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

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

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

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

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

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Aristos Aristidou Natureworks); Robert Kean (NatureWorks); Tom Schechinger (IronHorse Farms, Mat); Stuart Birrell (Iowa State); Jill Euken (Wallace Foundation & Iowa State)

2007-10-01

/storage/transportation equipment and the processor would build and operate the plant. Pilot fermentation studies demonstrated dramatic improvements in yields and rates with optimization of batch fermentor parameters. Demonstrated yields and rates are approaching those necessary for profitable commercial operation for production of ethanol or lactic acid. The ability of the biocatalyst to adapt to biomass hydrolysate (both biomass sugars and toxins in the hydrolysate) was demonstrated and points towards ultimate successful commercialization of the technology. However, some of this work will need to be repeated and possibly extended to adapt the final selected biocatalyst for the specific commercial hydrolysate composition. The path from corn stover in the farm field to final products, involves a number of steps. Each of these steps has options, problems, and uncertainties; thus creating a very complex multidimensional obstacle to successful commercial development. Through the tasks of this project, the technical and commercial uncertainties of many of these steps have been addressed; thus providing for a clearer understanding of paths forward and commercial viability of a corn stover-based biorefinery.

Final Technical Report DOE/GO/13142-1

Energy Technology Data Exchange (ETDEWEB)

Patrick Mulvihill; Quang Nguyen

2010-09-15

This research adds to the understanding of the areas of residual starch and biomass conversion to alcohol, by providing data from pilot plant equipment of larger scale than the minimum required to give commercially scalable data. Instrumentation and control is in place to capture the information produced, for economic and technical evaluation. The impact of rheology, recycle streams, and residence time distributions on the technical and economic performance can be assessed. Various processes can be compared technically and economically because the pilot plants are readily modifiable. Several technologies for residual starch yield improvement have been identified, implemented, and patent applications filed. Various biomass-to-ethanol processes have been compared and one selected for technical optimization and commercialization. The technical and economic feasibility of the current simplified biomass conversion process is being confirmed by intensive pilot plant efforts as of this writing. Optimization of the feedstock handling and pretreatment is occurring to increase the alcohol yield above the minimum commercially viable level already demonstrated. Samples of biomass residue and reactor blowdown condensate are being collected to determine the technical and economic performance of the high-water-recycle waste treatment system being considered for the process. The project is of benefit to the public because it is advancing the efforts to achieve low-cost fermentable substrates for conversion to transportation fuels. This process combines the hydrolysis of agricultural residues with novel enzymes and organisms to convert the sugars released to transportation fuels. The process development is taking place at a scale allowing commercial development to proceed at a rapid pace.

Summary report of the final technical meeting on 'International Reactor Dosimetry File: IRDF-2002'

International Nuclear Information System (INIS)

Griffin, Patrick J.; Paviotti-Corcuera, R.

2003-10-01

Presentations, recommendations and conclusions of the Final Technical Meeting on 'International Reactor Dosimetry File: IRDF-2002' are summarized in this report. The main aims of this meeting were to discuss scientific and technical matters related to reactor dosimetry and to assign responsibilities for the preparation of the final version of the IRDF- 2002 library and the associated TECDOC. Tasks were assigned and deadlines were agreed. Participants emphasized that accurate and complete nuclear data for reactor dosimetry are essential to improve the assessment accuracies for reactor pressure vessel service lifetimes in nuclear power plants, as well as for other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. (author)

48 CFR 252.235-7011 - Final scientific or technical report.

Science.gov (United States)

2010-10-01

... technical report. 252.235-7011 Section 252.235-7011 Federal Acquisition Regulations System DEFENSE... CLAUSES Text of Provisions And Clauses 252.235-7011 Final scientific or technical report. As prescribed in 235.072(d), use the following clause: Final Scientific or Technical Report (NOV 2004) The Contractor...

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

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

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

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

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

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

Guidelines for Preparing Final Technical Reports

International Development Research Centre (IDRC) Digital Library (Canada)

fdieudonne

Prior to submitting the Final Technical Report, any outstanding issues related to dissemination in accordance with ... The report should be an opportunity to reflect on the management of the project from various perspectives: .... of poor quality.

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

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

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)

Intergrated plant safety assessment. Systematic evaluation program. Palisades plant, Consumers Power Company, Docket No. 50-255. Final report

International Nuclear Information System (INIS)

1982-10-01

The Nuclear Regulatory Commission (NRC) has published its Final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0820), under the scope of the Systematic Evaluation Program (SEP), for Consumers Power Company's Palisades Plant located in Covert, Van Buren County, Michigan. The SEP was initiated by the NRC to review the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed under the SEP for the Palisades Plant. The review has provided for (1) as assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when all supplements to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in April 1982

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

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

Technical and economic assessment of solar hybrid repowering. Final report

Energy Technology Data Exchange (ETDEWEB)

None

1978-09-01

Public Service Company of New Mexico (PNM) has performed a Technical and Economic Assessment of Solar Hybrid Repowering under funding by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), Western Energy Supply and Transmission (WEST) Associates, and a number of southwestern utilities. Solar hybrid repowering involves placement of solar hardware adjacent to and connected to existing gas- and oil-fueled electric generation units to displace some of or all the fossil fuel normally used during daylight hours. The subject study assesses the technical economic viability of the solar hybrid repowering concept within the southwestern United States and the PNM system. This document is a final report on the study and its results. The study was divided into the six primary tasks to allow a systematic investigation of the concept: (1) market survey and cost/benefit analysis, (2) study unit selection, (3) conceptual design and cost estimates, (4) unit economic analysis, (5) program planning, future phases, and (6) program management. Reeves Station No. 2 at Albuquerque, New Mexico, was selected for repowering with a design goal of 50 percent (25 MWe). The solar system design is based on the 10 MW solar central receiver pilot plant preliminary design for Barstow, California. SAN--1608-4-2 contains the technical drawings. (WHK)

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

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.

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

Improving the safety of LWR power plants. Final report

International Nuclear Information System (INIS)

1980-04-01

This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs

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

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)

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

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

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

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

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

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

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

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

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

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

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

Simulated coal gas MCFC power plant system verification. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-30

The objective of the main project is to identify the current developmental status of MCFC systems and address those technical issues that need to be resolved to move the technology from its current status to the demonstration stage in the shortest possible time. The specific objectives are separated into five major tasks as follows: Stack research; Power plant development; Test facilities development; Manufacturing facilities development; and Commercialization. This Final Report discusses the M-C power Corporation effort which is part of a general program for the development of commercial MCFC systems. This final report covers the entire subject of the Unocal 250-cell stack. Certain project activities have been funded by organizations other than DOE and are included in this report to provide a comprehensive overview of the work accomplished.

Final technical report

DEFF Research Database (Denmark)

Juhl, Thomas Winther; Nielsen, Jakob Skov

gas jet chamber and laser beam path from the final focusing mirror. The project consists of three phases: Phase 1: Fundamental studies of cutting front mechanisms, beam propagation, nozzle design and chemical reactions in the cut kerf with special emphasize on high laser powers and thick sections...... cutting nozzle which can be adjusted independently to the laser beam has been developed. The position of the focus relative the workpiece can be adjusted to cutting applications with relatively large processing windows, i.e. both mild and stainless steels, and of a broad thickness range. A build-in auto......This project entails research with the goal to extend laser cutting of steel based metals to thickness above 20 mm and laser powers in the 10 kW range, with adequate accuracy and economically viable cutting speeds. The technical approach is to develop mirror based cutting heads with truly coaxial...

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

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

Southpoint power plant final environmental impact statement

International Nuclear Information System (INIS)

1999-01-01

This document is the Final Environmental Impact Statement (FEIS) for a proposed lease of acreage on the Fort Mojave Indian Reservation in Mohave County, Arizona for development of a natural gas fired 500 megawatt combined cycle power plant. The Bureau of Indian Affairs (BIA) serves as the federal lead agency and the Fort Mojave Indian Tribe (FMIT) and the Western Area Power Administration (WAPA) are cooperating agencies for the EIS process. The purpose of this document is to provide information to the public and to interested public agencies regarding the environmental consequences of the approval of a long-term lease for the construction and operation of the proposed Southpoint power plant. The FEIS, prepared by Hallock/Gross, Inc. under the direction of the BIA and in cooperation with the FMIT and WAPA, addresses the comparative analysis of alternatives and evaluates the environmental consequences of such alternatives on various resources and addresses public comments. A number of technical reports were used in the preparation of the Draft EIS and FEIS and are available for review as Appendices to this document under separate cover that can be reviewed at the BIA offices which are listed

Systems study 'Alternative Entsorgung'. Final report. Technical annex 10

International Nuclear Information System (INIS)

Hartje, B.; Kronschnabel, H.; Mueller, W.F.W.

