenging, with outcomes dependent upon technical performance. No robust objective assessment tool exists for laparoscopic rectal resection surgery. This study aimed to investigate the application of the objective clinical human reliability analysis (OCHRA) technique for assessing technical performance of laparoscopic rectal surgery and explore the validity and reliability of this technique. Laparoscopic rectal cancer resection operations were described in the format of a hierarchical task analysis. Potential technical errors were defined. The OCHRA technique was used to identify technical errors enacted in videos of twenty consecutive laparoscopic rectal cancer resection operations from a single site. The procedural task, spatial location, and circumstances of all identified errors were logged. Clinical validity was assessed through correlation with clinical outcomes; reliability was assessed by test-retest. A total of 335 execution errors identified, with a median 15 per operation. More errors were observed during pelvic tasks compared with abdominal tasks (p technical performance of laparoscopic rectal surgery.

  10. Experiences with a technically oriented plant management system; Erfahrungen mit einem technisch orientierten Betriebs-Management-System

    Energy Technology Data Exchange (ETDEWEB)

    Haffmann, E. [GiS Gesellschaft fuer integrierte Systemplanung mbH, Erlangen (Germany)

    2000-07-01

    This contribution first deals with the duality of mercantile and technical plant management systems. The following aspects are considered: reasons for and history of this duality; different approaches taken by mercantile and technical plant management systems; differences in the standardisability of mercantile and technical tasks. Dissolution of the duality through coordinated interplay. The author then goes on to explain the most important components of technically oriented maintenance management. These include the collection of technical plant data (with maintenance-relevant data and relations); the establishment of recurring tasks, the commissioning method (involving occupational safety, packaging and evaluation), compilation of manuals, reporting and accompanying plant documentation. The following tools are useful for DP-assisted maintenance: depiction of organisational and operational structures (authorisation system + IBFS application); workflow systems; modelling (data and object models); navigators; form and dialogue generators; integration of external software (project planning, CAD and Office); interface to mercantile systems. Some highlights of the C/S-IBFS were demonstrated in practice at the symposium. [German] Das Referat behandelt zunaechst die Dualitaet von kaufmaennischen und technischen Betriebs-Management-Systemen anhand folgender Aspekte: - Gruende und Historie dieser Dualitaet, - unterschiedliche Loesungsansaetze von kaufmaennischen und technischen Betriebs-Management-Systemen, - unterschiedliche Standardisierbarkeit von kaufmaennischen und technischen Aufgabenstellungen, - Aufloesung der Dualitaet durch koordniertes Zusammenwirken. Sodann werden wichtige Bausteine eines technisch orientierten Instandhaltungs-Managements erlaeutert. Dazu gehoeren die technische Anlagenerfassung (mit instandhaltungsrelevanten Daten und Relationen), die Einrichtung wiederkehrender Aufgaben, das Arbeitsauftragsverfahren (mit Arbeitssicherheit, Paketierung und

  11. Implications of power uprates on safety margins of nuclear power plants. Report of a technical meeting

    International Nuclear Information System (INIS)

    2004-09-01

    The safety of nuclear power plants (NPPs) is based on the defence in depth concept, which relies on successive physical barriers (fuel matrix, cladding, primary system pressure boundary and containment) and other provisions to control radioactive materials and on multiple levels of protection against damage to these barriers. Deterministic safety analysis is an important tool for conforming the adequacy and efficiency of provisions within the defence in depth concept and is used to predict the response of an NPP in predetermined operational states. This type of safety analysis applies a specific set of rules and specific acceptance criteria. Deterministic analysis is typically focused on neutronic, thermohydraulic, radiological and structural aspects, which are often analysed with different computational tools. The advanced computational tools developed for deterministic safety analysis are used for better establishment and utilization of licensing margins or safety margins in consideration of analysis results. At the same time, the existence of such margins ensures that NPPs operate safely in all modes of operation and at all times. To properly assess and address the existing margins and to be able to take advantage of unnecessary conservatisms, state of the art analytical tools intended for safety assessment have been developed. Progress made in the development and application of modern codes for safety analysis and better understanding of phenomena involved in plant design and operation enable the analysts to determine safety margins in consideration of analysis results (licensing margins) with higher precision. There is a general tendency for utilities to take advantage of unnecessarily large conservatisms in safety analyses and to utilize them for reactor power uprates, better utilization of nuclear fuel, higher operational flexibility and for justification of lifetime extension. The present publication sets forth the results of a Technical Meeting on the

  12. Nuclear power plant control room operators' performance research

    International Nuclear Information System (INIS)

    Gray, L.H.; Haas, P.M.

    1984-01-01

    A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator capabilities, of procedures and data for specifying and verifying simulator performance, and of methods and applications of task analysis

  13. Technical and economic evaluation of processes for krypton-85 recovery from power fuel-reprocessing plant off-gas

    International Nuclear Information System (INIS)

    Waggoner, R.C.

    1982-08-01

    A technical and economical analysis has been made of methods for collecting and concentrating krypton from the off-gas from a typical nuclear fuel reprocessing plant. The methods considered were cryogenic distillation, fluorocarbon absorption, mordenite adsorption, and selective permeation. The conclusions reached were: Cryogenic distillation is the only demonstrated route to date. Fluorocarbon absorption may offer economic and technical advantages if fully developed and demonstrated. Mordenite adsorption has been demonstrated only on a bench scale and is estimated to cost more than either cryogenic distillation or fluorocarbon absorption. Selective permeation through a silicone rubber membrane is not sufficiently selective for the route to be cost effective

  14. Technical update on pressure suppression type containments in use in U.S. light water reactor nuclear power plants

    International Nuclear Information System (INIS)

    1978-07-01

    In 1972, Dr. S. H. Hanauer (Technical Advisor to the NRC's Executive Director for Operations) wrote a memorandum that raised several questions on the viability of pressure suppression containment concepts. The concerns raised by Dr. Hanauer have recently become the subject of considerable discussion by several members of the U.S. Congress and public. The report provides a response to these expressed concerns and a status summary for various technical matters that relate to the safety of pressure suppression type containments for light water cooled reactor plants

  15. The Apatity nuclear heating plant project: modern technical and economic issues of nuclear heat application in Russia

    International Nuclear Information System (INIS)

    Adamov, E.O.; Romenkov, A.A.

    1998-01-01

    Traditionally Russia is a country with advanced structure of centralized heat supply. Many thermal plants and heating networks need technical upgrading to improve their technical and economic efficiency. Fossil fuelled heating capacities have a negative influence on ecology, which can be seen especially in the northern regions of Russia. Furthermore, fossil fuel prices are rising in Russia. The above factors tend to intensify the need for alternative heat sources being capable of solving the problem. Nuclear heat sources may be the alternative. In this paper, the main features of a proposed NHP in the Murmansk region are summarized. (author)

  16. Estimate of Technical Potential for Minimum Efficiency Performance Standards in 13 Major World Economies

    Energy Technology Data Exchange (ETDEWEB)

    Letschert, Virginie [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Desroches, Louis-Benoit [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Ke, Jing [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); McNeil, Michael [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2012-07-01

    As part of the ongoing effort to estimate the foreseeable impacts of aggressive minimum efficiency performance standards (MEPS) programs in the world’s major economies, Lawrence Berkeley National Laboratory (LBNL) has developed a scenario to analyze the technical potential of MEPS in 13 major economies around the world1 . The “best available technology” (BAT) scenario seeks to determine the maximum potential savings that would result from diffusion of the most efficient available technologies in these major economies.

  17. A test to evaluate the physical impact on technical performance in soccer

    DEFF Research Database (Denmark)

    Rostgaard, Thomas; Iaia, F. Marcello; Simonsen, Dennis S.

    2008-01-01

    The aim of the study was to develop and examine a test for evaluation of the physical and technical capacity of soccer players. Fourteen youth elite (YE) and seven sub-elite (SE) players performed a physical and technical test (PT-test) consisting of 10 long kicks interspersed with intense......(-1), and 76 +/- 11 umol L(-1) at the end of the test, respectively. After the test muscle CP, glycogen and lactate was 52.9 +/- 6.6, 354 +/- 39, and 25.3 +/- 5.9 mmol kg(-1) d.w., respectively. In summary, the PT-test can be used to evaluate a soccer player's technical skills under conditions similar...... intermittent exercise. In addition, a control test (CON-test) without intense exercise was performed. In both cases, the test result was evaluated by the precision of the 10 kicks. The players also performed the Yo-Yo intermittent recovery test level 2 (Yo-Yo IR2). For the SE-players, blood samples were...

  18. Analysis of Running and Technical Performance in Substitute Players in International Male Rugby Union Competition.

    Science.gov (United States)

    Lacome, Mathieu; Piscione, Julien; Hager, Jean-Philippe; Carling, Christopher

    2016-09-01

    To investigate the patterns and performance of substitutions in 18 international 15-a-side men's rugby union matches. A semiautomatic computerized time-motion system compiled 750 performance observations for 375 players (422 forwards, 328 backs). Running and technical-performance measures included total distance run, high-intensity running (>18.0 km/h), number of individual ball possessions and passes, percentage of passes completed, and number of attempted and percentage of successful tackles. A total of 184 substitutions (85.2%) were attributed to tactical and 32 (14.8%) to injury purposes respectively. The mean period for non-injury-purpose substitutions in backs (17.7%) occurred between 70 and 75 min, while forward substitutions peaked equally between 50-55 and 60-65 min (16.4%). Substitutes generally demonstrated improved running performance compared with both starter players who completed games and players whom they replaced (small differences, ES -0.2 to 0.5) in both forwards and backs over their entire time played. There was also a trend for better running performance in forward and back substitutes over their first 10 min of play compared with the final 10 min for replaced players (small to moderate differences, ES 0.3-0.6). Finally, running performance in both forward and back substitutes was generally lower (ES -0.1 to 0.3, unclear or small differences) over their entire 2nd-half time played compared with their first 10 min of play. The impact of substitutes on technical performance was generally considered unclear. This information provides practitioners with practical data relating to the physical and technical contributions of substitutions that subsequently could enable optimization of their impact on match play.

  19. Instrumentation and process control for fossil demonstration plants. Quarterly technical progress report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    LeSage, L.G.

    1977-07-01

    Work has been performed on updating the study of the state-of-the-art of instrumentation for Fossil Demonstration Plants (FDP), development of mass-flow and other on-line instruments for FDP, process control analysis for FDP, and organization of a symposium on instrumentation and control for FDP. A Solids/Gas Flow Test Facility (S/GFTF) under construction for instrument development, testing, evaluation, and calibration is described. The development work for several mass-flow and other on-line instruments is described: acoustic flowmeter, capacitive density flowmeter, neutron activation flowmeter and composition analysis system, gamma ray correlation flowmeter, optical flowmeter, and capacitive liquid interface level meter.

  20. Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-category I systems for Palisades nuclear power plant

    International Nuclear Information System (INIS)

    Collins, E.K.

    1979-10-01

    The technical evaluation is presented of Consumers Power Company's Palisades nuclear power plant to determine whether the failure of any non-Category I (seismic) equipment could result in a condition, such as flooding, that might potentially adversely affect the performance of safety-related equipment required for the safe shutdown of the facility or to mitigate the consequences of an accident. Criteria developed by the US Nuclear Regulatory Commission were used to evaluate the acceptability of the existing protection as well as measures taken by Consumers Power Company to minimize the danger of flooding and to protect safety-related equipment

  1. Independent verification of a material balance at a LEU fuel fabrication plant. Program for technical assistance to IAEA safeguards

    International Nuclear Information System (INIS)

    Sorenson, R.J.; McSweeney, T.I.; Hartman, M.G.; Brouns, R.J.; Stewart, K.B.; Granquist, D.P.

    1977-11-01

    This report describes the application of methodology for planning an inspection according to the procedures of the International Atomic Energy Agency (IAEA), and an example evaluation of data representative of low-enriched uranium fuel fabrication facilities. Included are the inspection plan test criteria, the inspection sampling plans, the sample data collected during the inspection, acceptance testing of physical inventories with test equipment, material unaccounted for (MUF) evaluation, and quantitative statements of the results and conclusions that could be derived from the inspection. The analysis in this report demonstrates the application of inspection strategies which produce quantitative results. A facility model was used that is representative of large low-enriched uranium fuel fabrication plants with material flows, inventory sizes, and compositions of material representative of operating commercial facilities. The principal objective was to determine and illustrate the degree of assurance against a diversion of special nuclear materials (SNM) that can be achieved by an inspection and the verification of material flows and inventories. This work was performed as part of the USA program for technical assistance to the IAEA. 10 figs, 14 tables

  2. Review on technical issues influencing the performance of chemical barriers of TRU waste repository

    International Nuclear Information System (INIS)

    Fujita, Tomonari; Sugiyama, Daisuke; Tsukamoto, Masaki; Yokoyama, Hayaichi

    1997-01-01

    Studies of technical issues influencing the performance assessment of TRU waste disposal which is occurred from the nuclear fuel reprocessing were reviewed in related to the development of safety analysis method. Especially, the chemical containment was investigated as a key barrier to radionuclide migration. TRU waste including long-lived radionuclides need long-term performance assessment which could be assumed only by the chemical barrier. The description of technical issues concerned with the performance of TRU waste repository has been divided into the following categories: long-term degradation of cementitious materials as engineered barrier for radionuclide migration, effect of colloids, organic macromolecules and organic degradation products on chemical behavior of radionuclides, gas generation by corrosion of metallic wastes, and effects of microbial activity. Preliminary performance assessment indicated that important factors affecting performance of chemical barriers in near-field were the distribution coefficient and the solubility of radionuclides in near-field groundwater. Therefore, it was identified that key issues associated with performance of chemical barrier were evaluation of (a) the long-term change of distribution coefficient of cementitious material through the degradation under repository condition and (b) chemical speciation change of radionuclides such as increase of solubility by the presence of colloidal-size materials. (author)

  3. Safe and economic performance of nuclear power plant. Operation through meticulous Q/A programmes - a german example

    International Nuclear Information System (INIS)

    Schenk, H.J.

    1989-01-01

    Safe and reliable operation of a nuclear power plant over its life time of 40 to 60 years is the essential condition for an economic performance. This goal can be achieved by a qualified responsible staff realizing a high quality of operation and by maintaining high quality and technical standards in the plant in accordance with the status of science and technology. Quality assurance procedures have to verify this in detail, in close contact with the work to be performed. In this presentation I would like to describe our approach in Philippsburg to cope with this task

  4. Biochar Improves Performance of Plants for Mine Soil Revegetation

    Science.gov (United States)

    Biochar (the solid by-product of pyrolysis of biomass), has the potential to improve plant performance for revegetation of mine soils by improving soil chemistry, fertility, moisture holding capacity and by binding heavy metals. We investigated the effect of gasified conifer sof...

  5. Operational safety performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    2000-05-01

    Since the late 1980s, the IAEA has been actively sponsoring work in the area of indicators to monitor nuclear power plant (NPP) operational safety performance. The early activities were mainly focused on exchanging ideas and good practices in the development and use of these indicators at nuclear power plants. Since 1995 efforts have been directed towards the elaboration of a framework for the establishment of an operational safety performance indicator programme. The result of this work, compiled in this publication, is intended to assist NPPs in developing and implementing a monitoring programme, without overlooking the critical aspects related to operational safety performance. The framework proposed in this report was presented at two IAEA workshops on operational safety performance indicators held in Ljubljana, Slovenia, in September 1998 and at the Daya Bay NPP, Szenzhen, China, in December 1998. During these two workshops, the participants discussed and brainstormed on the indicator framework presented. These working sessions provided very useful insights and ideas which where used for the enhancement of the framework proposed. The IAEA is acknowledging the support and contribution of all the participants in these two activities. The programme development was enhanced by pilot plant studies. Four plants from different countries with different designs participated in this study with the objective of testing the applicability, usefulness and viability of this approach

  6. Introducing Model Predictive Control for Improving Power Plant Portfolio Performance

    DEFF Research Database (Denmark)

    Edlund, Kristian Skjoldborg; Bendtsen, Jan Dimon; Børresen, Simon

    2008-01-01

    This paper introduces a model predictive control (MPC) approach for construction of a controller for balancing the power generation against consumption in a power system. The objective of the controller is to coordinate a portfolio consisting of multiple power plant units in the effort to perform...

  7. Comparative study of the performance of Jute plant ( Corchorus ...

    African Journals Online (AJOL)

    This experiment was carried out in the green house at the College of Agricultural Sciences, Olabisi Onabanjo University, Yewa Campus, to assess the performance of jute plant (Corchorus olitorius L.) on three soil-use types (viz; farmland soil, cocoa plantation soil and residential or home garden soil) treated with five ...

  8. Study on Biodiesel plants growth performance and tolerance to ...

    African Journals Online (AJOL)

    Abstract. In this research, we studied the growth performance and tolerance of three biodiesel plants namely; Jatropha curcas, Moringa oleifera and Ricinus communis to water stress. Research conducted on the three different soils from Kaita, Jibiya and Mai'adua in the semi-desert environments of Katsina State, Nigeria.

  9. Radiographic technical quality of root canal treatment performed by a new rotary single-file system.

    Science.gov (United States)

    Colombo, Marco; Bassi, Cristina; Beltrami, Riccardo; Vigorelli, Paolo; Spinelli, Antonio; Cavada, Andrea; Dagna, Alberto; Chiesa, Marco; Poggio, Claudio

    2017-01-01

    The aim of the present study was to evaluate radiographically the technical quality of root canal filling performed by postgraduate students with a new single-file Nickel-Titanium System (F6 Skytaper Komet) in clinical practice. Records of 74 patients who had received endodontic treatment by postgraduate students at the School of Dentistry, Faculty of Medicine, University of Pavia in the period between September 2015 and April 2016 were collected and examined: the final sample consisted 114 teeth and 204 root canals. The quality of endodontic treatment was evaluated by examining the length of the filling in relation to the radiographic apex, the density of the obturation according to the presence of voids and the taper of root canal filling. Chi-squared analysis was used to determine statistically significant differences between the technical quality of root fillings according to tooth's type, position and curvature. The results showed that 75,49%, 82,84% and 90,69% of root filled canals had adequate length, density and taper respectively. Overall, the technical quality of root canal fillings performed by postgraduates students was acceptable in 60,78% of the cases.

  10. TECHNICAL ASPECTS REGARDING THE IMPROVEMENT OF AEROSPACE AIR DEFENSE VECTORS’ PERFORMANCES

    Directory of Open Access Journals (Sweden)

    Vasile SANDRU

    2013-01-01

    Full Text Available Confronted with the spectacular evolution of the aircraft and other aerial vehicles, the systems destined to combat them, especially Surface-to-Air Missile Systems (SAMS, went through an accelerated loss of their performance. The financial crisis has forced an extension of the system operation even if the system is outdated. Therefore, a new modernized version has been designed. Many times, it is better to improve an existing system than to buy a new one. This article describes the diversity of SAMS’s challenges, involving a decrease in time regarding their number. The types of challenges can be divided in two categories: technical and institutional ones. The technical challenges can be also divided in two categories: deterioration of material and obsolescence. The classes of material that present interest for us are aerodynamic vector structure, propulsion, and special systems. From an institutional point of view, the main problems are: cost versus performance and cost versus the remaining lifetime (technical resource of the air defense system. The article finishes with conclusions that support the possibility and necessity of a SAMS upgrade, given the change of the threats characteristics.

  11. The experiences to improve plant performance and reliability of Ko-Ri nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Ho Weon [Korea Electric Power Corp. Ko-Ri nuclear power division, Ko-Ri (Korea, Republic of)

    1998-07-01

    This paper provides a discussion of the lessons learned from operational experience and the future plans to improve performance of the Ko-Ri plant. To operate nuclear power plants safely with good performance is the only way to mitigate the negative image of nuclear power generation to the public and to enhance the economical benefit compared to other electrical generation method. Therefore, in a continuous effort to overcome a negative challenge from outside, we have driven an aggressive 'OCTF' campaign as part of safety. As a result of our efforts, the following remarkable achievements have been accomplished. (1) 3 times of OCTF during recent three years (2) Selected twice as a top notch power plant on the list of NEI magazine in terms of plant capacity factor (3) No scram recorded in 1997 for all 4 units at Ko-Ri site. Ko-Ri is now undergoing the large scale plant betterment projects for retaking-off our operating performance to the level of new challenge target. Such improvement of critical components in the reactor coolant system and turbine system greatly contribute to increase the safety and reliability of the plant and to shortening of the planned outage period as well as to reduction of radiation exposure and radwaste. (Cho, G. S.). 5 tabs., 10 figs.

  12. The experiences to improve plant performance and reliability of Ko-Ri nuclear power plants

    International Nuclear Information System (INIS)

    Kang, Ho Weon

    1998-01-01

    This paper provides a discussion of the lessons learned from operational experience and the future plans to improve performance of the Ko-Ri plant. To operate nuclear power plants safely with good performance is the only way to mitigate the negative image of nuclear power generation to the public and to enhance the economical benefit compared to other electrical generation method. Therefore, in a continuous effort to overcome a negative challenge from outside, we have driven an aggressive 'OCTF' campaign as part of safety. As a result of our efforts, the following remarkable achievements have been accomplished. (1) 3 times of OCTF during recent three years (2) Selected twice as a top notch power plant on the list of NEI magazine in terms of plant capacity factor (3) No scram recorded in 1997 for all 4 units at Ko-Ri site. Ko-Ri is now undergoing the large scale plant betterment projects for retaking-off our operating performance to the level of new challenge target. Such improvement of critical components in the reactor coolant system and turbine system greatly contribute to increase the safety and reliability of the plant and to shortening of the planned outage period as well as to reduction of radiation exposure and radwaste. (Cho, G. S.). 5 tabs., 10 figs

  13. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  14. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  15. Meta-analysis of the technical performance of an imaging procedure: guidelines and statistical methodology.

    Science.gov (United States)

    Huang, Erich P; Wang, Xiao-Feng; Choudhury, Kingshuk Roy; McShane, Lisa M; Gönen, Mithat; Ye, Jingjing; Buckler, Andrew J; Kinahan, Paul E; Reeves, Anthony P; Jackson, Edward F; Guimaraes, Alexander R; Zahlmann, Gudrun

    2015-02-01

    Medical imaging serves many roles in patient care and the drug approval process, including assessing treatment response and guiding treatment decisions. These roles often involve a quantitative imaging biomarker, an objectively measured characteristic of the underlying anatomic structure or biochemical process derived from medical images. Before a quantitative imaging biomarker is accepted for use in such roles, the imaging procedure to acquire it must undergo evaluation of its technical performance, which entails assessment of performance metrics such as repeatability and reproducibility of the quantitative imaging biomarker. Ideally, this evaluation will involve quantitative summaries of results from multiple studies to overcome limitations due to the typically small sample sizes of technical performance studies and/or to include a broader range of clinical settings and patient populations. This paper is a review of meta-analysis procedures for such an evaluation, including identification of suitable studies, statistical methodology to evaluate and summarize the performance metrics, and complete and transparent reporting of the results. This review addresses challenges typical of meta-analyses of technical performance, particularly small study sizes, which often causes violations of assumptions underlying standard meta-analysis techniques. Alternative approaches to address these difficulties are also presented; simulation studies indicate that they outperform standard techniques when some studies are small. The meta-analysis procedures presented are also applied to actual [18F]-fluorodeoxyglucose positron emission tomography (FDG-PET) test-retest repeatability data for illustrative purposes. © The Author(s) 2014 Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  16. Savannah River Plant, Works Technical Department monthly progress report for March 1956

    International Nuclear Information System (INIS)

    1956-01-01

    This document details activities of the Works Technical Department during the month of March 1956. It covers reactor technology, separations technology, engineering assistance and heavy water technology

  17. Technical assessment of agricultural biogas plants. Utilization ratio and energy efficiency; Verfahrenstechnische Bewertung landwirtschaftlicher Biogasanlagen. Auslastung und energetische Effizienz

    Energy Technology Data Exchange (ETDEWEB)

    Effenberger, Mathias; Kissel, Rainer; Lehner, Andreas; Gronauer, Andreas [Bayerische Landesanstalt fuer Landwirtschaft, Freising (Germany). Arbeitsgruppe Biogastechnologie und Reststoffmanagement

    2008-07-01

    Technical indicators of six selected modern agricultural biogas plants (BGP) were determined to evaluate utilization ratio and energy efficiency. In all of these plants, renewable raw materials were treated in combination with animal manure. At a specific installed electrical capacity between 0.09 and 0.25 kW per m{sup 3} usable digester volume, electrical utilization ratios between 88 and 98 % were achieved. The combination of these two characteristic values may be used as a first indicator of process stability and functionality of a BGP. The external utilization ratio for the off-heat from the combined-heat-and-power unit was between 0 and 46 %. (orig.)

  18. Performance analysis of WWER-440/230 nuclear power plants

    International Nuclear Information System (INIS)

    1997-01-01

    This report examines one particular design, the WWER-440/230, the first generation of commercial WWERs, essentially comparable to the western PWR. This design was installed widely in eastern Europe with a total of 16 unites being completed in what are now Armenia, Bulgaria, Germany (the former German Democratic Republic) the Slovak Republic and Russia. The plants in Armenia and Germany (the former German Democratic Republic) have been closed down, but particularly in Bulgaria and to a lesser extent the Slovak Republic the remaining plants supply a significant proportion of the electricity of the country and decisions to close them could not be taken lightly. The aim of this report is twofold: first to determine whether the impression given by these good overall performance indicators is confirmed using more detailed indicators covering a wide range of factors; second, to see to what extent good performance can be attributed to the industrial and institutional environment in which these plants were designed, built and operated. Particular attention is paid to identifying factors that may impact the quality of the service provided, especially those factors under management control which can be strongly influenced by current and future policy changes and those factors that are beyond the plant management control but could have influenced the performance of the power plants. Issues concerning the safety of these plants are of considerable importance, but they remain outside the scope of this report. Conclusions and recommendations formulated by the IAEA related to WWER safety are contained in the series of reports prepared in the framework of the Extrabudgetary Programme on WWER Safety. A programme progress report was published in 1994 (IAEA-TECDOC-773). Refs, figs, tabs

  19. Performance analysis of WWER-440/230 nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    This report examines one particular design, the WWER-440/230, the first generation of commercial WWERs, essentially comparable to the western PWR. This design was installed widely in eastern Europe with a total of 16 unites being completed in what are now Armenia, Bulgaria, Germany (the former German Democratic Republic) the Slovak Republic and Russia. The plants in Armenia and Germany (the former German Democratic Republic) have been closed down, but particularly in Bulgaria and to a lesser extent the Slovak Republic the remaining plants supply a significant proportion of the electricity of the country and decisions to close them could not be taken lightly. The aim of this report is twofold: first to determine whether the impression given by these good overall performance indicators is confirmed using more detailed indicators covering a wide range of factors; second, to see to what extent good performance can be attributed to the industrial and institutional environment in which these plants were designed, built and operated. Particular attention is paid to identifying factors that may impact the quality of the service provided, especially those factors under management control which can be strongly influenced by current and future policy changes and those factors that are beyond the plant management control but could have influenced the performance of the power plants. Issues concerning the safety of these plants are of considerable importance, but they remain outside the scope of this report. Conclusions and recommendations formulated by the IAEA related to WWER safety are contained in the series of reports prepared in the framework of the Extrabudgetary Programme on WWER Safety. A programme progress report was published in 1994 (IAEA-TECDOC-773). Refs, figs, tabs.