1984-01-01

There is an investigation whether accessibility can be produced to fuel elements stored in a salt mine. All solutions of the problem were followed up until the technically best one was found. Two conditions must be fulfilled for access to the final storage barrel: - There must be a climate which is suitable for people. The Mining Order is the basis for this. - The pit building must be fixed, in the convergence in the salt mine should not lead to it becoming impossible to reach part of the mine. Due to heat-producing waste, rock temperatures are caused in the salt mine, in which mining is no longer possible. Building on the idea of cooling the whole final storage area using concentric sections, the amount of heat to be removal was first estimated. Cooling of the whole final storage area proved to be technically unjustifiable and uninteresting at present. (orig./HP) [de

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Bohdan W. Oppenheim; Rudolf Marloth

2007-10-26

Executive Summary The document contains Final Technical Report on the Industrial Assessment Center Program at Loyola Marymount University in Los Angeles, covering the contract period of 9/1/2002 to 11/30/2006, under the contract DE-FC36-02GO 12073. The Report describes six required program tasks, as follows: TASK 1 is a summary of the assessments performed over the life of the award: 77 assessments were performed, 595 AR were recommended, covering a very broad range of manufacturing plants. TASK 2 is a description of the efforts to promote and increase the adoption of assessment recommendations and employ innovative methods to assist in accomplishing these goals. The LMU IAC has been very successful in accomplishing the program goals, including implemented savings of $5,141,895 in energy, $10,045,411 in productivity and $30,719 in waste, for a total of $15,218,025. This represents 44% of the recommended savings of $34,896,392. TASK 3 is a description of the efforts promoting the IAC Program and enhancing recruitment efforts for new clients and expanded geographic coverage. LMU IAC has been very successful recruiting new clients covering Southern California. Every year, the intended number of clients was recruited. TASK 4 describes the educational opportunities, training, and other related activities for IAC students. A total of 38 students graduated from the program, including 2-3 graduate students every semester, and the remainder undergraduate students, mostly from the Mechanical Engineering Department. The students received formal weekly training in energy (75%) and productivity (25). All students underwent extensive safety training. All students praised the IAC experience very highly. TASK 5 describes the coordination and integration of the Center activities with other Center and IAC Program activities, and DOE programs. LMU IAC worked closely with MIT, and SDSU IAC and SFSU IAC, and enthusiastically supported the SEN activities. TASK 6 describes other tasks

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.)

10 CFR 52.157 - Contents of applications; technical information in final safety analysis report.

Science.gov (United States)

2010-01-01

...; technical information in final safety analysis report. The application must contain a final safety analysis... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.157 Section 52.157 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

10 CFR 52.79 - Contents of applications; technical information in final safety analysis report.

Science.gov (United States)

2010-01-01

...; technical information in final safety analysis report. (a) The application must contain a final safety... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.79 Section 52.79 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

48 CFR 1852.235-73 - Final Scientific and Technical Reports.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Final Scientific and Technical Reports. 1852.235-73 Section 1852.235-73 Federal Acquisition Regulations System NATIONAL..., including recommendations and conclusions based on the experience and results obtained. The final report...

Conditioning of spent fuel for interim and final storage in the pilot conditioning plant (PKA) at Gorleben

International Nuclear Information System (INIS)

Lahr, H.; Willax, H.O.; Spilker, H.

1999-01-01

In 1994, due to the change of the nuclear law in Germany, the concept of direct final disposal for spent fuel was developed as an equivalent alternative to the waste management with reprocessing. Since 1979, tests for the direct final disposal of spent fuel have been conducted in Germany. In 1985, the State and the utilities came to an agreement to develop this concept of waste management to technical maturity. Gesellschaft fuer Nuklear-Service (GNS) was commissioned by the utilities with the following tasks: to develop and test components with regard to conditioning technology, to construct and operate the pilot conditioning plant (PKA), and to develop casks suitable for final disposal. Since 1990, the construction of the PKA has taken place at the Brennelementlager Gorleben site. The PKA has been designed as a multipurpose facility and can thus fulfil various tasks within the framework of the conditioning and management of spent fuel assemblies and radioactive waste. The pilot character of the plant allows for development and testing in the field of spent fuel assembly conditioning. The objectives of the PKA may be summarized as follows: to condition spent fuel assemblies, to reload spent fuel assemblies and waste packages, to condition radioactive waste, and to do maintenance work on transport and storage casks as well as on waste packages. Currently, the buildings of the PKA are constructed and the technical facilities are installed. The plant will be ready for service in the middle of 1999. It is the first plant of its kind in the world. (author)

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.

International safeguards for reprocessing plants. Final report

International Nuclear Information System (INIS)

Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

1981-04-01

Proliferation risks inherent in reprocessing show the need to employ technically effective safeguards which can detect, with a high degree of assurance and on a timely basis, the diversion of significant quantities of fissionable material. A balance must be struck between what is technically feasible and effective and what is institutionally acceptable. Purpose of this report is to examine the several technical approaches to safeguards in light of their prospective acceptability. This study defines the economic, political and institutional nature of the safeguards problem; surveys generically alternative technical approaches to international safeguards including their effectiveness and relative development; characterizes the institutional implications and uncertainties associated with the acceptance and implementation of each technical alternative; and integrates these assessments into a set of overall judgments on feasible directions for reprocessing plant safeguards systems

International safeguards for reprocessing plants. Final report

Energy Technology Data Exchange (ETDEWEB)

Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

1981-04-01

Proliferation risks inherent in reprocessing show the need to employ technically effective safeguards which can detect, with a high degree of assurance and on a timely basis, the diversion of significant quantities of fissionable material. A balance must be struck between what is technically feasible and effective and what is institutionally acceptable. Purpose of this report is to examine the several technical approaches to safeguards in light of their prospective acceptability. This study defines the economic, political and institutional nature of the safeguards problem; surveys generically alternative technical approaches to international safeguards including their effectiveness and relative development; characterizes the institutional implications and uncertainties associated with the acceptance and implementation of each technical alternative; and integrates these assessments into a set of overall judgments on feasible directions for reprocessing plant safeguards systems.

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)

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)

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

Final Technical Report - Kotzebue Wind Power Project - Volume II

Energy Technology Data Exchange (ETDEWEB)

Rana Zucchi, Global Energy Concepts, LLC; Brad Reeve, Kotzebue Electric Association; DOE Project Officer - Doug Hooker

2007-10-31

The Kotzebue Wind Power Project is a joint undertaking of the U.S. Department of Energy (DOE); Kotzebue Electric Association (KEA); and the Alaska Energy Authority (AEA). The goal of the project is to develop, construct, and operate a wind power plant interconnected to a small isolated utility grid in an arctic climate in Northwest Alaska. The primary objective of KEA’s wind energy program is to bring more affordable electricity and jobs to remote Alaskan communities. DOE funding has allowed KEA to develop a multi-faceted approach to meet these objectives that includes wind project planning and development, technology transfer, and community outreach. The first wind turbines were installed in the summer of 1997 and the newest turbines were installed in the spring of 2007. The total installed capacity of the KEA wind power project is 1.16 MW with a total of 17 turbines rated between 65 kW and 100 kW. The operation of the wind power plant has resulted in a wind penetration on the utility system in excess of 35% during periods of low loads. This document and referenced attachments are presented as the final technical report for the U.S. Department of Energy (DOE) grant agreement DE-FG36-97GO10199. Interim deliverables previously submitted are also referenced within this document and where reasonable to do so, specific sections are incorporated in the report or attached as appendices.

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

Technical specification improvements to containment heat removal and emergency core cooling systems: Final report

International Nuclear Information System (INIS)

Sullivan, W.P.; Ha, C.; Pentzien, D.C.; Visweswaran, S.

1988-07-01

This report presents the results of an analysis for technical specification improvements to the emergency core cooling systems (ECCS) and containment heat removal systems (EPRI Research Project 2142-3). The objective of this project is to further develop a reliability- and risk-based methodology to provide improvements by considering groups of surveillance test intervals and allowed out-of-service times jointly. This was done for the technical specifications for the ECCS, containment heat removal equipment, and supporting systems of a boiling water reactor plant. The project (1) developed a methodology for optimizing groups of surveillance test intervals and allowed out-of-service times jointly, (2) applied the methodology in a case study of a specific operating plant, Hatch-2, and (3) evaluated benefits of the application. The results of the case study demonstrate that beneficial technical specification improvements can be realized with application of the methodology. By tightening a small group of sensitive surveillance test intervals (STIs) and allowed out-of-service times (AOTs), a larger group of less sensitive STIs and AOTs can be extended resulting in an overall plant operating cost improvement without reducing the plant safety. The reliability- and risk-based methodology and results from this project can be effectively applied for technical specification improvements at other operating plants

Systems study 'Alternative Entsorgung'. Final report. Technical annex 6

International Nuclear Information System (INIS)

1984-08-01

In the conditioning plant, fuel elements which have been stored for ten years are loaded into transport containers, unloaded, identified and welded into a dry storage box. The dry store barrel is introduced into a final storage container, which, after being closed, is packed in lost shielding. This so-called final storage barrel is finally placed in a transport container and leaves the conditioning plant in this form by rail for transport to the final storage mine. The fuel element method of treatment 'packing of three complete fuel elements' was used as the reference process. In addition, the method of treatment 'fuel elements dismantled into fuel rods' was also examined. The handling of fuel elements and secondary waste treatment in the reference process are described in detail. (orig./HP) [de

ITER technical basis

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties.