  20. Study on key technologies of optimization of big data for thermal power plant performance

    Science.gov (United States)

    Mao, Mingyang; Xiao, Hong

    2018-06-01

    Thermal power generation accounts for 70% of China's power generation, the pollutants accounted for 40% of the same kind of emissions, thermal power efficiency optimization needs to monitor and understand the whole process of coal combustion and pollutant migration, power system performance data show explosive growth trend, The purpose is to study the integration of numerical simulation of big data technology, the development of thermal power plant efficiency data optimization platform and nitrogen oxide emission reduction system for the thermal power plant to improve efficiency, energy saving and emission reduction to provide reliable technical support. The method is big data technology represented by "multi-source heterogeneous data integration", "large data distributed storage" and "high-performance real-time and off-line computing", can greatly enhance the energy consumption capacity of thermal power plants and the level of intelligent decision-making, and then use the data mining algorithm to establish the boiler combustion mathematical model, mining power plant boiler efficiency data, combined with numerical simulation technology to find the boiler combustion and pollutant generation rules and combustion parameters of boiler combustion and pollutant generation Influence. The result is to optimize the boiler combustion parameters, which can achieve energy saving.

  1. Security during the Construction of New Nuclear Power Plants: Technical Basis for Access Authorization and Fitness-For-Duty Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Branch, Kristi M.; Baker, Kathryn A.

    2009-09-01

    A technical letter report to the NRC summarizing the findings of a benchmarking study, literature review, and workshop with experts on current industry standards and expert judgments about needs for security during the construction phase of critical infrastructure facilities in the post-September 11 U.S. context, with a special focus on the construction phase of nuclear power plants and personnel security measures.

  2. Fuel performance of licensed nuclear power plants through 1974

    International Nuclear Information System (INIS)

    Bobe, P.E.

    1976-01-01

    General aspects of fuel element design and specific design data for typical Pressurized and Boiling Water Reactors are presented. Based on a literature search, failure modes and specific failures incurred through December 31, 1974 are described, together with a discussion of those problems which have had a significant impact upon plant operation. The relationship between fuel element failures and the resultant coolant activity/radioactive gaseous effluents upon radiation exposure, plant availability and capacity factors, economic impact, and waste management, are discussed. An assessment was made regarding the generation, availability, and use of fuel performance data

  3. Vehicle Integrated Performance Analysis, the VIPA Experience: Reconnecting with Technical Integration

    Science.gov (United States)

    McGhee, David S.

    2005-01-01

    Today's NASA is facing significant challenges and changes. The Exploration initiative indicates a large increase in projects with limited increase in budget. The Columbia report has criticized NASA for its lack of insight and technical integration impacting its ability to provide safety. The Aldridge report is advocating NASA find new ways of doing business. Very early in the Space Launch Initiative (SLI) program a small team of engineers at MSFC were asked to propose a process for performing a system level assessment of a launch vehicle. The request was aimed primarily at providing insight and making NASA a "smart buyer." Out of this effort the VIPA team was created. The difference between the VIPA effort and many integration attempts is that VIPA focuses on using experienced people from various disciplines and a process which focuses them on a technically integrated assessment. Most previous attempts have focused on developing an all encompassing software tool. In addition, VIPA anchored its process formulation in the experience of its members and in early developmental Space Shuttle experience. The primary reference for this is NASA-TP-2001-210092, "Launch Vehicle Design Process: Characterization, Technical Integration, and Lessons Learned," and discussions with its authors. The foundations of VIPA's process are described. The VIPA team also recognized the need to drive detailed analysis earlier in the design process. Analyses and techniques typically done in later design phases, are brought forward using improved computing technology. The intent is to allow the identification of significant sensitivities, trades, and design issues much earlier in the program. This process is driven by the T-model for Technical Integration described in the aforementioned reference. VIPA's approach to performing system level technical integration is discussed in detail. Proposed definitions are offered to clarify this discussion and the general systems integration dialog. VIPA

  4. Effect of Age Group on Technical-Tactical Performance Profile of the Serve in Men's Volleyball.

    Science.gov (United States)

    García-de-Alcaraz, Antonio; Ortega, Enrique; Palao, José M

    2016-10-01

    The aim of this study was to analyze the technical-tactical performance profile of the serve for various age groups and categories of competition in men's volleyball. The sample comprised 13,262 serves performed by 986 players in 299 sets observed in various categories of competition (U-14, U-16, U-19, national senior, and international senior). An observational design was used. The variables studied were category of competition, type of execution, and serve performance. The results showed that for higher age groups (senior categories), there were significantly fewer jump serves and poorer serve performance, regardless of players' maturity and training development. The use of the jump serves increased the serve risk while attempting to hinder the organization of the opponent attack. This paper discusses the serve evolution and the implications on the training process at the different age groups in men's volleyball. © The Author(s) 2016.

  5. Nuclear steam power plant cycle performance calculations supported by power plant monitoring and results computer

    International Nuclear Information System (INIS)

    Bettes, R.S.

    1984-01-01

    The paper discusses the real time performance calculations for the turbine cycle and reactor and steam generators of a nuclear power plant. Program accepts plant measurements and calculates performance and efficiency of each part of the cycle: reactor and steam generators, turbines, feedwater heaters, condenser, circulating water system, feed pump turbines, cooling towers. Presently, the calculations involve: 500 inputs, 2400 separate calculations, 500 steam properties subroutine calls, 200 support function accesses, 1500 output valves. The program operates in a real time system at regular intervals

  6. Quantitative imaging biomarkers: a review of statistical methods for technical performance assessment.

    Science.gov (United States)

    Raunig, David L; McShane, Lisa M; Pennello, Gene; Gatsonis, Constantine; Carson, Paul L; Voyvodic, James T; Wahl, Richard L; Kurland, Brenda F; Schwarz, Adam J; Gönen, Mithat; Zahlmann, Gudrun; Kondratovich, Marina V; O'Donnell, Kevin; Petrick, Nicholas; Cole, Patricia E; Garra, Brian; Sullivan, Daniel C

    2015-02-01

    Technological developments and greater rigor in the quantitative measurement of biological features in medical images have given rise to an increased interest in using quantitative imaging biomarkers to measure changes in these features. Critical to the performance of a quantitative imaging biomarker in preclinical or clinical settings are three primary metrology areas of interest: measurement linearity and bias, repeatability, and the ability to consistently reproduce equivalent results when conditions change, as would be expected in any clinical trial. Unfortunately, performance studies to date differ greatly in designs, analysis method, and metrics used to assess a quantitative imaging biomarker for clinical use. It is therefore difficult or not possible to integrate results from different studies or to use reported results to design studies. The Radiological Society of North America and the Quantitative Imaging Biomarker Alliance with technical, radiological, and statistical experts developed a set of technical performance analysis methods, metrics, and study designs that provide terminology, metrics, and methods consistent with widely accepted metrological standards. This document provides a consistent framework for the conduct and evaluation of quantitative imaging biomarker performance studies so that results from multiple studies can be compared, contrasted, or combined. © The Author(s) 2014 Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  7. Domestic activity for technical development of the APR1400's RCP performance test

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seok; Kim, Seok; Bae, Byung-Uhn; Cho, Yun-Jae; Kim, Yeon-Sik; Jeon, Woo-Jin; Yun, Young-Jung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The thermal hydraulic and electric capability of the RCP test facility (RCPTF) covers up to 18.5 MPa, 343 .deg. C, 11.7 m{sup 3}/s, and 14.0 MW in the design pressure, temperature, flow rate, and the maximum electric power, respectively. In 2013, commissioning test had been performed to verify its designed capability, followed by several modifications in the RCPTF including signal processing and control logic to enhance verification and evaluation capability of the RCP performance. After finishing the commissioning and modification of the RCPTF, type test for the new-type RCP had been performed successfully. In this paper, several technical issues developed in the 2013 and the type test's method and results will be described. In the present paper, the technical activities for the development of the verification test of APR1400's RCP are described. KAERI has completed the full set of technology development, prerequisite for the RCP verification test, and now on the way to perform a test for the sealing capacity of the seal assembly during the Station Block Out (SBO) condition of APR1400.

  8. Simulator training and non-technical factors improve laparoscopic performance among OBGYN trainees.

    Science.gov (United States)

    Ahlborg, Liv; Hedman, Leif; Nisell, Henry; Felländer-Tsai, Li; Enochsson, Lars

    2013-10-01

    To investigate how simulator training and non-technical factors affect laparoscopic performance among residents in obstetrics and gynecology. In this prospective study, trainees were randomized into three groups. The first group was allocated to proficiency-based training in the LapSimGyn(®) virtual reality simulator. The second group received additional structured mentorship during subsequent laparoscopies. The third group served as control group. At baseline an operation was performed and visuospatial ability, flow and self-efficacy were assessed. All groups subsequently performed three tubal occlusions. Self-efficacy and flow were assessed before and/or after each operation. Simulator training was conducted at the Center for Advanced Medical Simulation and Training, Karolinska University Hospital. Sterilizations were performed at each trainee's home clinic. Twenty-eight trainees/residents from 21 hospitals in Sweden were included. Visuospatial ability was tested by the Mental Rotation Test-A. Flow and self-efficacy were assessed by validated scales and questionnaires. Laparoscopic performance was measured as the duration of surgery. Visuospatial ability, self-efficacy and flow were correlated to the laparoscopic performance using Spearman's correlations. Differences between groups were analyzed by the Mann-Whitney U-test. No differences across groups were detected at baseline. Self-efficacy scores before and flow scores after the third operation were significantly higher in the trained groups. Duration of surgery was significantly shorter in the trained groups. Flow and self-efficacy correlate positively with laparoscopic performance. Simulator training and non-technical factors appear to improve the laparoscopic performance among trainees/residents in obstetrics and gynecology. © 2013 Nordic Federation of Societies of Obstetrics and Gynecology.

  9. Hydroponic isotope labeling of entire plants and high-performance mass spectrometry for quantitative plant proteomics.

    Science.gov (United States)

    Bindschedler, Laurence V; Mills, Davinia J S; Cramer, Rainer

    2012-01-01

    Hydroponic isotope labeling of entire plants (HILEP) combines hydroponic plant cultivation and metabolic labeling with stable isotopes using (15)N-containing inorganic salts to label whole and mature plants. Employing (15)N salts as the sole nitrogen source for HILEP leads to the production of healthy-looking plants which contain (15)N proteins labeled to nearly 100%. Therefore, HILEP is suitable for quantitative plant proteomic analysis, where plants are grown in either (14)N- or (15)N-hydroponic media and pooled when the biological samples are collected for relative proteome quantitation. The pooled (14)N-/(15)N-protein extracts can be fractionated in any suitable way and digested with a protease for shotgun proteomics, using typically reverse phase liquid chromatography nanoelectrospray ionization tandem mass spectrometry (RPLC-nESI-MS/MS). Best results were obtained with a hybrid ion trap/FT-MS mass spectrometer, combining high mass accuracy and sensitivity for the MS data acquisition with speed and high-throughput MS/MS data acquisition, increasing the number of proteins identified and quantified and improving protein quantitation. Peak processing and picking from raw MS data files, protein identification, and quantitation were performed in a highly automated way using integrated MS data analysis software with minimum manual intervention, thus easing the analytical workflow. In this methodology paper, we describe how to grow Arabidopsis plants hydroponically for isotope labeling using (15)N salts and how to quantitate the resulting proteomes using a convenient workflow that does not require extensive bioinformatics skills.

  10. Introducing Model Predictive Control for Improving Power Plant Portfolio Performance

    DEFF Research Database (Denmark)

    Edlund, Kristian Skjoldborg; Bendtsen, Jan Dimon; Børresen, Simon

    2008-01-01

    This paper introduces a model predictive control (MPC) approach for construction of a controller for balancing the power generation against consumption in a power system. The objective of the controller is to coordinate a portfolio consisting of multiple power plant units in the effort to perform...... reference tracking and disturbance rejection in an economically optimal way. The performance function is chosen as a mixture of the `1-norm and a linear weighting to model the economics of the system. Simulations show a significant improvement of the performance of the MPC compared to the current...