ITER technical basis

International Nuclear Information System (INIS)

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties

The decommissioning of WWER type nuclear power plants. Final report on an IAEA regional technical co-operation project

International Nuclear Information System (INIS)

2000-01-01

Numerous WWER-440 nuclear power plants are in operation in central and eastern Europe and a small number have already been shut down. In addition to reactors already shut down, many other reactors will reach the end of their design lifetime in a few years and become candidates for decommissioning. It is unfortunate that little consideration was devoted to decommissioning of WWER-440 reactors at the plant design and construction stage, and little emphasis was placed on planning for decommissioning. It is within this context that the IAEA launched a regional technical co-operation project in 1994 with the aim of providing guidance on planning and management of decommissioning for WWERs. The project, which had a duration of four years (1995-1998), included the organization of workshops and scientific visits to countries having WWERs and other countries where active decommissioning projects were under way. Eventually, participants suggested the consolidation of expert guidance and collective opinions into a TECDOC, which was drafted by both designated participants from project recipient countries and invited experts. The TECDOC has the aim of serving as a stimulus for all concerned parties in central and eastern European countries to initiate concrete decommissioning planning, including assessment of existing and required resources for the eventual implementation of decommissioning plans. In addition, the regional technical co-operation project has managed to bring together in this TECDOC a number of good practices that could be useful in WWER-440 decommissioning

Encapsulation plant at Forsmark

International Nuclear Information System (INIS)

Nystroem, Anders

2007-08-01

SKB has already carried out a preliminary study of an encapsulation plant detached from Clab (Central interim storage for spent fuels). This stand-alone encapsulation plant was named FRINK and its assumed siting was the above-ground portion of the final repository, irrespective of the repository's location. The report previously presented was produced in cooperation with BNFL Engineering Ltd in Manchester and the fuel reception technical solution was examined by Gesellschaft fuer Nuklear-Service mbH (GNS) in Hannover and by Societe Generale pour les Techniques Nouvelles (SGN) in Paris. This report is an update of the earlier preliminary study report and is based on the assumption that the encapsulation plant and also the final repository will be sited in the Forsmark area. SKB's main alternative for siting the encapsulation plant is next to Clab. Planning of this facility is ongoing and technical solutions from the planning work have been incorporated in this report. An encapsulation plant placed in proximity to any final repository in Forsmark forms part of the alternative presentation in the application for permission to construct and operate an installation at Clab. The main technical difference between the planned encapsulation plant at Clab and an encapsulation plant at a final repository at Forsmark is how the fuel is managed and prepared before actual encapsulation. Fuel reception at the encapsulation plant in Forsmark would be dry, i.e. there would be no water-filled pools at the facility. Clab is used for verificatory fuel measurements, sorting and drying of the fuel before transport to Forsmark. This means that Clab will require a measure of rebuilding and supplementary equipment. In purely technical terms, the prospects for building an encapsulation plant sited at Forsmark are good. A description of the advantages and drawbacks of siting the encapsulation plant at Clab as opposed to any final repository at Forsmark is presented in a separate report

Encapsulation plant at Forsmark

Energy Technology Data Exchange (ETDEWEB)

Nystroem, Anders

2007-08-15

SKB has already carried out a preliminary study of an encapsulation plant detached from Clab (Central interim storage for spent fuels). This stand-alone encapsulation plant was named FRINK and its assumed siting was the above-ground portion of the final repository, irrespective of the repository's location. The report previously presented was produced in cooperation with BNFL Engineering Ltd in Manchester and the fuel reception technical solution was examined by Gesellschaft fuer Nuklear-Service mbH (GNS) in Hannover and by Societe Generale pour les Techniques Nouvelles (SGN) in Paris. This report is an update of the earlier preliminary study report and is based on the assumption that the encapsulation plant and also the final repository will be sited in the Forsmark area. SKB's main alternative for siting the encapsulation plant is next to Clab. Planning of this facility is ongoing and technical solutions from the planning work have been incorporated in this report. An encapsulation plant placed in proximity to any final repository in Forsmark forms part of the alternative presentation in the application for permission to construct and operate an installation at Clab. The main technical difference between the planned encapsulation plant at Clab and an encapsulation plant at a final repository at Forsmark is how the fuel is managed and prepared before actual encapsulation. Fuel reception at the encapsulation plant in Forsmark would be dry, i.e. there would be no water-filled pools at the facility. Clab is used for verificatory fuel measurements, sorting and drying of the fuel before transport to Forsmark. This means that Clab will require a measure of rebuilding and supplementary equipment. In purely technical terms, the prospects for building an encapsulation plant sited at Forsmark are good. A description of the advantages and drawbacks of siting the encapsulation plant at Clab as opposed to any final repository at Forsmark is presented in a separate

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.)

DOE final technical report 3/1997 to 2/2005

International Nuclear Information System (INIS)

Gross, Franz L.

2005-01-01

DOE final technical report 3/1997 to 2/2005 This grant supported basic theoretical research into the derivation (from relativistic field theories) of relativistic equations for few body systems, with practical applications to the properties of 2 and 3 nucleon systems and to the nature of few-quark systems

77 FR 47495 - Final Priority; Technical Assistance on State Data Collection, Analysis, and Reporting-National...

Science.gov (United States)

2012-08-08

... Priority; Technical Assistance on State Data Collection, Analysis, and Reporting--National IDEA Technical... 34 CFR Chapter III [CFDA Number 84.373Z] Final Priority; Technical Assistance on State Data Collection, Analysis, and Reporting--National IDEA Technical Assistance Center on Early Childhood...

Technical area status report for low-level mixed waste final waste forms

International Nuclear Information System (INIS)

Mayberry, J.L.; DeWitt, L.M.; Darnell, R.

1993-08-01

The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA's Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities

76 FR 18624 - Research, Technical Assistance and Training Programs: Notice of Final Circular

Science.gov (United States)

2011-04-04

... to FTA Circular 6100.1D, Research and Technical Assistance Training Program: Application Instructions... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Research, Technical Assistance and Training Programs: Notice of Final Circular AGENCY: Federal Transit Administration (FTA), DOT. ACTION...

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

Pinellas Plant feasibility study. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

The Pinellas Plant was built in 1956 to manufacture neutron generators, a principal component in nuclear weapons. In September 1990, the Department of Health and Rehabilitative Services (HRS) entered into an agreement with DOE to independently examine environmental monitoring data from the plant and health data from Pinellas County to determine if an epidemiological study is technically feasible to measure possible off-site health effects from ionizing radiation. Through normal plant operations, some radioactive materials have been released to the environment. Eighty percent of the total plant releases of 107,707 curies occurred in the early years of plant operation (1957--1960). The primary materials released were tritium gas, tritium oxide and krypton-85. Environmental monitoring for radioactive releases from the plant has been done regularly since 1975. The US Public Health Service Centers for Disease Control and Prevention (CDC), in assisting HRS, has determined that sufficient radiological data exist by which a dose reconstruction can be done. A dose reconstruction can provide an estimate of how much radiological exposure someone living in the vicinity of the Pinellas Plant may have suffered from environmental releases.

Pinellas Plant feasibility study. Final report

International Nuclear Information System (INIS)

1994-09-01

The Pinellas Plant was built in 1956 to manufacture neutron generators, a principal component in nuclear weapons. In September 1990, the Department of Health and Rehabilitative Services (HRS) entered into an agreement with DOE to independently examine environmental monitoring data from the plant and health data from Pinellas County to determine if an epidemiological study is technically feasible to measure possible off-site health effects from ionizing radiation. Through normal plant operations, some radioactive materials have been released to the environment. Eighty percent of the total plant releases of 107,707 curies occurred in the early years of plant operation (1957--1960). The primary materials released were tritium gas, tritium oxide and krypton-85. Environmental monitoring for radioactive releases from the plant has been done regularly since 1975. The US Public Health Service Centers for Disease Control and Prevention (CDC), in assisting HRS, has determined that sufficient radiological data exist by which a dose reconstruction can be done. A dose reconstruction can provide an estimate of how much radiological exposure someone living in the vicinity of the Pinellas Plant may have suffered from environmental releases

AIMES Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Katz, Daniel S [Univ. of Illinois, Urbana-Champaign, IL (United States). National Center for Supercomputing Applications (NCSA); Jha, Shantenu [Rutgers Univ., New Brunswick, NJ (United States); Weissman, Jon [Univ. of Minnesota, Minneapolis, MN (United States); Turilli, Matteo [Rutgers Univ., New Brunswick, NJ (United States)

2017-01-31

This is the final technical report for the AIMES project. Many important advances in science and engineering are due to large-scale distributed computing. Notwithstanding this reliance, we are still learning how to design and deploy large-scale production Distributed Computing Infrastructures (DCI). This is evidenced by missing design principles for DCI, and an absence of generally acceptable and usable distributed computing abstractions. The AIMES project was conceived against this backdrop, following on the heels of a comprehensive survey of scientific distributed applications. AIMES laid the foundations to address the tripartite challenge of dynamic resource management, integrating information, and portable and interoperable distributed applications. Four abstractions were defined and implemented: skeleton, resource bundle, pilot, and execution strategy. The four abstractions were implemented into software modules and then aggregated into the AIMES middleware. This middleware successfully integrates information across the application layer (skeletons) and resource layer (Bundles), derives a suitable execution strategy for the given skeleton and enacts its execution by means of pilots on one or more resources, depending on the application requirements, and resource availabilities and capabilities.

NCSU reactor sharing program. Final technical report

International Nuclear Information System (INIS)

Perez, P.B.

1997-01-01

The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities. This report is the Final Technical Report for the DOE award reference number DE-FG05-95NE38136 which covers the period September 30, 1995 through September 30, 1996

TVA coal-gasification commercial demonstration plant project. Volume 5. Plant based on Koppers-Totzek gasifier. Final report

Energy Technology Data Exchange (ETDEWEB)

1980-11-01

This volume presents a technical description of a coal gasification plant, based on Koppers-Totzek gasifiers, producing a medium Btu fuel gas product. Foster Wheeler carried out a conceptual design and cost estimate of a nominal 20,000 TPSD plant based on TVA design criteria and information supplied by Krupp-Koppers concerning the Koppers-Totzek coal gasification process. Technical description of the design is given in this volume.

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

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

Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants (Cooperative Agreement DE-FC03-99SF21902, Am. M004) Final Technical Report

International Nuclear Information System (INIS)

Ritterbusch, Stanley E.

2003-01-01

accidents would be an inherent part of the Probabilistic Safety Assessment for the plant and their evaluation would be probabilistic. Other first year accomplishments include (1) the conversion of an NRC database for cross-referencing NRC criteria and industry codes and standards to Microsoft 2000 software, (2) an assessment of the NRC's hearing process which concluded that the normal cross-examination during public hearings is not actually required by the U.S. Administrative Procedures Act, (3) the identification and listing of reliability data sources, and (4) interfacing with other industry groups (e.g., NEI and IAEA) and NRC at workshops for risk-informing regulations. The major accomplishments during the second year consisted of (1) issuance of the final report for Subtask 1.1, ''Identify Current Applicable Regulatory Requirements [and Industry Standards],'' (2) issuance of the final report for Subtask 1.2,'' Identify Structures, Systems, and Components and Their Associate d Costs for a Typical Plant,'' (3) extension of the new, highly risk-informed design and regulatory framework to non-light-water-reactor technology, (4) completion of more detailed thermal-hydraulic and probabilistic analyses of advanced conceptual reactor system/component designs, (6) initial evaluation and recommendations for improvement of the NRC design review process, and (7) initial development of the software format, procedures and statistical routines needed to store, analyze and retrieve the available reliability data. Final reports for Subtasks 1.1 (regulatory and design criteria) and 1.2 (costs for structures, systems, and components) were prepared and issued. A final report for Subtask 1.3 (Regulatory Framework) was drafted with the aim to issue it in Phase 3 (Year 3). One technical report was produced for Subtask 1.4 (methods development) and two technical reports were produced for Subtask 1.6 (sample problem analysis). An interim report on the NRC design review process (Subtask 1.7) was

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

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

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

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

High energy physics research. Final technical report, 1957--1994

International Nuclear Information System (INIS)

Williams, H.H.

1995-01-01

This is the final technical report to the Department of Energy on High Energy Physics at the University of Pennsylvania. It discusses research conducted in the following areas: neutrino astrophysics and cosmology; string theory; electroweak and collider physics; supergravity; cp violation and baryogenesis; particle cosmology; collider detector at Fermilab; the sudbury neutrino observatory; B-physics; particle physics in nuclei; and advanced electronics and detector development

High energy physics research. Final technical report, 1957--1994

Energy Technology Data Exchange (ETDEWEB)

Williams, H.H.

1995-10-01

This is the final technical report to the Department of Energy on High Energy Physics at the University of Pennsylvania. It discusses research conducted in the following areas: neutrino astrophysics and cosmology; string theory; electroweak and collider physics; supergravity; cp violation and baryogenesis; particle cosmology; collider detector at Fermilab; the sudbury neutrino observatory; B-physics; particle physics in nuclei; and advanced electronics and detector development.

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.

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.

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)

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)

Technical approach to finalizing sensible soil cleanup levels at the Fernald Environmental Management Project

International Nuclear Information System (INIS)

Carr, D.; Hertel, B.; Jewett, M.; Janke, R.; Conner, B.

1996-01-01

The remedial strategy for addressing contaminated environmental media was recently finalized for the US Department of Energy's (DOE) Fernald Environmental Management Project (FEMP) following almost 10 years of detailed technical analysis. The FEMP represents one of the first major nuclear facilities to successfully complete the Remedial Investigation/Feasibility Study (RI/FS) phase of the environmental restoration process. A critical element of this success was the establishment of sensible cleanup levels for contaminated soil and groundwater both on and off the FEMP property. These cleanup levels were derived based upon a strict application of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) regulations and guidance, coupled with positive input from the regulatory agencies and the local community regarding projected future land uses for the site. The approach for establishing the cleanup levels was based upon a Feasibility Study (FS) strategy that examined a bounding range of viable future land uses for the site. Within each land use, the cost and technical implications of a range of health-protective cleanup levels for the environmental media were analyzed. Technical considerations in driving these cleanup levels included: direct exposure routes to viable human receptors; cross- media impacts to air, surface water, and groundwater; technical practicality of attaining the levels; volume of affected media; impact to sensitive environmental receptors or ecosystems; and cost. This paper will discuss the technical approach used to support the finalization of the cleanup levels for the site. The final cleanup levels provide the last remaining significant piece to the puzzle of establishing a final site-wide remedial strategy for the FEMP, and positions the facility for the expedient completion of site-wide remedial activities

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

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

78 FR 12955 - Final Requirements, Definitions, and Selection Criteria-Native American Career and Technical...

Science.gov (United States)

2013-02-26

... career and technical education programs (20 U.S.C. 2326(e)). This notice does not preclude us from... DEPARTMENT OF EDUCATION 34 CFR Chapter IV [Docket ID ED-2012-OVAE-0053] Final Requirements, Definitions, and Selection Criteria--Native American Career and Technical Education Program (NACTEP) [Catalog...

Technical planning activity: Final report

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

In April 1985, the US Department of Energy's (DOE's) Office of Fusion Energy commissioned the Technical Planning Activity (TPA). The purpose of this activity was to develop a technical planning methodology and prepare technical plans in support of the strategic and policy framework of the Magnetic Fusion Program Plan issued by DOE in February 1985. Although this report represents the views of only the US magnetic fusion community, it is international in scope in the sense that the technical plans contained herein describe the full scope of the tasks that are prerequisites for the commercialization of fusion energy. The TPA has developed a well-structured methodology that includes detailed definitions of technical issues, definitions of program areas and elements, statements of research and development objectives, identification of key decision points and milestones, and descriptions of facility requirements.

Technical planning activity: Final report

International Nuclear Information System (INIS)

1987-01-01

In April 1985, the US Department of Energy's (DOE's) Office of Fusion Energy commissioned the Technical Planning Activity (TPA). The purpose of this activity was to develop a technical planning methodology and prepare technical plans in support of the strategic and policy framework of the Magnetic Fusion Program Plan issued by DOE in February 1985. Although this report represents the views of only the US magnetic fusion community, it is international in scope in the sense that the technical plans contained herein describe the full scope of the tasks that are prerequisites for the commercialization of fusion energy. The TPA has developed a well-structured methodology that includes detailed definitions of technical issues, definitions of program areas and elements, statements of research and development objectives, identification of key decision points and milestones, and descriptions of facility requirements

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).

Technical area status report for low-level mixed waste final waste forms. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Mayberry, J.L.; DeWitt, L.M. [Science Applications International Corp., Idaho Falls, ID (United States); Darnell, R. [EG and G Idaho, Inc., Idaho Falls, ID (United States)] [and others

1993-08-01

The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA`s Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities.

77 FR 30512 - Native American Career and Technical Education Program; Final Waivers and Extension of Project...

Science.gov (United States)

2012-05-23

... DEPARTMENT OF EDUCATION Native American Career and Technical Education Program; Final Waivers and... American Career and Technical Education Program Catalog of Federal Domestic Assistance (CFDA) Number: 84... and Technical Education Program (NACTEP), the Secretary waives 34 CFR 75.250 and 75.261(c)(2) in order...

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.

"Type Ia Supernovae: Tools for Studying Dark Energy" Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Woosley, Stan [Lick Observatory, San Jose, CA (United States); Kasen, Dan [Univ. of California, Berkeley, CA (United States)

2017-05-10

Final technical report for project "Type Ia Supernovae: Tools for the Study of Dark Energy" awarded jointly to scientists at the University of California, Santa Cruz and Berkeley, for computer modeling, theory and data analysis relevant to the use of Type Ia supernovae as standard candles for cosmology.

AISI Direct Steelmaking Program. Final technical report

Energy Technology Data Exchange (ETDEWEB)

Aukrust, E.

1994-08-01

This final report deals with the results of a 5-yr project for developing a more energy-efficient, environmentally friendly, less costly process for producing hot metal than current coke ovens and blast furnaces. In the process, iron ore pellets are smelted in a foamy slag created by reaction of coal char with molten slag to produce CO. The CO further reacts with oxygen, which also reacts with coal volatile matter, to produce the heat necessary to sustain the endothermic reduction reaction. The uncombusted CO and H{sub 2} from the coal are used to preheat and prereduce hematite pellets for the most efficient use of the energy in the coal. Laboratory programs confirmed that the process steps worked. Pilot plant studies were successful. Economic analysis for a 1 million tpy plant is promising.

Plant systems/components modularization study. Final report

International Nuclear Information System (INIS)

1977-07-01

The final results are summarized of a Plant Systems/Components Modularization Study based on Stone and Webster's Pressurized Water Reactor Reference Design. The program has been modified to include evaluation of the most promising areas for modular consideration based on the level of the Sundesert Project engineering design completion and the feasibility of their incorporation into the plant construction effort

Key technical issues associated with a method of pulse compression. Final technical report

International Nuclear Information System (INIS)

Hunter, R.O. Jr.