  11. IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The majority of instrumentation and control (I and C) equipment in nuclear power plants in the world was designed 30 to over 45 years ago with analog and relay components, and in some cases rudimentary digital technology. Today, most of these plants continue to operate with a substantial amount of this original I and C equipment that is or soon will be obsolete. Much of this equipment is approaching or exceeding its life expectancy, resulting in increasing maintenance efforts to sustain acceptable system performance. Decreasing availability of replacement parts, and the accelerating deterioration of the infrastructure of manufacturers that support analog technology, accentuate the obsolescence problems and cause operation and maintenance (O and M) cost increases. Refurbishments and license extensions mean that a plant must be supported longer, which will increase the obsolescence issues. In addition, the older technology limits the possibilities for adding new beneficial capabilities to the plant systems and interfaces. New technology provides the opportunity to improve plant performance, human system interface (HSI) functionality, and reliability; to enhance operator performance and reliability, and to address difficulties in finding young professionals with education and experience with older analog technology. Finally, there may be changes in regulatory requirements that could necessitate modernization activities. Modernization of I and C systems and components, using digital equipment to address these obsolescence issues and the need to improve plant performance (e.g., increase power output capacity, reliability, and availability) while maintaining high levels of safety, is a current major issue for nuclear power plants throughout the world. A number of nuclear power utilities are committing to major modernization programs. The need for this modernization will accelerate as plants age, obsolescence issues increase, plants receive license renewals, and features

  12. Formative evaluation of a telemedicine model for delivering clinical neurophysiology services part I: utility, technical performance and service provider perspective.

    LENUS (Irish Health Repository)

    Breen, Patricia

    2010-01-01

    Formative evaluation is conducted in the early stages of system implementation to assess how it works in practice and to identify opportunities for improving technical and process performance. A formative evaluation of a teleneurophysiology service was conducted to examine its technical and sociological dimensions.

  13. Thermal performance monitoring and assessment in Dukovany nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Madron, F. [Chemplant Technology s.r.o., Hrncirska 4, 400 01 Usti nad Labem (Czech Republic); Papuga, J. [CEZ a.s., JE Dukovany, 675 50 Dukovany (Czech Republic); Pliska, J. [I and C ENERGO a.s., Prazska 684, 674 01 Trebic (Czech Republic)

    2006-07-01

    Competition in the European electricity market forces generators to achieve - in compliance with safety and environmental standards - efficiency of production as high as possible. This efficiency or heat rate is an important indicator of both the condition of the plant equipment and the quality of plant operation. Similar thermal performance indicators can also be calculated for components of the plant equipment such as heat exchangers. However, it is not easy to quantify these indicators with sufficient precision so that the results can be used for conduct of plant operation in near-real time and for predictive maintenance. This paper describes a present state of the system monitoring and evaluating thermal performance of the reactor units in Dukovany Nuclear Power Plant. The system provides information on actual and desirable (should-be) values of thermal performance indicators for control room operators, performance engineers and maintenance planners. The system is designed to monitor steady states and has two main functions: data validation and process simulation. Data validation is based on data reconciliation methodology and carried out with Recon software by Chemplant Technology. A detailed model of the secondary side for mass and heat balancing has been made up by means of the Recon's graphical editor; now it contains roughly 300 flows and employs data of about 200 measurements. Main advantages of the data reconciliation are: - reconciled data are consistent with the model, - reconciled data are more precise than data directly measured with consequence that the thermal power of steam generators is determined with substantially lower uncertainty than before - data reconciliation represents a solid basis for detection and identification of data corrupted by gross errors. Simulation is performed with a different analytical model of plant components configured into secondary side. The model has been developed by I and C Energo. Main purposes of simulation

  14. Performance optimization of the Växtkraft biogas production plant

    International Nuclear Information System (INIS)

    Thorin, Eva; Lindmark, Johan; Nordlander, Eva; Odlare, Monica; Dahlquist, Erik; Kastensson, Jan; Leksell, Niklas; Pettersson, Carl-Magnus

    2012-01-01

    Highlights: ► Pre-treatment of ley crop can increase the biogas plant performance. ► Membrane filtration can increase the capacity of the biogas plant. ► Mechanical pre-treatment of the ley crop shows the highest energy efficiency. ► Using a distributor to spread the residues as fertilizer show promising results. -- Abstract: All over the world there is a strong interest and also potential for biogas production from organic residues as well as from different crops. However, to be commercially competitive with other types of fuels, efficiency improvements of the biogas production process are needed. In this paper, results of improvements studies done on a full scale co-digestion plant are presented. In the plant organic wastes from households and restaurants are mixed and digested with crops from pasture land. The areas for improvement of the plant addressed in this paper are treatment of the feed material to enhance the digestion rate, limitation of the ballast of organics in the water stream recirculated in the process, and use of the biogas plant residues at farms. Results from previous studies on pre-treatment and membrane filtration of recirculated process water are combined for an estimation of the total improvement potential. Further, the possibility of using neural networks to predict biogas production using historical data from the full-scale biogas plant was investigated. Results from an investigation using the process residues as fertilizer are also presented. The results indicate a potential to increase the biogas yield from the process with up to over 30% with pre-treatment of the feed and including membrane filtration in the process. Neural networks have the potential to be used for prediction of biogas production. Further, it is shown that the residues from biogas production can be used as fertilizers but that the emission of N 2 O from the fertilized soil is dependent on the soil type and spreading technology.

  15. Life prediction study of reactor pressure vessel as essential technical foundation for plant life extension

    International Nuclear Information System (INIS)

    Nakajima, H.; Nakajima, N.; Kondo, T.

    1987-01-01

    The life of a LWR plant is determined essentially by the limit of reliable performance of the components which are difficult to replace without high economic and/or safety risks. Typical of such a component is the reactor pressure vessel (RPV). The engineering life of a RPV of a given quality of steel is considered to be a complex function of factors such as the resistance to fracture, which has deteriorated due to neutron irradiation and thermal aging, and generation of surface flaws by environmental effects such as corrosion and their growth under operational load that varies during steady state operation and transients. In an attempt to evaluate the engineering life of a RPV of a LWR, a preliminary survey was made by applying a set of knowledge accumulated primarily in the field of subcritical crack growth behavior of RPV steels in reactor water environments. The major conclusions drawn are: (1) the life of a RPV is dependent on the quality of steel used, particularly with respect to any minor impurities it contains. (2) The issue of plant life extension in RPV aspect is found to be optimistic for cases where the steels used satisfy a reasonable level of quality control. (3) The importance of providing sound scientific foundation is stressed for the implementation of a practicable life extension scheme: this can be established through intensified studies of flaw growth and fracture behaviours in well defined testings under reasonably simulated service conditions

  16. Reducing the occurrence of plant events through improved human performance

    International Nuclear Information System (INIS)

    Ross, T.; Burkhart, A.D.

    1993-01-01

    During a routine control room surveillance, the reactor operator is distracted by an alarming secondary annunciator and a telephone call. When the reactor operator resumes the surveillance, he inadvertently performs the procedural steps out of order. This causes a reportable nuclear event. How can procedure-related human performance problems such as this be prevented? The question is vitally important for the nuclear industry. The U.S. Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data observed, open-quotes With the perceived reduction in the number of events caused by equipment failures, INPO and other industry groups and human performance experts agree that a key to continued improvement in plant performance and safety is improved human performance.close quotes In fact, open-quotes more than 50% of the reportable events occurring at nuclear power plants involve human error.close quotes Prevention (or correction) of a human performance problem is normally based on properly balancing the following three factors: (1) supervisory involvement; (2) personnel training; and (3) procedures. The nuclear industry is implementing a formula known as ACME, which better balances supervisory involvement, personnel training, and procedures. Webster's New World Dictionary defines acme as the highest point, the peak. ACME human performance is the goal: ACME Adherence to and use of procedures; Self-Checking; Management Involvement; and Event Investigations

  17. Solar power plant performance evaluation: simulation and experimental validation

    International Nuclear Information System (INIS)

    Natsheh, E M; Albarbar, A

    2012-01-01

    In this work the performance of solar power plant is evaluated based on a developed model comprise photovoltaic array, battery storage, controller and converters. The model is implemented using MATLAB/SIMULINK software package. Perturb and observe (P and O) algorithm is used for maximizing the generated power based on maximum power point tracker (MPPT) implementation. The outcome of the developed model are validated and supported by a case study carried out using operational 28.8kW grid-connected solar power plant located in central Manchester. Measurements were taken over 21 month's period; using hourly average irradiance and cell temperature. It was found that system degradation could be clearly monitored by determining the residual (the difference) between the output power predicted by the model and the actual measured power parameters. It was found that the residual exceeded the healthy threshold, 1.7kW, due to heavy snow in Manchester last winter. More important, the developed performance evaluation technique could be adopted to detect any other reasons that may degrade the performance of the P V panels such as shading and dirt. Repeatability and reliability of the developed system performance were validated during this period. Good agreement was achieved between the theoretical simulation and the real time measurement taken the online grid connected solar power plant.

  18. Solar power plant performance evaluation: simulation and experimental validation

    Science.gov (United States)

    Natsheh, E. M.; Albarbar, A.

    2012-05-01

    In this work the performance of solar power plant is evaluated based on a developed model comprise photovoltaic array, battery storage, controller and converters. The model is implemented using MATLAB/SIMULINK software package. Perturb and observe (P&O) algorithm is used for maximizing the generated power based on maximum power point tracker (MPPT) implementation. The outcome of the developed model are validated and supported by a case study carried out using operational 28.8kW grid-connected solar power plant located in central Manchester. Measurements were taken over 21 month's period; using hourly average irradiance and cell temperature. It was found that system degradation could be clearly monitored by determining the residual (the difference) between the output power predicted by the model and the actual measured power parameters. It was found that the residual exceeded the healthy threshold, 1.7kW, due to heavy snow in Manchester last winter. More important, the developed performance evaluation technique could be adopted to detect any other reasons that may degrade the performance of the P V panels such as shading and dirt. Repeatability and reliability of the developed system performance were validated during this period. Good agreement was achieved between the theoretical simulation and the real time measurement taken the online grid connected solar power plant.

  19. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3 (Docket No. 50-286)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  20. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the James A. Fitzpatrick Nuclear Power Plant (Docket No. 50-333)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the James A. FitzPatrick Nuclear Power Plant. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  1. The Future Cybersecurity Workforce: Going Beyond Technical Skills for Successful Cyber Performance

    Directory of Open Access Journals (Sweden)

    Jessica Dawson

    2018-06-01

    Full Text Available One of the challenges in writing an article reviewing the current state of cyber education and workforce development is that there is a paucity of quantitative assessment regarding the cognitive aptitudes, work roles, or team organization required by cybersecurity professionals to be successful. In this review, we argue that the people who operate within the cyber domain need a combination of technical skills, domain specific knowledge, and social intelligence to be successful. They, like the networks they operate, must also be reliable, trustworthy, and resilient. Defining the knowledge, skills, attributes, and other characteristics is not as simple as defining a group of technical skills that people can be trained on; the complexity of the cyber domain makes this a unique challenge. There has been little research devoted to exactly what attributes individuals in the cyber domain need. What research does exist places an emphasis on technical and engineering skills while discounting the important social and organizational influences that dictate success or failure in everyday settings. This paper reviews the literature on cyber expertise and cyber workforce development to identify gaps and then argues for the important contribution of social fit in the highly complex and heterogenous cyber workforce. We then identify six assumptions for the future of cybersecurity workforce development, including the requirement for systemic thinkers, team players, a love for continued learning, strong communication ability, a sense of civic duty, and a blend of technical and social skill. Finally, we make recommendations for social and cognitive metrics which may be indicative of future performance in cyber work roles to provide a roadmap for future scholars.

  2. The Future Cybersecurity Workforce: Going Beyond Technical Skills for Successful Cyber Performance.

    Science.gov (United States)

    Dawson, Jessica; Thomson, Robert

    2018-01-01

    One of the challenges in writing an article reviewing the current state of cyber education and workforce development is that there is a paucity of quantitative assessment regarding the cognitive aptitudes, work roles, or team organization required by cybersecurity professionals to be successful. In this review, we argue that the people who operate within the cyber domain need a combination of technical skills, domain specific knowledge, and social intelligence to be successful. They, like the networks they operate, must also be reliable, trustworthy, and resilient. Defining the knowledge, skills, attributes, and other characteristics is not as simple as defining a group of technical skills that people can be trained on; the complexity of the cyber domain makes this a unique challenge. There has been little research devoted to exactly what attributes individuals in the cyber domain need. What research does exist places an emphasis on technical and engineering skills while discounting the important social and organizational influences that dictate success or failure in everyday settings. This paper reviews the literature on cyber expertise and cyber workforce development to identify gaps and then argues for the important contribution of social fit in the highly complex and heterogenous cyber workforce. We then identify six assumptions for the future of cybersecurity workforce development, including the requirement for systemic thinkers, team players, a love for continued learning, strong communication ability, a sense of civic duty, and a blend of technical and social skill. Finally, we make recommendations for social and cognitive metrics which may be indicative of future performance in cyber work roles to provide a roadmap for future scholars.

  3. Impact of aging and material structure on CANDU plant performance

    International Nuclear Information System (INIS)

    Nadeau, E.; Ballyk, J.; Ghalavand, N.