1980-06-01

Key technical issues for angular multiplexing as a method of pulse compression in a 100 KJ KrF laser have been studied. Environmental issues studied include seismic vibrations man-made vibrations, air propagation, turbulence, and thermal gradient-induced density fluctuations. These studies have been incorporated in the design of mirror mounts and an alignment system, both of which are reported. A design study and performance analysis of the final amplifier have been undertaken. The pulse compression optical train has been designed and assessed as to its performance. Individual components are described and analytical relationships between the optical component size, surface quality, damage threshold and final focus properties are derived. The optical train primary aberrations are obtained and a method for aberration minimization is presented. Cost algorithms for the mirrors, mounts, and electrical hardware are integrated into a cost model to determine system costs as a function of pulse length, aperture size, and spot size

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].

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.

The Michigan high-level radioactive waste program: Final technical progress report

International Nuclear Information System (INIS)

1987-01-01

This report comprises the state of Michigan's final technical report on the location of a proposed high-level radioactive waste disposal site. Included are a list of Michigan's efforts to review the DOE proposal and a detailed report on the application of geographic information systems analysis techniques to the review process

Final Technical Report, Wind Generator Project (Ann Arbor)

Energy Technology Data Exchange (ETDEWEB)

Geisler, Nathan [City of Ann Arbor, MI (United States)

2017-03-20

A Final Technical Report (57 pages) describing educational exhibits and devices focused on wind energy, and related outreach activities and programs. Project partnership includes the City of Ann Arbor, MI and the Ann Arbor Hands-on Museum, along with additional sub-recipients, and U.S. Department of Energy/Office of Energy Efficiency and Renewable Energy (EERE). Report relays key milestones and sub-tasks as well as numerous graphics and images of five (5) transportable wind energy demonstration devices and five (5) wind energy exhibits designed and constructed between 2014 and 2016 for transport and use by the Ann Arbor Hands-on Museum.

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.

Energy-related inventions program invention 637. Final technical report

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-31

The final technical report for the Pegasus plow, a stalk and root embedding apparatus, describes progress from the development stage to the product support stage. The US Department of Agriculture - Agriculture Research Service (ARS) is now in the second year of a three year study comparing the Pegasus to conventional tillage. So far, no downside has been with the Pegasus and the following benefits have been documented: (1) Energy savings of 65.0 kilowatt hours per hectare over conventional tillage. This is when the Pegasus plow is used to bury whole stalks, and represents a 70% savings over conventional tillage (92.5 kilowatt hours per hectare). (2) Four to seven fewer passes of tillage, depending on the particular situation. This represents a substantial time savings to farmers. (3) So far, no differences in cotton yields. Recent cotton boll counts in one study indicate a higher yield potential with the Pegasus. (4) No disease problems. (5) Significantly higher levels of organic matter in the soil. A hypothesis of the study is that whole stalk burial may reduce plant disease problems. This hypothesis has not yet been proven. (6) Significantly higher levels of nitrate nitrogen. Total nitrogen and ammonia nitrogen trended higher but were not significantly different. This shows that whole stalk burial does not adversely affect the nitrogen cycle in the soil and may actually improve it. The marketing support stage of the project is also described in the report.

Iowa Hill Pumped Storage Project Investigations - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Hanson, David [Sacramento Municipal Unitlity District, Sacramento, CA (United States)

2016-07-01

This Final Technical Report is a summary of the activities and outcome of the Department of Energy (DOE) Assistance Agreement DE-EE0005414 with the Sacramento Municipal Utility District (SMUD). The Assistance Agreement was created in 2012 to support investigations into the Iowa Hill Pumped-storage Project (Project), a new development that would add an additional 400 MW of capacity to SMUD’s existing 688MW Upper American River Hydroelectric Project (UARP) in the Sierra Nevada mountains east of Sacramento, California.

Admiralty Inlet Pilot Tidal Project Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Collar, Craig [Public Utility District No. 1 of Snohomish County, Everett, WA (United States)

2015-09-14

This document represents the final report for the Admiralty Inlet Pilot Tidal Project, located in Puget Sound, Washington, United States. The Project purpose was to license, permit, and install a grid-connected deep-water tidal turbine array (two turbines) to be used as a platform to gather operational and environmental data on tidal energy generation. The data could then be used to better inform the viability of commercial tidal energy generation from technical, economic, social, and environmental standpoints. This data would serve as a critical step towards the responsible advancement of commercial scale tidal energy in the United States and around the world. In late 2014, Project activities were discontinued due to escalating costs, and the DOE award was terminated in early 2015. Permitting, licensing, and engineering design activities were completed under this award. Final design, deployment, operation, and monitoring were not completed. This report discusses the results and accomplishments achieved under the subject award.

Scientific-technical cooperation with foreign (esp. Europe and INSC partner countries) nuclear regulatory authorities and their technical support organizations in the fields of nuclear safety of operating nuclear power plants and on the concept evaluation of generation 3+ plants. Final report; Wissenschaftlich-Technische Zusammenarbeit (WTZ) mit auslaendischen (insbesondere in Europa und INSC-Partnerstaaten) atomrechtlichen Behoerden und deren Sachverstaendigenorganisationen zur nuklearen Sicherheit in Betrieb befindlicher Kernkraftwerke und zur Konzeptbewertung von Generation-3+-Anlagen. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Wolff, Holger

2016-09-15

The BMUB/BfS-Project 3614I01512 forms the frame of the GRS for the scientific-technical cooperation with Technical Support Organisations and Nuclear Regulatory Authorities in the field of nuclear safety in operating NPPs and for the concept evaluation of generation 3{sup +} plants in Europe and INSC Partner Countries. In the present final project report results are described which were gained within the project duration 15.10.2014 up to the 30.09.2016 in the following working packages: Investigations following the catastrophe of Fukushima Daiichi, Evaluation of selected National Action Plans, DBA and severe accident analyses for NPP with PWR (WWER-440, WWER-1000), cooperation with INSC partner countries on DBA, BDBA and severe accident analyses for WWER plants of generation 3{sup +} and building NRA and safety evaluation capacities and decommissioning of nuclear facilities and disposal of radioactive waste. The results are preceded by an outline on the activities related to the project management and to the planning of the bilateral work.

77 FR 30514 - Native Hawaiian Career and Technical Education Program; Final Waiver and Extension of Project Period

Science.gov (United States)

2012-05-23

... DEPARTMENT OF EDUCATION Native Hawaiian Career and Technical Education Program; Final Waiver and... Career and Technical Education Program Catalog of Federal Domestic Assistance (CFDA) Number: 84.259A... Technical Education Program (NHCTEP), the Secretary hereby waives 34 CFR 75.261(c)(2) in order to extend the...

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

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Schuur, Edward [Northern Arizona Univ., Flagstaff, AZ (United States); Luo, Yiqi [Univ. of Oklahoma, Norman, OK (United States)

2016-12-01

This final grant report is a continuation of the final grant report submitted for DE-SC0006982 as the Principle Investigator (Schuur) relocated from the University of Florida to Northern Arizona University. This report summarizes the original project goals, as well as includes new project activities that were completed in the final period of the project.

Characterization of the radon source in North-Central Florida. Final report part 1 -- Final project report; Final report part 2 -- Technical report

International Nuclear Information System (INIS)

1997-01-01

This report contains two separate parts: Characterization of the Radon Source in North-Central Florida (final report part 1 -- final project report); and Characterization of the Radon Source in North-Central Florida (technical report). The objectives were to characterize the radon 222 source in a region having a demonstrated elevated indoor radon potential and having geology, lithology, and climate that are different from those in other regions of the U.S. where radon is being studied. Radon availability and transport in this region were described. Approaches for predicting the radon potential of lands in this region were developed

Clean Energy Works Oregon Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Jacob, Andria [City of Portland; Cyr, Shirley [Clean Energy Works

2013-12-31

In April 2010, the City of Portland received a $20 million award from the U.S. Department of Energy, as part of the Energy Efficiency and Conservation Block Grant program. This award was appropriated under the American Recovery and Reinvestment Act (ARRA), passed by President Obama in 2009. DOE’s program became known as the Better Buildings Neighborhood Program (BBNP). The BBNP grant objectives directed the City of Portland Bureau of Planning and Sustainability (BPS) as the primary grantee to expand the BPS-led pilot program, Clean Energy Works Portland, into Clean Energy Works Oregon (CEWO), with the mission to deliver thousands of home energy retrofits, create jobs, save energy and reduce carbon dioxide emissions.The Final Technical Report explores the successes and lessons learned from the first 3 years of program implementation.

Energy Impact Illinois - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Olson, Daniel [Senior Energy Efficiency Planner; Plagman, Emily [Senior Energy Planner; Silberhorn, Joey-Lin [Energy Efficiency Program Assistant

2014-02-18

Energy Impact Illinois (EI2) is an alliance of government organizations, nonprofits, and regional utility companies led by the Chicago Metropolitan Agency for Planning (CMAP) that is dedicated to helping communities in the Chicago metropolitan area become more energy efficient. Originally organized as the Chicago Region Retrofit Ramp-Up (CR3), EI2 became part of the nationwide Better Buildings Neighborhood Program (BBNP) in May 2010 after receiving a $25 million award from the U.S. Department of Energy (DOE) authorized through the American Recovery and Reinvestment Act of 2009 (ARRA). The program’s primary goal was to fund initiatives that mitigate barriers to energy efficiency retrofitting activities across residential, multifamily, and commercial building sectors in the seven-county CMAP region and to help to build a sustainable energy efficiency marketplace. The EI2 Final Technical Report provides a detailed review of the strategies, implementation methods, challenges, lessons learned, and final results of the EI2 program during the initial grant period from 2010-2013. During the program period, EI2 successfully increased direct retrofit activity in the region and was able to make a broader impact on the energy efficiency market in the Chicago region. As the period of performance for the initial grant comes to an end, EI2’s legacy raises the bar for the region in terms of helping homeowners and building owners to take action on the continually complex issue of energy efficiency.