    2011-01-01

    In-service behaviour of pressure tubes is a key factor in the assessment of safety margins during plant operation. Pressure tube deformation (diametral expansion) affects fuel bundle dry out characteristics resulting in reduced margin to trip for some events. Pressure tube aging mechanisms also erode design margins on fuel channels or interfacing reactor components. The degradation mechanisms of interest are primarily deformation, loss of fracture resistance and hydrogen ingress. CANDU (CANada Deuterium Uranium, a registered trademark of the Atomic Energy of Canada Limited used under exclusive licence by Candu Energy Inc.) owners and operators need to maximize plant capacity factor and meet or exceed the reactor design life targets while maintaining safety margins. The degradation of pressure tube material and geometry are characterized through a program of inspection, material surveillance and assessment and need to be managed to optimize plant performance. Candu is improving pressure tubes installed in new build and life extension projects. Improvements include changes designed to reduce or mitigate the impact of pressure tube elongation and diametral expansion rates, improvement of pressure tube fracture properties, and reduction of the implications of hydrogen ingress. In addition, Candu provides an extensive array of engineering services designed to assess the condition of pressure tubes and address the impact of pressure tube degradation on safety margins and plant performance. These services include periodic and in-service inspection and material surveillance of pressure tubes and deterministic and probabilistic assessment of pressure tube fitness for service to applicable standards. Activities designed to mitigate the impact of pressure tube deformation on safety margins include steam generator cleaning, which improves trip margins, and trip design assessment to optimize reactor trip set points restoring safety and operating margins. This paper provides an

  4. Impact of aging and material structure on CANDU plant performance

    Energy Technology Data Exchange (ETDEWEB)

    Nadeau, E.; Ballyk, J.; Ghalavand, N. [Candu Energy Inc., Mississauga, Ontario (Canada)

    2011-07-01

    In-service behaviour of pressure tubes is a key factor in the assessment of safety margins during plant operation. Pressure tube deformation (diametral expansion) affects fuel bundle dry out characteristics resulting in reduced margin to trip for some events. Pressure tube aging mechanisms also erode design margins on fuel channels or interfacing reactor components. The degradation mechanisms of interest are primarily deformation, loss of fracture resistance and hydrogen ingress. CANDU (CANada Deuterium Uranium, a registered trademark of the Atomic Energy of Canada Limited used under exclusive licence by Candu Energy Inc.) owners and operators need to maximize plant capacity factor and meet or exceed the reactor design life targets while maintaining safety margins. The degradation of pressure tube material and geometry are characterized through a program of inspection, material surveillance and assessment and need to be managed to optimize plant performance. Candu is improving pressure tubes installed in new build and life extension projects. Improvements include changes designed to reduce or mitigate the impact of pressure tube elongation and diametral expansion rates, improvement of pressure tube fracture properties, and reduction of the implications of hydrogen ingress. In addition, Candu provides an extensive array of engineering services designed to assess the condition of pressure tubes and address the impact of pressure tube degradation on safety margins and plant performance. These services include periodic and in-service inspection and material surveillance of pressure tubes and deterministic and probabilistic assessment of pressure tube fitness for service to applicable standards. Activities designed to mitigate the impact of pressure tube deformation on safety margins include steam generator cleaning, which improves trip margins, and trip design assessment to optimize reactor trip set points restoring safety and operating margins. This paper provides an

  5. Positional interchanges influence the physical and technical match performance variables of elite soccer players.

    Science.gov (United States)

    Schuth, G; Carr, G; Barnes, C; Carling, C; Bradley, P S

    2016-01-01

    Positional variation in match performance is well established in elite soccer but no information exists on players switching positions. This study investigated the influence of elite players interchanging from one position to another on physical and technical match performance. Data were collected from multiple English Premier League (EPL) seasons using a computerised tracking system. After adhering to stringent inclusion criteria, players were examined across several interchanges: central-defender to fullback (CD-FB, n = 11, 312 observations), central-midfielder to wide-midfielder (CM-WM, n = 7, 171 observations), wide-midfielder to central-midfielder (WM-CM, n = 7, 197 observations) and attacker to wide-midfielder (AT-WM, n = 4, 81 observations). Players interchanging from CD-FB covered markedly more high-intensity running and sprinting distance (effect size [ES]: -1.56 and -1.26), lost more possessions but made more final third entries (ES: -1.23 and -1.55). Interchanging from CM-WM and WM-CM resulted in trivial to moderate differences in both physical (ES: -0.14-0.59 and -0.21-0.39) and technical performances (ES: -0.48-0.64 and -0.36-0.54). Players interchanging from AT-WM demonstrated a moderate difference in high-intensity running without possession (ES: -0.98) and moderate-to-large differences in the number of clearances, tackles and possessions won (ES: -0.77, -1.16 and -1.41). The data demonstrate that the physical and technical demands vary greatly from one interchange to another but utility players seem able to adapt to these positional switches.

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  7. Final technical report: Atmospheric emission analysis for the Hanford Waste Vitrification plant

    International Nuclear Information System (INIS)

    Andrews, G.L.; Rhoads, K.C.

    1996-03-01

    This report is an assessment of chemical and radiological effluents that are expected to be released to the atmosphere from the Hanford Waste Vitrification Plant (HWVP). The report is divided into two sections. In the first section, the impacts of carbon monoxide (CO) and nitrogen oxides as NO 2 have been estimated for areas within the Hanford Site boundary. A description of the dispersion model used to-estimate CO and NO 2 average concentrations and Hanford Site meteorological data has been included in this section. In the second section, calculations were performed to estimate the potential radiation doses to a maximally exposed off-site individual. The model used to estimate the horizontal and vertical dispersion of radionuclides is also discussed

  8. Emergency-control planning in the vicinity of large-scale technical plants

    International Nuclear Information System (INIS)

    Lindackers, K.H.

    1982-01-01

    In 7 theses, the author shows the most important aspects of disaster control planning: 1) The planning of disaster control measures should not be the object of a licencing procedure. 2) On site allocation or planned determination of sites for potentially hazardous plants it shall be examined whether disaster control measures can be performed sufficiently. 3) Planning of disaster control measures must not be based on detailed accident scenarios. 4) It should be limited to a few day's duration after the accident has occurred. 5) Special attention should be dedicated to the problems of - information and communications, - decision-taking procedures and translation of decicions into action, - practical realization of measures. 6) The bodies charged with planning and implementation must have appropriate personnel and material. 7) Only adequate exercises can guarantee planned disaster control measures to engage under conditions of severity. (HSCH) [de

  9. Methodology to determine the technical performance and value proposition for grid-scale energy storage systems :

    Energy Technology Data Exchange (ETDEWEB)

    Byrne, Raymond Harry; Loose, Verne William; Donnelly, Matthew K.; Trudnowski, Daniel J.

    2012-12-01

    As the amount of renewable generation increases, the inherent variability of wind and photovoltaic systems must be addressed in order to ensure the continued safe and reliable operation of the nation's electricity grid. Grid-scale energy storage systems are uniquely suited to address the variability of renewable generation and to provide other valuable grid services. The goal of this report is to quantify the technical performance required to provide di erent grid bene ts and to specify the proper techniques for estimating the value of grid-scale energy storage systems.

  10. Confronting Regulatory Cost and Quality Expectations. An Exploration of Technical Change in Minimum Efficiency Performance Standards

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, Margaret [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Stanford Univ., CA (United States); Spurlock, C. Anna [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Yang, Hung-Chia [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2015-09-21

    The dual purpose of this project was to contribute to basic knowledge about the interaction between regulation and innovation and to inform the cost and benefit expectations related to technical change which are embedded in the rulemaking process of an important area of national regulation. The area of regulation focused on here is minimum efficiency performance standards (MEPS) for appliances and other energy-using products. Relevant both to U.S. climate policy and energy policy for buildings, MEPS remove certain product models from the market that do not meet specified efficiency thresholds.

  11. Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-09-01

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

  12. Instituting a Surgical Skills Competition Increases Technical Performance of Surgical Clerkship Students Over Time.

    Science.gov (United States)

    Leraas, Harold J; Cox, Morgan L; Bendersky, Victoria A; Sprinkle, Shanna S; Gilmore, Brian F; Gunasingha, Rathnayaka M; Tracy, Elisabeth T; Sudan, Ranjan

    2017-10-04

    Surgical skills training varies greatly between institutions and is often left to students to approach independently. Although many studies have examined single interventions of skills training, no data currently exists about the implementation of surgical skills assessment as a component of the medical student surgical curriculum. We created a technical skills competition and evaluated its effect on student surgical skill development. Second-year medical students enrolled in the surgery clerkship voluntarily participated in a surgical skills competition consisting of knot tying, laparoscopic peg transfer, and laparoscopic pattern cut. Winning students were awarded dinner with the chair of surgery and a resident of their choice. Individual event times and combined times were recorded and compared for students who completed without disqualification. Disqualification included compromising cutting pattern, dropping a peg out of the field of vision, and incorrect knot tying technique. Timed performance was compared for 2 subsequent academic years using Mann-Whitney U test. Overall, 175 students competed and 71 students met qualification criteria. When compared by academic year, 2015 to 2016 students (n = 34) performed better than 2014 to 2015 students (n = 37) in pattern cut (133s vs 167s, p = 0.040), peg transfer (66s vs 101s, p skills competition improves student technical performance. Further research is needed regarding long-term benefits of surgical competitions for medical students. Copyright © 2017 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  13. Determination of technical and economic parameters of an ionic transport membrane air separation unit working in a supercritical power plant

    Directory of Open Access Journals (Sweden)

    Kotowicz Janusz

    2016-09-01

    Full Text Available In this paper an air separation unit was analyzed. The unit consisted of: an ionic transport membrane contained in a four-end type module, an air compressor, an expander fed by gas that remains after oxygen separation and heat exchangers which heat the air and recirculated flue gas to the membrane operating temperature (850 °C. The air separation unit works in a power plant with electrical power equal to 600 MW. This power plant additionally consists of: an oxy-type pulverized-fuel boiler, a steam turbine unit and a carbon dioxide capture unit. Life steam parameters are 30 MPa/650 °C and reheated steam parameters are 6 MPa/670 °C. The listed units were analyzed. For constant electrical power of the power plant technical parameters of the air separation unit for two oxygen recovery rate (65% and 95% were determined. One of such parameters is ionic membrane surface area. In this paper the formulated equation is presented. The remaining technical parameters of the air separation unit are, among others: heat exchange surface area, power of the air compressor, power of the expander and auxiliary power. Using the listed quantities, the economic parameters, such as costs of air separation unit and of individual components were determined. These quantities allowed to determine investment costs of construction of the air separation unit. In addition, they were compared with investment costs for the entire oxy-type power plant.

  14. Use of PSA Level 2 analysis for improving containment performance. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1998-03-01

    In order to discuss and exchange experience on different aspects of methods associated with Level 2 PSA and its applications for improving containment performance, the IAEA held a Technical Committee meeting in Vienna in December 1996. The meeting, which was attended by 26 participants from 20 Member States, provided a broad forum for discussion. The meeting addressed the issues related to the actual performance of Level 2 PSA studies as well as the insights gained from applications to improve containment performance. Particular attention was given to studies and applications for WWER type reactors, for which Level 2 work is still in its early stages, and for channel type reactors where modelling of accident progression is complex and significantly different from vessel type light water reactors. This TECDOC contains the papers presented at the meeting and the results of extensive discussions which were held in specific working groups

  15. Structure of technical systems: interpersonal networks and performance in nuclear waste and photovoltaic research

    International Nuclear Information System (INIS)

    Shrum, W.M. Jr.

    1982-01-01

    The organization of scientific technology in modern, industrialized societies is examined by comparing two large-scale, multi-organizational, mission-oriented research networks. Using national data from personal interviews with 297 scientists, engineers, research managers, and policy makers from 97 organizations involved in nuclear waste management and solar-photovoltaic development, this study develops and tests hypotheses on the relationships among governmental, academic, private, and public interest sectors and the kinds of social linkages which are associated with technical performance. The principal finding is that in photovoltaic research, contacts with the research community are associated with high levels of performance, while for nuclear waste researchers, they are not. Instead, linkages to the governmental sector predict performance in nuclear waste research. This difference is explained by the governmental domination of the nuclear-waste system and the lack of private-sector involvement

  16. Performance evaluation of effluent treatment plant for automobile industry

    Energy Technology Data Exchange (ETDEWEB)

    Ansari, Farid [Department of Applied Science and Humanities, PDM College of Engineering, Bahadurgarh (Haryana) (India); Pandey, Yashwant K. [School of Energy and Environmental Studies, Devi Ahilya Vishwavidyalaya, Indore (India); Kumar, P.; Pandey, Priyanka [Department of Environmental Science, Post Graduate College Ghazipur (IN

    2013-07-01

    The automobile industry’s wastewater not only contains high levels of suspended and total solids such as oil, grease, dyestuff, chromium, phosphate in washing products, and coloring, at various stages of manufacturing but also, a significant amount of dissolved organics, resulting in high BOD or COD loads. The study reveals the performance, evaluation and operational aspects of effluent treatment plant and its treatability, rather than the contamination status of the real property. The Results revealed that the treated effluent shows most of the parameters are within permissible limits of Central Pollution Control Board (CPCB), India and based on the site visits, discussion with operation peoples, evaluation of process design, treatment system, existing effluent discharge, results of sample analyzed and found that effluent treatment plant of automobile industry are under performance satisfactory.

  17. An innovative fuel design concept for improved light water reactor performance and safety. Final technical report

    International Nuclear Information System (INIS)

    Tulenko, J.S.; Connell, R.G.

    1995-07-01

    Light water reactor (LWR) fuel performance is limited by thermal and mechanical constraints associated with the design, fabrication, and operation of fuel in a nuclear reactor. The purpose of this research was to explore a technique for extending fuel performance by thermally bonding LWR fuel with a non-alkaline liquid metal alloy. Current LWR fuel rod designs consist of enriched uranium oxide (UO 2 ) fuel pellets enclosed in a zirconium alloy cylindrical clad. The space between the pellets and the clad is filled by an inert gas. Due to the thermal conductivity of the gas, the gas space thermally insulates the fuel pellets from the reactor coolant outside the fuel rod, elevating the fuel temperatures. Filling the gap between the fuel and clad with a high conductivity liquid metal thermally bonds the fuel to the cladding, and eliminates the large temperature change across the gap, while preserving the expansion and pellet loading capabilities. The resultant lower fuel temperature directly impacts fuel performance limit margins and also core transient performance. The application of liquid bonding techniques to LWR fuel was explored for the purposes of increasing LWR fuel performance and safety. A modified version of the ESCORE fuel performance code (ESBOND) has been developed under the program to analyze the in-reactor performance of the liquid metal bonded fuel. An assessment of the technical feasibility of this concept for LWR fuel is presented, including the results of research into materials compatibility testing and the predicted lifetime performance of Liquid Metal Bonded LWR fuel

  18. Advanced digital technology - improving nuclear power plant performance through maintainability

    International Nuclear Information System (INIS)

    Ford, J.L.; Senechal, R.R.; Altenhein, G.D.; Harvey, R.P.

    1998-01-01

    In today's energy sector there is ever increasing pressure on utilities to operate power plants at high capacity factors. To ensure nuclear power is competitive into the next century, it is imperative that strategic design improvements be made to enhance the performance of nuclear power plants. There are a number of factors that affect a nuclear power plant's performance; lifetime maintenance is one of the major contributors. The maturing of digital technology has afforded ABB the opportunity to make significant design improvements in the area of maintainability. In keeping with ABB's evolutionary advanced nuclear plant design approach, digital technology has systematically been incorporated into the control and protection systems of the most recent Korean nuclear units in operation and under construction. One example of this was the multi-functional design team approach that was utilized for the development of ABB's Digital Plant Protection System (DPPS). The design team consisted of engineers, maintenance technicians, procurement specialists and manufacturing personnel in order to provide a complete perspective on all facets of the design. The governing design goals of increased reliability and safety, simplicity of design, use of off-the-shelf products and reduced need for periodic surveillance testing were met with the selection of proven ABB-Advant Programmable Logic Controllers (PLCs) as the heart of the DPPS. The application of digital PLC technology allows operation for extended periods without requiring routine maintenance or re-calibration. A well documented commercial dedication program approved by the United States Nuclear Regulatory Commission (US NRC) as part of the System 80+ TM Advanced Light Water Reactor Design Certification Program, allowed the use of off-the shelf products in the design of the safety protection system. In addition, a number of mechanical and electrical improvements were made which support maintainability. The result is a DPPS

  19. Methodological guide for the follow-up and elaboration of performance assessments of a methanization plant

    International Nuclear Information System (INIS)

    Bastide, Guillaume

    2014-06-01

    This guide aims at giving indications required for a good implementation of an exploitation follow-up of a methanization plant. More precisely, it aims at foreseeing equipment necessary to the follow-up of installation construction, at preparing the operator to the follow-up and command of his installation, at elaborating operation assessments and performance interpretations, at proposing solutions and/or improvements. The described follow-up process can be applied to all the process stages (from receipt to by-product valorization), and addresses technical as well as economic aspects. Thus, four types of assessments are made: technical, energetic, environmental, and social-economic. This guide comprises five parts: a presentation of follow-up objectives (information to be looked for, benefits and drawbacks, follow-up level to be implemented), the follow-up methodology, follow-up assessments (what they are and how to elaborate them), practical sheets (practical presentation of techniques, typical Excel spreadsheets), and a glossary which explains the main technical terms

  20. The development and use of plant models to assist with both the commissioning and performance optimisation of plant control systems

    International Nuclear Information System (INIS)

    Conner, A.S.; Region, S.E.

    1984-01-01

    Successful engagement of cascade control systems used to control complex nuclear plant often present control engineers with difficulties when trying to obtain early automatic operation of these systems. These difficulties often arise because prior to the start of live plant operation, control equipment performance can only be assessed using open loop techniques. By simulating simple models of plant on a computer and linking it to the site control equipment, the performance of the system can be examined and optimised prior to live plant operation. This significantly reduces the plant down time required to correct control equipment performance faults during live plant operation

  1. Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

    Energy Technology Data Exchange (ETDEWEB)

    Kim, I.S.; Samanta, P.K. [Brookhaven National Lab., Upton, NY (United States); Mankamo, T.

    1995-04-01

    When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require {open_quotes}immediate{close_quotes} shutdown of the plant. In this paper, we present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion.

  2. Acceptability analysis of technical-scale plants for electricity generation; Ansatz zur Akzeptabilitaetsanalyse grosstechnischer Anlagen zur Stromerzeugung

    Energy Technology Data Exchange (ETDEWEB)

    Schubert, Katharina; Koch, Marco K. [Bochum Univ. (Germany). AG Reaktorsimulation und -sicherheit

    2013-03-15

    Public acceptance of technical-scale plants for electricity generation is an indispensable prerequisite for the long-term continuity of supply of electricity. Even though nuclear power in Germany continues to meet with particularly grave objections, this is no longer an exception. Problems associated with the rapidly declining willingness of the public to accept specific disadvantages connected with electricity generation are confronting not only nuclear, but also large fossil-fired and renewable-resource power plants. To investigate to what extent these objections based on subjective heuristics are justified, a model is developed for analyzing the objective acceptability of electricity-producing large power plants, which allows the assessment of their acceptability to be measured on the basis of quantitative analysis of the discrepancies between acceptability and acceptance and may serve as a tool for promoting public acceptance. (orig.)

  3. Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

    International Nuclear Information System (INIS)

    Kim, I.S.; Samanta, P.K.

    1994-01-01

    When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require ''immediate'' shutdown of the plant. In this paper, the authors present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion

  4. Technical and economical aspects of a large and a small plant for irradiation of liquid waste

    International Nuclear Information System (INIS)

    Herrnhut, H.; Marsch, U.; Bosshard, E.

    1976-01-01

    Description of the further development of the irradiation plant for sewage sludge which is in operation at the sewage water treatment plant of the Abwasserverband Ampergruppe at Geiselbullach. Taking into consideration the operating experience, the conception of the plant was optimized, the design was simplified. The loading and reloading of the radioactive sources could now be carried out during operation of the plant. The economical aspects were considered too and the calculated cost of the treatment was summarized in a table. (author)

  5. 75 FR 62096 - Agricultural Technical Advisory Committees for Trade in Tobacco, Cotton, Peanuts and Planting...

    Science.gov (United States)

    2010-10-07

    ... many of the issues that the GFO committee addresses, such as genetically modified organisms, new... modifying the existing structure of both the Agricultural Technical Advisory Committees (ATAC) for Trade in...

  6. Independent technical review of the Bin and Alcove test programs at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-12-01

    This Independent Technical Review (ITR) assessed the need for and technical validity of the proposed Bin and Alcove test programs using TRU-waste at the WIPP site. The ITR Team recommends that the planned Bin and Alcove tests be abandoned, and that new activities be initiated in support of the WIPP regulatory compliance processes. Recommendations in this report offer an alternate path for expeditiously attaining disposal certification and permitting

  7. Fuel performance experience at TVO nuclear power plant

    International Nuclear Information System (INIS)

    Patrakka, E.T.

    1985-01-01

    TVO nuclear power plant consists of two BWR units of ASEA-ATOM design. The fuel performance experience extending through six cycles at TVO I and four cycles at TVO II is reported. The experience obtained so far is mainly based on ASEA-ATOM 8 x 8 fuel and has been satisfactory. Until autumn 1984 one leaking fuel assembly had been identified at TVO I and none at TVO II. Most of the problems encountered have been related to leaf spring screws and channel screws. The experience indicates that satisfactory fuel performance can be achieved when utilizing strict operational rules and proper control of fuel design and manufacture. (author)

  8. Technical specifications, Vogtle Electric Generating Plant, Unit No. 1 (Docket No. 50-424): Appendix ''A'' to license No. NPF-61

    International Nuclear Information System (INIS)

    1987-01-01

    This technical specifications report presents information concerning the Vogtle Electric Generating Plant in the following areas: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  9. Effect of obstetric team training on team performance and medical technical skills: a randomised controlled trial.

    Science.gov (United States)

    Fransen, A F; van de Ven, J; Merién, A E R; de Wit-Zuurendonk, L D; Houterman, S; Mol, B W; Oei, S G

    2012-10-01

    To determine whether obstetric team training in a medical simulation centre improves the team performance and utilisation of appropriate medical technical skills of healthcare professionals. Cluster randomised controlled trial. The Netherlands. The obstetric departments of 24 Dutch hospitals. The obstetric departments were randomly assigned to a 1-day session of multiprofessional team training in a medical simulation centre or to no such training. Team training was given with high-fidelity mannequins by an obstetrician and a communication expert. More than 6 months following training, two unannounced simulated scenarios were carried out in the delivery rooms of all 24 obstetric departments. The scenarios, comprising a case of shoulder dystocia and a case of amniotic fluid embolism, were videotaped. The team performance and utilisation of appropriate medical skills were evaluated by two independent experts. Team performance evaluated with the validated Clinical Teamwork Scale (CTS) and the employment of two specific obstetric procedures for the two clinical scenarios in the simulation (delivery of the baby with shoulder dystocia in the maternal all-fours position and conducting a perimortem caesarean section within 5 minutes for the scenario of amniotic fluid embolism). Seventy-four obstetric teams from 12 hospitals in the intervention group underwent teamwork training between November 2009 and July 2010. The teamwork performance in the training group was significantly better in comparison to the nontraining group (median CTS score: 7.5 versus 6.0, respectively; P = 0.014). The use of the predefined obstetric procedures for the two clinical scenarios was also significantly more frequent in the training group compared with the nontraining group (83 versus 46%, respectively; P = 0.009). Team performance and medical technical skills may be significantly improved after multiprofessional obstetric team training in a medical simulation centre. © 2012 The Authors BJOG An

  10. Performance Assesment of Bauchi Polytechnics and Technical Colleges Using Quality Assurance Indicators in Nigeria Qualification Framework

    Directory of Open Access Journals (Sweden)

    Idris Adamu

    2016-07-01

    Full Text Available Technical and Vocational Education emphases skill acquisition, Quality Assurance in vocational education is concept that is concerned with high performance involved activities with vocational education such as teaching, learning, infrastructures, student’s behavior and entire academic process. Good quality education is very necessary in the total development of staff and students which ensures proper development, job prospects and the realization of academic goals and objects. Enhanced and sustained to ensure accountability and improve performance. Higher educational institutions in Nigeria continue to experience carelessly attitude about the use of Quality Assurance to understand the risk they are exposed to poor standard. To address these issues, the study embarked upon to determine the level of performance and difference usability of Quality Assurance in Polytechnics and Technical Colleges in Bauchi state. Quantitative method technique was employed using survey questionnaires, 60 staff both senior and junior within these institutions were selected and a questionnaire distributed for their responses. The data were analysed using SPSS software. The result reveals that Federal Polytechnic Bauchi and State Polytechnic Bauchi has high level of Performance about Quality Assurance indicators while College of Education Azare has medium level of Performance. College of education Azare has highest mean rank of 29.87 and percentage of 31.8% obtained from the output result indicated that it has high usability to Quality Assurance, followed by Federal Polytechnic Bauchi with medium usability then State Polytechnic Bauchi has low usability to Quality Assurance. The study concluded by Quality Assurance Unit be made aware to each institution staff to enable recognize the benefits of it. Federal government should give more funding and employ staff to cater the need of Quality Assurance Unit in every institution so that it will help the students to develop

  11. Technical notes for the conceptual design for an atmospheric fluidized-bed direct combustion power generating plant. [570 MWe plant

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-04-01

    The design, arrangement, thermodynamics, and economics of a 592 MW(e) (nominal gross) electric power generating plant equipped with a Babcock and Wilcox Company (B and W) atmospheric fluidized bed (AFB) boiler are described. Information is included on capital and operating costs, process systems, electrical systems, control and instrumentation, and environmental systems. This document represents a portion of an overall report describing the conceptual designs of two atmospheric fluidized bed boilers and balance of plants for the generation of electric power and the analysis and comparison of these conceptual designs to a conventional pulverized coal-fired electric power generation plant equipped with a wet limestone flue gas desulfurization system.