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

District heating and cooling systems for communities through power plant retrofit and distribution networks. Phase I. Identification and assessment. Final report

Energy Technology Data Exchange (ETDEWEB)

1979-09-01

The study assesses the preliminary technical, economic, and institutional feasibility of district heating systems achieved by retrofitting existing utility power plants in three Wisconsin cities: Green Bay, Janesville/Beloit, and Madison. The overall approach consists of surveying the State of Wisconsin to identify all existing intermediate and base-loaded electric-generating facilities. Once identified, screening criteria are developed to narrow the list to the three most promising sites. For each of the three sites, an extensive market analysis is performed to identify and characterize thermal loads and survey potential users on their views and concerns regarding the concept. Parallel to this effort, each of the three sites is evaluated on its technical and institutional merits. The technical evaluation centers on identifying and evaluating utility plant retrofit schemes and distribution system alternatives to service the identified thermal market. The institutional analysis evaluates potential barriers such as environmental, distribution system right-of-way, and legal issues within the infrastructure of the state, city, and community. Finally, all previous aspects of the analysis are combined to determine the economic viability of each site. It is concluded that Green Bay is the most promising site.

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

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.

Direct application of geothermal energy at the L'eggs Product Plant, Las Cruces, New Mexico. Final report

Energy Technology Data Exchange (ETDEWEB)

1981-02-01

The study program to determine the feasibility of interfacing a potential geothermal resource of Dona Ana County, New Mexico L'eggs Product industrial process is discussed in this final report. Five separate sites were evaluated initially as to geothermal potential and technical feasibility. Preliminary analysis revealed that three sites were considered normal, but that two sites (about three miles from the L'eggs Plant) had very high shallow subsurface temperature gradients (up to 14.85/sup 0/F/100 ft). An initial engineering analysis showed that to meet the L'eggs plant temperature and energy requirements a geothermal fluid temperature of about 250/sup 0/F and 200 gpm flow rate would be necessary. A brief economic comparison indicated that the L'eggs plant site and a geothermal site approximately four miles from the plant did merit further investigation. Detailed engineering and economic design and analysis of these two sites (including the drilling of an 1873 feet deep temperature gradient test hole at the L'eggs Plant) showed that development of the four mile distant site was technically feasible and was the more economic option. It was determined that a single-stage flash system interface design would be most appropriate for the L'eggs Plant. Approximately 39 billion Btu/yr of fossil fuel could be replaced with geothermal energy at the L'eggs facility for a total installed system cost of slightly over $2 million. The projected economic payback period was calculated to be 9.2 years before taxes. This payback was not considered acceptable by L'eggs Products, Inc., to merit additional design or construction work at this time.

Final Technical Report for DE-FG02-98ER45737

Energy Technology Data Exchange (ETDEWEB)

Ade, Harald W.

2018-04-24

Final Technical Report For DOE Grant No. DE-FG02-98ER45737 Development of a Scanning Transmission X-Ray Microscope Polymer Thin Films and Self Assembled Monolayers: Pattern Formation and Surface Interactions NEXAFS Microscopy and Resonant Scattering of Polymeric Materials Organic Heterojunction Devices: Structure, Composition, and Performance at <20 nm Resolution Fundamental Science of High Open Circuit Voltage Excitonic Solar Cells Control of Interface- and Mesoscopic Structure in High Performance Organic Solar Cells: Towards a Predictive Device Paradigm

Plant systems/components modularization study. Final report. [PWR

Energy Technology Data Exchange (ETDEWEB)

1977-07-01

The final results are summarized of a Plant Systems/Components Modularization Study based on Stone and Webster's Pressurized Water Reactor Reference Design. The program has been modified to include evaluation of the most promising areas for modular consideration based on the level of the Sundesert Project engineering design completion and the feasibility of their incorporation into the plant construction effort.

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.

B-Plant Canyon Ventilation Control System Description; FINAL

International Nuclear Information System (INIS)

MCDANIEL, K.S.

1999-01-01

Project W-059 installed a new B Plant Canyon Ventilation System. Monitoring and control of the system is implemented by the Canyon Ventilation Control System (CVCS). This document describes the CVCS system components which include a Programmable Logic Controller (PLC) coupled with an Operator Interface Unit (OIU) and application software. This document also includes an Alarm Index specifying the setpoints and technical basis for system analog and digital alarms

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Eggeman, Tim [ZeaChem Inc., Lakewood, CO (United States); O' Neill, Brian [ZeaChem Inc., Lakewood, CO (United States)

2016-08-17

ZeaChem Inc. and US DOE successfully demonstrated the ZeaChem process for producing sugars and ethanol from high-impact biomass feedstocks. The project was executed over a 5-year period under a $31.25 million cooperative agreement (80:20 Federal:ZeaChem cost share). The project was managed by dividing it into three budget periods. Activities during Budget Period 1 were limited to planning, permitting, and other pre-construction planning. Budget Period 2 activities included engineering, procurement, construction, commissioning, start-up and initial operations through the Independent Engineer Test Runs. The scope of construction was limited to the Chem Frac and Hydrogenolysis units, as the Core Facility was already in place. Construction was complete in December 2012, and the first cellulosic ethanol was produced in February 2013. Additional operational test runs were conducted during Budget Period 3 (completed June 2015) using hybrid poplar, corn stover, and wheat straw feedstocks, resulting in the production of cellulosic ethanol and various other biorefinery intermediates. The research adds to the understanding of the Chem Frac and Hydrogenolysis technologies in that the technical performance of each unit was measured, and the resulting data and operational experience can be used as the basis for engineering designs, thus mitigating risks for deployment in future commercial facilities. The Chem Frac unit was initially designed to be operated as two-stage dilute acid hydrolysis, with first stage conditions selected to remove the hemicellulose fraction of the feedstock, and the second stage conditions selected to remove the cellulose fraction. While the Chem Frac unit met or exceeded the design capacity of 10 ton(dry)/day, the technical effectiveness of the Chem Frac unit was below expectations in its initial two-stage dilute acid configuration. The sugars yields were low, the sugars were dilute, and the sugars had poor fermentability caused by excessive inhibitors

DE-FG02-04ER63746 FinalTechnicalReport

Energy Technology Data Exchange (ETDEWEB)

Lidstrom, M.E.

2009-09-05

This is the final technical report for a project involving the study of stress response systems in the radiation-resistant bacterium, Deinococcus radiodurans. Three stresses of importance for a mixed waste treatment strain were studied, heat shock, solvent shock, and phosphate starvation. In each case, specific genes involved in the ability to survive the stress were identified using a systems biology approach, and analysis of mutants was used to understand mechanisms. This study has led to increased understanding of the ways in which a potential treatment strain could be manipulated to survive multiple stresses for treatment of mixed wastes.

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)

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.

Functional criteria for emergency response facilities. Technical report (final)

International Nuclear Information System (INIS)

1981-02-01

This report describes the facilities and systems to be used by nuclear power plant licensees to improve responses to emergency situations. The facilities include the Technical Support Center (TSC), Onsite Operational Support Center (OSC), and Nearsite Emergency Operations Facility (EOF), as well as a brief discussion of the emergency response function of the control room. The data systems described are the Safety Parameter Display System (SPDS) and Nuclear Data Link (NDL). Together, these facilities and systems make up the total Emergency Response Facilities (ERFs). Licensees should follow the guidance provided both in this report and in NUREG-0654 (FEMA-REP-1), Revision 1, for design and implementation of the ERFs

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

Guidelines for preparing specifications for nuclear power plants (NCIG-04): Final report

International Nuclear Information System (INIS)

1988-04-01

This document provides guidance for preparing technical requirements used in procurement and installation specifications. It is a compilation of recommend practices for writing specifications to preserve the best guidance coming out of recent years experience from construction of nuclear plants. It is intended to: Establish good practices for the content of specifications used for nuclear power plants; Be applicable to a wide range of specifications used for initial construction of plants and modifications to existing plants, including equipment replacement; and Provide guidance to specification preparers and reviewers

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

Mathematics Intensive Summer Session (MISS). Final technical report

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

This final technical report appears in two parts: the report for the 1995 summer MISS program and the report for the 1996 summer MISS program. Copies of the US Department of Energy Pre-Freshman Enrichment Program 1995 Entry Form and 1996 Entry Form completed by all participants were sent to the Oak Ridge Institute for Science and Education in the fall of 1995 and 1996 respectively. Those forms are on file should they be needed. Attached also is a copy of the Summary of ideas for panel discussions, problem-solving sessions, or small group discussions presented at the Department of Energy Oak Ridge Institute for Science and Education Pre-Freshman Enrichment Program Project Directors Meeting held in San Antonio, TX, November 12--14, 1995.

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

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.)