  12. Technical notes for the conceptual design for an atmospheric fluidized-bed direct combustion power generating plant. [570 MWe plant

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-04-01

    The design, arrangement, thermodynamics, and economics of a 578 MW(e) (nominal gross) electric power generating plant equipped with a Foster Wheeler Energy Corporation (FWEC) atmospheric fluidized bed (AFB) boiler are described. Information is included on capital and operating costs, process systems, electrical systems, control and instrumentation, and environmental systems. This document represents a portion of an overall report describing the conceptual designs of two atmospheric fluidized bed boilers and balance of plants for the generation of electric power and the analysis and comparison of these conceptual designs to a conventional pulverized coal-fired electric power generation plant equipped with a wet limestone flue gas desulfurization system.

  13. Proceedings of a NEA/CSNI-UNIPEDE specialist meeting on improving technical specifications for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-07-01

    This CSNI specialist meeting on improving technical specifications for nuclear power plants is sponsored by the OECD Nuclear Energy Agency jointly with UNIPEDE. Technical specifications for nuclear power plants are in a way a prescription which has a direct bearing on the success or failure of the particular installation, and on the success or failure of fission energy around the world. It is therefore highly important that these prescriptions are made as clear and as concise as possible and that it distinguishes requirements which are essential for public health and safety, from the many others which are less important accordingly. The conference was held in september 1987 in madrid (Spain); it is composed of about 40 papers grouped into 8 sessions: invited papers (6 papers), international survey results (1 paper), limiting conditions for operation (8 papers), maintenance and testing (4 papers), actions statements and allowed outage times (8 papers), methodology and technical justification (8 papers), future trends and alternative approaches (4 papers), and a final panel

  14. Technical Quality of Root Fillings Performed by Undergraduate Students: A Radiographic Study

    Directory of Open Access Journals (Sweden)

    Tatjana Vukadinov

    2014-01-01

    Full Text Available Aim. The aim of this study was to evaluate the radiographic technical quality of endodontic treatment performed by undergraduate students at the School of Dentistry, Faculty of Medicine, University of Novi Sad, Serbia. Materials and Methods. Electronic records of 220 patients treated by final-year undergraduate students during the school year 2011/2012 were examined, and the final sample consisted of 212 patients, 322 teeth, and 565 root canals. The criteria for overall radiographic adequacy of root canal fillings were defined as the presence of adequate length and density and absence of iatrogenic errors (ledge, fractured instrument, untreated canal, and apical transportation. Chi-square test was used to determine statistical significance between different parameters. Results. Adequate root canal fillings were found in 74.22% of the teeth. The percentage of root fillings with adequate length and density was 89.73% and 92.6%, respectively. Fractured instruments and ledges were present in 16 root canals (2.8%, while the presence of missed canal and apical transportation was observed in 2 cases, each (0.3%. Conclusions. Overall, the technical quality of root canal fillings performed by undergraduate students was satisfactory.

  15. IMPROVEMENT OF SYSTEMS OF TECHNICAL WATER SUPPLY WITH COOLING TOWERS FOR STEAM POWER PLANTS TECHNICAL AND ECONOMIC INDICATORS PERFECTION. Part 1

    Directory of Open Access Journals (Sweden)

    Yu. A. Zenovich-Leshkevich-Olpinskiy

    2016-01-01

    Full Text Available In order to reduce the temperature of cooling water and increase the efficiency of use of power resources the main directions of modernization of systems of technical water supply with cooling towers at steam power plants are presented. The problems of operation of irrigation systems and water distribution systems of cooling towers are reviewed. The design of heat and mass transfer devices, their shortcomings and the impact on the cooling ability of the cooling tower are also under analysis. The use of droplet heat and mass transfer device based on the lattice polypropylene virtually eliminates the shortcomings of the film and droplet-film heat and mass transfer devices of the cooling tower, increasing lifetime, and improving the reliability and efficiency of the operation of the main equipment of thermal power plants. The design of the water distribution devices of cooling towers is also considered. It is noted that the most effective are water-spattering low-pressure nozzles made of polypropylene that provides uniform dispersion of water and are of a high reliability and durability.

  16. Management of life cycle and ageing at nuclear power plants: Improved I and C maintenance. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2004-08-01

    The topic of this TECDOC was originally suggested in the May 2001 meeting of the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG NPPCI). It was then approved by the IAEA for work to begin in 2002. It originated from the remarks of the TWG members that it is now time to address the instrumentation and control (I and C) ageing issues in terms of plant life management and licence renewal. Furthermore, the nuclear industry is believed to be able to survive only if plant economy is favourable in addition to plant safety. Therefore, in dealing with I and C ageing and obsolescence, one has to consider how to proceed in addressing this question, not only from a plant operational and safety standpoint, but also in the context of plant economy in terms of the cost of electricity production, and including initial and recurring capital costs. For this important reason, consideration of new technologies, such as on-line monitoring and in situ testing methods is recommended. These can be used not only to predict the consequences of ageing, and guard against it, but also to verify equipment performance throughout the lifetime of the plant, and help establish replacement schedules for I and C equipment, and predict residual life. The basic ageing and obsolescence management process involves: Understanding the ageing and obsolescence phenomena and identifying the (potential) effects on I and C; Addressing the specific impact of these effects on the plant taking into account operational profiles and analyzing the risks; Carrying out necessary mitigating actions to counteract the effects of ageing and obsolescence. Based on the above listed activities the ageing and obsolescence management programme needs to be an iterative process. The goal of this TECDOC is to provide the latest information on ageing, obsolescence, and performance monitoring of those I and C equipment that are classified as safety equipment and/or safety-related equipment, are

  17. Process auditing and performance improvement in a mixed wastewater-aqueous waste treatment plant.

    Science.gov (United States)

    Collivignarelli, Maria Cristina; Bertanza, Giorgio; Abbà, Alessandro; Damiani, Silvestro

    2018-02-01

    The wastewater treatment process is based on complex chemical, physical and biological mechanisms that are closely interconnected. The efficiency of the system (which depends on compliance with national regulations on wastewater quality) can be achieved through the use of tools such as monitoring, that is the detection of parameters that allow the continuous interpretation of the current situation, and experimental tests, which allow the measurement of real performance (of a sector, a single treatment or equipment) and comparison with the following ones. Experimental tests have a particular relevance in the case of municipal wastewater treatment plants fed with a strong industrial component and especially in the case of plants authorized to treat aqueous waste. In this paper a case study is presented where the application of management tools such as careful monitoring and experimental tests led to the technical and economic optimization of the plant: the main results obtained were the reduction of sludge production (from 4,000 t/year w.w. (wet weight) to about 2,200 t/year w.w.) and operating costs (e.g. from 600,000 €/year down to about 350,000 €/year for reagents), the increase of resource recovery and the improvement of the overall process performance.

  18. Good practices for improved nuclear power plant performance

    International Nuclear Information System (INIS)

    1989-04-01

    This report provides an overview of operational principles, practice and improvements which have contributed to good performance of eight selected world nuclear power stations. The IAEA Power Reactor Information System (PRIS) was used to identify a population of good performers. It is recognized that there are many other good performing nuclear power stations not included in this report. Specific criteria described in the introduction were used in selecting these eight stations. The information contained in this report was obtained by the staff from IAEA, Division of Nuclear Power. This was accomplished by visits to the stations and visits to a number of utility support groups and three independent organizations which provide support to more than one utility. The information in this report is intended as an aid for operating organizations to identify possible improvement initiatives to enhance plant performance. Figs and tabs

  19. Modernization of the automation control system of technological processes at the preparation plant in the conditions of technical re-equipment

    Science.gov (United States)

    Lyakhovets, M. V.; Wenger, K. G.; Myshlyaev, L. P.; Shipunov, M. V.; Grachev, V. V.; Melkozerov, M. Yu; Fairoshin, Sh A.

    2018-05-01

    The experience of modernization of the automation control system of technological processes at the preparation plant under the conditions of technical re-equipment of the preparation plant “Barzasskoye Tovarischestvo” LLC (Berezovsky) is considered. The automated process control systems (APCS), the modernization goals and the ways to achieve them are indicated, the main subsystems of the integrated APCS are presented, the enlarged functional and technical structure of the upgraded system is given. The procedure for commissioning an upgraded system is described.

  20. Nuclear power plant thermal-hydraulic performance research program plan

    International Nuclear Information System (INIS)

    1988-07-01

    The purpose of this program plan is to present a more detailed description of the thermal-hydraulic research program than that provided in the NRC Five-Year Plan so that the research plan and objectives can be better understood and evaluated by the offices concerned. The plan is prepared by the Office of Nuclear Regulatory Research (RES) with input from the Office of Nuclear Reactor Regulation (NRR) and updated periodically. The plan covers the research sponsored by the Reactor and Plant Systems Branch and defines the major issues (related to thermal-hydraulic behavior in nuclear power plants) the NRC is seeking to resolve and provides plans for their resolution; relates the proposed research to these issues; defines the products needed to resolve these issues; provides a context that shows both the historical perspective and the relationship of individual projects to the overall objectives; and defines major interfaces with other disciplines (e.g., structural, risk, human factors, accident management, severe accident) needed for total resolution of some issues. This plan addresses the types of thermal-hydraulic transients that are normally considered in the regulatory process of licensing the current generation of light water reactors. This process is influenced by the regulatory requirements imposed by NRC and the consequent need for technical information that is supplied by RES through its contractors. Thus, most contractor programmatic work is administered by RES. Regulatory requirements involve the normal review of industry analyses of design basis accidents, as well as the understanding of abnormal occurrences in operating reactors. Since such transients often involve complex thermal-hydraulic interactions, a well-planned thermal-hydraulic research plan is needed

  1. Technical analysis of magneto-inductive crane cables in nuclear power plants. Application crane Cofrentes Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gavilan Moreno, C. J.

    2010-01-01

    In 2009, the Cofrentes Nuclear Power Plant made a study about crane inspection techniques available on the market and other industries. The result was the location of the magneto-inductive technique inspection. Its use provides an objective assessment of the resistant section and; through these data; it could be made calculations as the maximum voltage allowed. Therefore, the technique is proven and available to all nuclear power plants.

  2. Proceedings from the technical workshop on near-field performance assessment for high-level waste

    International Nuclear Information System (INIS)

    Sellin, P.; Apted, M.; Gago, J.

    1991-12-01

    This report contains the proceedings of 'Technical workshop of near-filed performance assessment for high-level waste' held in Madrid October 15-17, 1990. It includes the invited presentations and summaries of the scientific discussions. The workshop covered several topics: * post-emplacement environment, * benchmarking of computer codes, * glass release, * spent-fuel release, * radionuclide solubility, * near-field transport processes, * coupled processes in the near-field, * integrated assessments, * sensitivity analyses and validation. There was an invited presentation on each topic followed by an extensive discussion. One of the points highlighted in the closing discussion of the workshop was the need for international cooperation in the field of near-field performance assessment. The general opinion was that this was best achieved in smaller groups discussing specific questions. (au) Separate abstracts were prepared for 9 papers in this volume

  3. Effects of Performance-Based Financial Incentives on Work Performance: A Study of Technical-Level Employees in the Private Sector in Sri Lanka

    Science.gov (United States)

    Wickramasinghe, Vathsala; Dabere, Sampath

    2012-01-01

    The objective of the study is to investigate the effect of performance-based financial incentives on work performance. The study hypothesized that the design features of performance-based financial incentive schemes themselves may influence individuals' work performance. For the study, survey methodology was used and 93 technical-level employees…

  4. Technical Review of Operator's Destructive Analyses at the Rokkasho Reprocessing Plant: Strengthening the Transparency of the Operator's Measurement System

    International Nuclear Information System (INIS)

    Sato, N.; Katchi, T.; Niitsu, Y.; Duhamel, G.; Decaillon, J.-G.; Toervenyi, A.; Sayama, H.; Hara, S.