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

Assessment of technical risks and R and D requirements for a magnetic confinement fusion fuel system. Final report

International Nuclear Information System (INIS)

DeFreece, D.A.

1983-11-01

This report documents a specific use and results of a novel technique for assessing the technical risks associated with the hardware development of a possible future commercial fusion power plant fuel system. Technical risk is defined as the risk that a particular technology or component which is currently under development will not achieve a set of required technical specifications. A technical risk assessment is the quantification of this risk. This Technical Risk Assessment (TRA) methodology was applied to a deuterium-tritium fuel system for a magnetic-confinement fusion power plant. The fuel system is defined to support a generic commercial reactor with at least two viable options for each critical subsystem. Each subsystem option is defined in detail including nominal performance requirements and subsystem interfaces. Subsystem experts were canvassed to obtain values for past, present and future technical performance parameters for each of the subsystem options. These forecasts are presented as probabilities of achieving given levels of performance in specific time periods for assumed funding scenarios. Several funding scenarios were examined to discern whether performance limitations are caused by funding or technology. A computerized Fuel System simulation is described which uses these subsystem performance parameter forecasts as inputs

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

University of Maryland component of the Center for Multiscale Plasma Dynamics: Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Dorland, William [University of Maryland

2014-11-18

The Center for Multiscale Plasma Dynamics (CMPD) was a five-year Fusion Science Center. The University of Maryland (UMD) and UCLA were the host universities. This final technical report describes the physics results from the UMD CMPD.

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.

SENTINEL trademark technical basis report for Limerick. Final report

International Nuclear Information System (INIS)

Burns, E.T.; Lee, L.K.; Mitman, J.T.; Vanover, D.E.; Wilson, D.K.

1997-12-01

PECO Energy in cooperation with the Electric Power Research Institute (EPRI) installed the SENTINEL trademark software at its Limerick Generating Station. This software incorporates models of the safety and support systems which are used to display the defense in depth present in the plant and a quantitative assessment of the plant risks during proposed on-line maintenance. During the past year, PECO Energy personnel have used this display to evaluate the safety of proposed on-line maintenance schedules. The report describes the motivation for and the development of the SENTINEL software. It describes the generation of Safety Function Assessment Trees and Plant Transient Assessment Trees and their use in evaluating the level of defense-in-depth of key plant safety functions and the susceptibility of the plant to critical transient events. Their results are displayed by color indicators ranging from green, through yellow and orange to red to show increasingly hazardous conditions. The report describes the use of the Limerick Probabilistic Safety Assessment within the SENTINEL code to calculate an instantaneous core damage frequency and the criteria by which this frequency is translated to a color indicator. Finally, the report describes the Performance Criteria Assessment which tracks and trends system/train unavailability to document conformance to the requirements of the Maintenance Rule

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

Final radioactive waste disposal: A European comparison of organization and costs

International Nuclear Information System (INIS)

Drasdo, P.

2000-01-01

The investigation is aimed to the comparison of organization structures of operators (plants) and governmental institutions concerned with the final disposal of radioactive waste. The study is covering Germany, France, United Kingdom and Sweden. The capital amount of total final disposal costs are the highest in Germany, the lowest in Sweden. This is also true for the final disposal costs that have to be financed by electricity production from nuclear power plants. The reasons for the differences with respect to economic efficiencies, political decisions and technical concepts are discussed

Nuclear power plant life management processes: Guidelines and practices for heavy water reactors. Report prepared within the framework of the Technical Working Groups on Advanced Technologies for Heavy Water Reactors and on Life Management of Nuclear Power Plants

International Nuclear Information System (INIS)

2006-06-01

The time is right to address nuclear power plant life management and ageing management issues in terms of processes and refurbishments for long term operation and license renewal aspects of heavy water reactors (HWRs) because some HWRs are close to the design life. In general, HWR nuclear power plant (NPP) owners would like to keep their NPPs in service as long as they can be operated safely and economically. This involves the consideration of a number of factors, such as the material condition of the plant, comparison with current safety standards, the socio-political climate and asset management/ business planning considerations. This TECDOC deals with organizational and managerial means to implement effective plan life management (PLiM) into existing plant in operating HWR NPPs. This TECDOC discusses the current trend of PLiM observed in NPPs to date and an overview of PLiM programmes and considerations. This includes key objectives of such programs, regulatory considerations, an overall integrated approach, organizational and technology infrastructure considerations, importance of effective plant data management and finally, human issues related to ageing and finally integration of PLiM with economic planning. Also general approach to HWR PLiM, including the key PLiM processes, life assessment for critical structures and components, conditions assessment of structures and components and obsolescence is mentioned. Technical aspects are described on component specific technology considerations for condition assessment, example of a proactive ageing management programme, and Ontario power generation experiences in appendices. Also country reports from Argentina, Canada, India, the Republic of Korea and Romania are attached in the annex to share practices and experiences to PLiM programme. This TECDOC is primarily addressed to both the management (decision makers) and technical staff (engineers and scientists) of NPP owners/operators and technical support

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.

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

Integrated Plant Safety Assessment, Systematic Evaluation Program, Palisades Plant (Docket No. 50-255)

International Nuclear Information System (INIS)

1983-11-01

This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Palisades Plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The Final IPSAR and its supplement will form part of the bases for considering the conversion of the provisional operating license to a full-term operating license

Beowawe Bottoming Binary Unit - Final Technical Report for EE0002856

Energy Technology Data Exchange (ETDEWEB)

McDonald, Dale Edward

2013-02-12

This binary plant is the first high-output refrigeration based waste heat recovery cycle in the industry. Its working fluid is environmentally friendly and as such, the permits that would be required with a butane based cycle are not necessary. The unit is modularized, meaning that the unit’s individual skids were assembled in another location and were shipped via truck to the plant site. This project proves the technical feasibility of using low temperature brine The development of the unit led to the realization of low temperature, high output, and environmentally friendly heat recovery systems through domestic research and engineering. The project generates additional renewable energy for Nevada, resulting in cleaner air and reduced carbon dioxide emissions. Royalty and tax payments to governmental agencies will increase, resulting in reduced financial pressure on local entities. The major components of the unit were sourced from American companies, resulting in increased economic activity throughout the country.

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)

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)

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

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.)

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.)

A study on safety assessment methodology for a vitrification plant

Energy Technology Data Exchange (ETDEWEB)

Seo, Y. C.; Lee, G. S.; Choi, Y. C.; Kim, G. H. [Yonsei Univ., Seoul (Korea, Republic of)

2002-03-15

In this study, the technical and regulatory status of radioactive waste vitrification technologies in foreign and domestic plants is investigated and analyzed, and then significant factors are suggested which must be contained in the final technical guideline or standard for the safety assessment of vitrification plants. Also, the methods to estimate the stability of vitrified waste forms are suggested with property analysis of them. The contents and scope of the study are summarized as follows : survey of the status on radioactive waste vitrification technologies in foreign and domestic plants, survey of the characterization methodology for radioactive waste form, analysis of stability for vitrified waste forms, survey and analysis of technical standards and regulations concerned with them in foreign and domestic plants, suggestion of significant factors for the safety assessment of vitrification plants, submission of regulated technical standard on radioactive waste vitrification plats.

SRC-I demonstration plant analytical laboratory methods manual. Final technical report

Energy Technology Data Exchange (ETDEWEB)

Klusaritz, M.L.; Tewari, K.C.; Tiedge, W.F.; Skinner, R.W.; Znaimer, S.

1983-03-01

This manual is a compilation of analytical procedures required for operation of a Solvent-Refined Coal (SRC-I) demonstration or commercial plant. Each method reproduced in full includes a detailed procedure, a list of equipment and reagents, safety precautions, and, where possible, a precision statement. Procedures for the laboratory's environmental and industrial hygiene modules are not included. Required American Society for Testing and Materials (ASTM) methods are cited, and ICRC's suggested modifications to these methods for handling coal-derived products are provided.

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)

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

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.

Evaluation of Routine Atmospheric Sounding Measurements using Unmanned Systems (ERASMUS): Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

de Boer, Gijs [Univ. of Colorado, Boulder, CO (United States); Lawrence, Dale [Univ. of Colorado, Boulder, CO (United States); Palo, Scott [Univ. of Colorado, Boulder, CO (United States); Argrow, Brian [Univ. of Colorado, Boulder, CO (United States); LoDolce, Gabriel [Univ. of Colorado, Boulder, CO (United States); Curry, Nathan [Univ. of Colorado, Boulder, CO (United States); Weibel, Douglas [Univ. of Colorado, Boulder, CO (United States); Finamore, William [Univ. of Colorado, Boulder, CO (United States); D' Amore, Phillip [Univ. of Colorado, Boulder, CO (United States); Borenstein, Steven [Univ. of Colorado, Boulder, CO (United States); Nichols, Tevis [Univ. of Colorado, Boulder, CO (United States); Elston, Jack [Blackswift Technologies, Boulder, CO (United States); Ivey, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bendure, Albert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schmid, Beat [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Long, Charles [Univ. of Colorado, Boulder, CO (United States); Telg, Hagen [Univ. of Colorado, Boulder, CO (United States); Gao, Ru-Shan [National Oceanic and Atmospheric Administration (NOAA), Boulder, CO (United States); Hock, Terry [National Center for Atmospheric Research, Boulder, CO (United States); Bland, Geoff [NASA Ames Research Center (ARC), Moffett Field, Mountain View, CA (United States)

2017-03-29

This final technical report details activities undertaken as part of the referenced project. Included is information on the preparation of aircraft for deployment to Alaska, summaries of the three deployments covered under this project, and a brief description of the dataset and science directions pursued. Additionally, we provide information on lessons learned, publications, and presentations resulting from this work.