    2015-01-01

    The Rokkasho Reprocessing Plant is a large-scale nuclear facility in Japan. For the purposes of process control, product management and nuclear material accountancy for safeguards purposes, the laboratory of the facility operator analyzes thousands of samples from various process streams and with a multitude of matrices. Transparency of operational procedures, quality control measures and sample analytical results among the facility operator and state and international safeguards authorities are required to assess the facility operator's measurement system, and thus to assure a credible safeguards approach. The facility operator, Japan Nuclear Fuel, Limited (JNFL), is engaged in continuous improvement of its nuclear material analyzes. For the declarations to the inspectorates, it is important that JNFL and the safeguards authorities be able to confirm that the analytical methods used by JNFL are reliable and meet the latest version of the International Target Values. Since 2012 JNFL, the IAEA and the SSAC have carried out several technical reviews of the destructive analysis (DA) processes as a means of strengthening the transparency of the DA measurement systems. The goal of the DA technical reviews is to (1) assess past commitments of the JNFL plan for analytical improvement, (2) review the JNFL Quality System by means of documentation reviews and in-field demonstrations, and (3) review the analytical performance of the JNFL lab through its own results or from inter-laboratory comparison exercises. Throughout this process, subject-matter experts from all organizations met with JNFL laboratory staff and discussed analytical concerns and solutions. The outcome of these technical reviews was a series of recommendations to JNFL for strengthening its plan for continuous improvement. This paper presents the methodology of the DA technical reviews, the communication scheme and some examples of the outcome for JNFL to improve its DA methods and analytical

  5. Assessment of Human Performance and Safety Culture at the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Toth, Janos; Hadnagy, Lajos

    2002-01-01

    Evaluation of human performance and safety culture of the personnel at a Nuclear Power Plant is a very important element of the self assessment process. At the Paks NPP a systematic approach to this problem started in the early 90's. The first comprehensive analysis of the human performance of the personnel was performed by the Hungarian Research Institute for Electric Power (VEIKI). The analysis of human failures is also a part of the investigation and analysis of safety related reported events. This human performance analysis of events is carried out by the Laboratory of Psychology of the plant and a supporting organisation namely the Department of Ergonomics and Psychology of the Budapest University of Technical and Economical Sciences. The analysis of safety culture at the Paks NPP has been in the focus of attention since the implementation of the INSAG-4 document started world-wide. In 1993 an IAEA model project namely 'Strengthening Training for Operational Safety' was initiated with a sub-project called 'Enhancement of Safety Culture'. Within this project the first step was the initial assessment of the safety culture level at the Paks NPP. It was followed by some corrective actions and safety culture improvement programme. In 1999 the second assessment was performed in order to evaluate the progress as a result of the improvement programme. A few indicators reflecting the elements of safety culture were defined and compared. The assessment of the safety culture with a survey among the managers was performed in September 2000 and the results are being evaluated at the moment. The intention of the plant management is to repeat the assessment every 2-3 years and evaluate the trend of the indicator. (authors)

  6. Replacing fossil based plastic performance products by bio-based plastic products-Technical feasibility.

    Science.gov (United States)

    van den Oever, Martien; Molenveld, Karin

    2017-07-25

    Larger scale market introduction of new bio-based products requires a clear advantage regarding sustainability, as well as an adequate techno-economic positioning relative to fossil based products. In a previous paper [Broeren et al., 2016], LCA results per kg and per functionality equivalent of bio-based plastics were presented, together with economic considerations. The present paper discusses the mechanical and thermal properties of a range of commercially available bio-based plastics based on polylactic acid (PLA), cellulose esters, starch and polyamides, and the feasibility of replacing fossil-based counterparts based on performance. The evaluation is approached from an end user perspective. First, potentially suitable bio-based plastics are selected based on manufacturers' specifications in technical data sheets, then a first experimental evaluation is performed on injection moulded ISO specimens, and finally a further selection of plastics is tested on large 50×70cm panels. This technical feasibility study indicates that so far bio-based plastics do not completely match the properties of high performance materials like flame retardant V-0 PC/ABS blends used in electronic devices. The performance gap is being decreased by the development of stereocomplex PLA and hybrid PLA blends with polycarbonate, which offer clearly improved properties with respect to maximum usage temperature and toughness. In addition, several materials meet the V-0 flammability requirements needed in specific durable applications. On the other hand, improving these properties so far has negative consequences for the bio-based content. This study also shows that replacement of bulk polymers like PS is feasible using PLA compounds with a bio-based content as high as 85%. Copyright © 2016 Elsevier B.V. All rights reserved.

  7. The impact of fatigue on the non-technical skills performance of critical care air ambulance clinicians.

    Science.gov (United States)

    Myers, J A; Powell, D M C; Aldington, S; Sim, D; Psirides, A; Hathaway, K; Haney, M F

    2017-11-01

    The relationship between fatigue-related risk and impaired clinical performance is not entirely clear. Non-technical factors represent an important component of clinical performance and may be sensitive to the effects of fatigue. The hypothesis was that the sum score of overall non-technical performance is degraded by fatigue. Nineteen physicians undertook two different simulated air ambulance missions, once when rested, and once when fatigued (randomised crossover design). Trained assessors blinded to participants' fatigue status performed detailed structured assessments based on expected behaviours in four non-technical skills domains: teamwork, situational awareness, task management, and decision making. Participants also provided self-ratings of their performance. The primary endpoint was the sum score of overall non-technical performance. The main finding, the overall non-technical skills performance rating of the clinicians, was better in rested than fatigued states (mean difference with 95% CI, 2.8 [2.2-3.4]). The findings remained consistent across individual non-technical skills domains; also when controlling for an order effect and examining the impact of a number of possible covariates. There was no difference in self-ratings of clinical performance between rested and fatigued states. Non-technical performance of critical care air transfer clinicians is degraded when they are fatigued. Fatigued clinicians may fail to recognise the degree to which their performance is compromised. These findings represent risk to clinical care quality and patient safety in the dynamic and isolated environment of air ambulance transfer. © 2017 The Acta Anaesthesiologica Scandinavica Foundation. Published by John Wiley & Sons Ltd.

  8. Temporal Changes in Technical and Physical Performances During a Small-Sided Game in Elite Youth Soccer Players.

    Science.gov (United States)

    Moreira, Alexandre; Saldanha Aoki, Marcelo; Carling, Chris; Alan Rodrigues Lopes, Rafael; Felipe Schultz de Arruda, Ademir; Lima, Marcelo; Cesar Correa, Umberto; Bradley, Paul S

    2016-12-01

    There have been claims that small-sided games (SSG) may generate an appropriate environment to develop youth players' technical performance associated to game-related problem solving. However, the temporal change in technical performance parameters of youth players during SSG is still unknown. The aim of this study was to examine temporal changes in technical and physical performances during a small-sided game (SSG) in elite soccer players. Sixty elite youth players (age 14.8 ± 0.2 yr; stature 177 ± 5 cm; body mass 66.2 ± 4.7 kg) completed a 5 v 5 SSG using two repetitions of 8 minutes interspersed by 3 minutes of passive recovery. To evaluate temporal changes in performance, the data were analysed across 4 minutes quarters. Physical performance parameters included the total distance covered (TDC), the frequency of sprints (>18 km•h -1 ), accelerations and decelerations (> 2.0 m•s -2 and - 2.0 m•s -2 ), metabolic power (W•kg -1 ), training impulse (TRIMP), TDC: TRIMP, number of impacts, and body load. Technical performance parameters included goal attempts, total number of tackles, tackles and interceptions, total number of passes, and passes effectiveness. All physical performance parameters decreased from the first to the last quarter with notable declines in TDC, metabolic power and the frequency of sprints, accelerations and decelerations (P performance parameters did not vary across quarters (P > 0.05; trivial ES for 1st v 4th quarters: 0.15 - 0.33). The data demonstrate that technical performance is maintained despite substantial declines in physical performance during a SSG in elite youth players. This finding may have implications for designing SSG's for elite youth players to ensure physical, technical and tactical capabilities are optimized. Modifications in player number, pitch dimensions, rules, coach encouragement, for instance, should be included taking into account the main aim of a given session and then focused on overloading physical or

  9. The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Gunther, W.; Martinez-Guridi, G.

    2010-01-01

    New and advanced reactors will use integrated digital instrumentation and control (I and C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I and C systems on human performance and plant operations. The objective was to develop human factors engineering (HFE) review guidance addressing the detection and management of degraded digital I and C conditions by plant operators. We reviewed pertinent standards and guidelines, empirical studies, and plant operating experience. In addition, we conducted an evaluation of the potential effects of selected failure modes of the digital feedwater system on human-system interfaces (HSIs) and operator performance. The results indicated that I and C degradations are prevalent in plants employing digital systems and the overall effects on plant behavior can be significant, such as causing a reactor trip or causing equipment to operate unexpectedly. I and C degradations can impact the HSIs used by operators to monitor and control the plant. For example, sensor degradations can make displays difficult to interpret and can sometimes mislead operators by making it appear that a process disturbance has occurred. We used the information obtained as the technical basis upon which to develop HFE review guidance. The guidance addresses the treatment of degraded I and C conditions as part of the design process and the HSI features and functions that support operators to monitor I and C performance and manage I and C degradations when they occur. In addition, we identified topics for future research.

  10. The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J.M.; W. Gunther, G. Martinez-Guridi

    2010-02-26

    New and advanced reactors will use integrated digital instrumentation and control (I&C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I&C systems on human performance and plant operations. The objective was to develop human factors engineering (HFE) review guidance addressing the detection and management of degraded digital I&C conditions by plant operators. We reviewed pertinent standards and guidelines, empirical studies, and plant operating experience. In addition, we conducted an evaluation of the potential effects of selected failure modes of the digital feedwater system on human-system interfaces (HSIs) and operator performance. The results indicated that I&C degradations are prevalent in plants employing digital systems and the overall effects on plant behavior can be significant, such as causing a reactor trip or causing equipment to operate unexpectedly. I&C degradations can impact the HSIs used by operators to monitor and control the plant. For example, sensor degradations can make displays difficult to interpret and can sometimes mislead operators by making it appear that a process disturbance has occurred. We used the information obtained as the technical basis upon which to develop HFE review guidance. The guidance addresses the treatment of degraded I&C conditions as part of the design process and the HSI features and functions that support operators to monitor I&C performance and manage I&C degradations when they occur. In addition, we identified topics for future research.

  11. Setting technical and economic features regarding nuclear heating plants implementation for heat supply in Romania by the year 2010

    International Nuclear Information System (INIS)

    Romascu, G.; Constantin, L.; Gheorghe, A.; Ciocanescu, M.; Ionescu, M.

    2008-01-01

    This paper presents the world wide preoccupation concerning the implementation of nuclear heating plants for fulfilling the heat demand and the main technical data of the reactors destined to such NHP's. The second part of this paper shows technical and economic aspects related to the implementation of NHP's equipped with nuclear thermal reactor specialized in the exclusive heat supply in Romania at the level of the year 2010. Among these aspects the following are mentioned: - the results of researches and the world wide achievements; - the development and structure of the production and of the thermal electric energy as well as the feasibility for covering the demands for nuclear sources; - the impact on environment of various technologies for the production of thermal energy with conventional fuels comparing with NHP; - the philosophy from economic stand point for the covering part of the NHP heat demand. (authors)

  12. Training and plant performance: a strategic planning partnership

    International Nuclear Information System (INIS)

    Coe, R.P.

    1987-01-01

    The nuclear industry as a whole, and specifically GPU Nuclear, is refocusing its attention on performance indicators. This standardized assessment of plant operational performance surfaces numerous examples of how performance-based training positively impacts plant performance. Numerous examples of high dollar savings range from scram reduction programs to reducing personnel rem exposures. The deeper the authors look the more they find that training is making a difference. The question now is, how long can they continue to afford the ever increasing demands of the pursuit of excellence. Early in 1985, the Training and Education Department at GPU Nuclear proactively began its strategic planning effort in order to address the increasing industry initiatives while facing flat or reduced commitments of resources. The Training Strategic Plan addresses detailed plans for each of the following areas: curriculum planning; program development; training and education organizational structure; training and education administrative procedures; training advisory structure and priority process; financial strategies. All of the above strategies are designed to assure training effectiveness. With the nuclear option under such strong public scrutiny, it is in the best interest of all of the nuclear utilities to assure the most cost effective approach to successful operation while achieving their standards of excellence

  13. Reliability of computerized safety systems at nuclear power plants. Report of a technical committee meeting held in Vienna, 21-25 June 1993

    International Nuclear Information System (INIS)

    1995-03-01

    Computer based technology is increasingly used in order to perform safety functions. In some recently designed nuclear power plants the whole safety system is computerized. In older plants replacement of conventional technology based system is seen to be of benefit. If the new technology is to be used, it must meet at least the same level of quality and reliability requirements as specified for conventional technology. However, there is a potential for enhancing the safety of nuclear power plants if the full power of computer technology is applied correctly through well designed, engineered and tested systems which are properly installed and maintained. It is essential that areas where reliability and quality can be improved are identified and that methods for assessing and assuring reliability are developed. The results of the Technical Committee Meeting on Reliability of Computerized Safety Systems at Nuclear Power Plants presented in this report are a step on the road to this goal of improved nuclear safety. Refs, figs and tabs

  14. New technical knowledge to be implemented to the revision of rules on pipe wall thinning management for PWR Plants. 2006 edition

    International Nuclear Information System (INIS)

    Hirai, Junya; Amano, Yoichi; Nakamura, Takao

    2013-01-01

    Rules for PWR plant pipe wall thinning management were formulated by the Japan Society of Mechanical Engineers in 2006. Since then thinning management of Japanese PWR plants has been carried out based on this rule. Pipe wall thinning phenomena to be dealt with in this rule have been identified in many piping components of power plants. New technical knowledge has been accumulated since the issuance of 2006 edition. We have formulated these knowledge and information about the thinning phenomena in PWR power plants. Given the history of application of this rule, we have to make our best effort to carry out a study of latest technical knowledge and implement them to the revision of rule and improve pipe wall thinning management. This paper summarizes the new technical knowledge and basis to be implemented to the revision of rules on pipe wall thinning management for PWR plants in Japan. (author)

  15. State of the art for noise reduction in biogas plants. Sound technical analyses, research, investigations

    International Nuclear Information System (INIS)

    2014-01-01

    Approximately 480 biogas plants are currently being built in Mecklenburg-Vorpommern, which were mainly built in an agricultural context. At the beginning of 2014 about 15 percent of the country's electricity was generated by domestic biogas plants. This publication is intended to serve as a guide to the authorities, planners and engineers, in order to be able to plan, erect and operate biogas plants in the most conflict-free manner. [de

  16. Complex effects of fertilization on plant and herbivore performance in