Final Technical Report for contract number DE-FG02-05ER15670

Energy Technology Data Exchange (ETDEWEB)

Glazebrook, Jane [Univ. of Minnesota, Minneapolis, MN (United States)

2016-02-29

This is the final technical report for contract number DE-FG02-05ER15670. The project is now complete, and results of the project have been published. Two papers were published based on work done in the last three-year funding period. The DOIs of these papers are included below. The abstracts of the papers, providing summaries of the work, are included in the body of the report.

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)

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.)

CHP plant Legionowo Poland - Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-12-01

In 1997, a new Energy Law was passed in Poland. An important element of the law is that local energy planning is made obligatory. The law describes obligatory tasks and procedures for Polish municipalities related to planning and organisation of the energy sector. With the objective of supporting the Polish municipalities in their obligations according to the energy law of 1997, the project 'Energy Planning in Poland at Municipal Level - Support to Decision Makers' was launched. As part of the project, Municipal Guideline Reports have been elaborated for three model municipalities. These guidelines present the basis for the Energy Supply Plans in these municipalities. For the city of Legionowo, the following was recommended: 1. The planning processes initiated during the project should be continues/followed up, 2. Master Plan for the district heating system should be prepared, 3. The possibilities of establishment of a major natural gas-fired CHP plant of the Combined Cycle type should be investigated. The present report is the final Master Plan based on the following reports: Master Plan for Legionowo - Status Report; Master Plan for Legionowo - Hydraulic Analysis; CHP Plant Legionowo Poland - CHP Feasibility Analysis. The final Master Plan describes the status in the DH Company in Legionowo, possible improvements and an investment plan for the selected scenario. (BA)

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

Technical and logistic provisions for the delivery of radioactive wastes in the final repository Konrad

International Nuclear Information System (INIS)

Poeppinghaus, Jens

2013-01-01

The beginning of radioactive waste delivery to the final repository Konrad is planned for 2019. The main issue for the technical and logistic provisions is the development of a concept for the transport of the licensed radioactive waste containers to the site, including a turning concept for cylindrical waste forms and planning, construction and manufacture of transport equipment. Further issues include a logistic concept considering specific boundary conditions as administrative processes, priorities, special features of the delivering institutions and technical requirements of the repository.

Osiris and SOMBRERO inertial confinement fusion power plant designs. Volume 2, Designs, assessments, and comparisons, Final report

Energy Technology Data Exchange (ETDEWEB)

Meier, W.R.; Bieri, R.L.; Monsler, M.J.

1992-03-01

The primary objective of the of the IFE Reactor Design Studies was to provide the Office of Fusion Energy with an evaluation of the potential of inertial fusion for electric power production. The term reactor studies is somewhat of a misnomer since these studies included the conceptual design and analysis of all aspects of the IFE power plants: the chambers, heat transport and power conversion systems, other balance of plant facilities, target systems (including the target production, injection, and tracking systems), and the two drivers. The scope of the IFE Reactor Design Studies was quite ambitious. The majority of our effort was spent on the conceptual design of two IFE electric power plants, one using an induction linac heavy ion beam (HIB) driver and the other using a Krypton Fluoride (KrF) laser driver. After the two point designs were developed, they were assessed in terms of their (1) environmental and safety aspects; (2) reliability, availability, and maintainability; (3) technical issues and technology development requirements; and (4) economics. Finally, we compared the design features and the results of the assessments for the two designs.

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

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.)

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

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

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

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.)

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

Correlated charge-changing uion-atom collisions. Final Technical Report

International Nuclear Information System (INIS)

John Tanis

2005-01-01

This document comprises the final technical report for atomic collisions research supported by DOE grant No. DE-FG02-87ER13778 from September 1, 2001 through August 31, 2004. The research involved the experimental investigation of excitation and charge-changing processes occurring in ion-atom and ion-molecule collisions. Major emphases of the study were: (1) interference effects resulting from coherent electron emission in H2, (2) production of doubly vacant K-shell (hollow ion) states due to electron correlation, and (3) formation of long-lived metastable states in electron transfer processes. During the period of the grant, this research resulted in 23 publications, 12 invited presentations, and 39 contributed presentations at national and international meetings and other institutions. Brief summaries of the completed research are presented below

FERMI(at)Elettra FEL Design Technical Optimization Final Report

International Nuclear Information System (INIS)

Fawley, William; Penn, Gregory; Allaria, Enrico; De Ninno, Giovanni; Graves, William

2006-01-01

This is the final report of the FEL Design Group for the Technical Optimization Study for the FERMI(at)ELETTRA project. The FERMI(at)ELETTRA project is based on the principle of harmonic upshifting of an initial ''seed'' signal in a single pass, FEL amplifier employing multiple undulators. There are a number of FEL physics principles which underlie this approach to obtaining short wavelength output: (1) the energy modulation of the electron beam via the resonant interaction with an external laser seed (2) the use of a chromatic dispersive section to then develop a strong density modulation with large harmonic overtones (3) the production of coherent radiation by the microbunched beam in a downstream radiator. Within the context of the FERMI project, we discuss each of these elements in turn

Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

International Nuclear Information System (INIS)

Zadrazil, J.; Cvan, M.; Strimelsky, V.

1987-01-01

The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)

Handbook for nuclear power plant self-assessment programs. Final report, July 1991

International Nuclear Information System (INIS)

1991-07-01

EPRI has prepared this handbook to help utilities with their Self-Assessment Programs at nuclear power plants. Self-assessments are independent reviews performed by nuclear plant utilities to identify trends in operational activities that are important to safety, and to assess the impact of these trends on plant safety. Activities performed as self-assessments include reviews and evaluations of plant performance and abnormal events, technical evaluations of plant activities to identify potential problem areas, and reviews of other sources of plant design and operating experience for applicability to safety. This handbook is based on information obtained from utilities and includes examples of activities and methods that have proven effective. The handbook includes a summary of NRC requirements, guidelines for self-assessment program planning, descriptions and examples of investigative techniques, and key references that can be consulted for additional information. It can serve as a training guide for plant staff members who are assigned to self-assessment activities. (author)

Telephone Flat Geothermal Development Project Environmental Impact Statement Environmental Impact Report. Final

Energy Technology Data Exchange (ETDEWEB)

None

1999-02-01

This Final Environmental Impact Statement and Environmental Impact Report (Final EIS/EIR) has been prepared to meet the requirements of the National Environmental Policy Act (NEPA) and the California Environmental Quality Act (CEQA). The Proposed Action includes the construction, operation, and decommissioning of a 48 megawatt (gross) geothermal power plant with ancillary facilities (10-12 production well pads and 3-5 injection well pads, production and injection pipelines), access roads, and a 230-kilovolt (kV) transmission line in the Modoc National Forest in Siskiyou County, California. Alternative locations for the power plant site within a reasonable distance of the middle of the wellfield were determined to be technically feasible. Three power plant site alternatives are evaluated in the Final EIS/EIR.

SIMS study on statistics and environmental factors in health. Final technical report to Department of Energy

International Nuclear Information System (INIS)

1982-07-01

This final technical report to DOE consists of five individual technical reports and one working paper by members of the SIMS Study at Stanford. Research topics include testing goodness-of-fit for the distribution of errors in regression models, mathematical models of cancer and their use in risk assessment, pollutant standards index (Psi), osteosarcomas among beagles exposed to 239 Plutonium, air pollution and respiratory disease, and models of human exposure to air pollution. Individual summaries of the six reports are indexed separately

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)

Final treatment of liquid radioactive wastes

International Nuclear Information System (INIS)

Svolik, S.

2004-01-01

Final treatment of liquid radioactive wastes which are produced by 1 st and 2 nd bloc of the Mochovce NPP, prepares the NPP in its natural range. The purpose of the equipment is liquidation of wastes, which are formed at production. Wastes are warehoused in the building of active auxiliary plants in the present time, where are reservoirs in which they are deposited. Because they are already feeling and in 2006 year they should be filled definitely, it is necessary to treat them in that manner, so as they may be liquidated. Therefore the Board of directors of the Slovenske elektrarne has disposed about construction of final treatment of liquid radioactive wastes in the Mochovce NPP. Because of transport the wastes have to be treated in the locality of power plant. Technically, the final treatment of the wastes will be interconnected with building of active operation by bridges. These bridges will transport the wastes for treatment into processing centre

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

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)

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

Intelligent distributed control for nuclear power plants

International Nuclear Information System (INIS)

Klevans, E.H.

1993-01-01

This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 steam plant. Described in this Final (Third Annual) Technical Progress Report is the accomplishment of the project's final milestone, an in-plant intelligent control experiment conducted on April 1, 1993. The development of the experiment included: simulation validation, experiment formulation and final programming, procedure development and approval, and experimental results. Other third year developments summarized in this report are: (1) a theoretical foundation for Reconfigurable Hybrid Supervisory Control, (2) a steam plant diagnostic system, (3) control console design tools and (4) other advanced and intelligent control

Concept of a HTR modular plant for generation of process heat in a chemical plant

International Nuclear Information System (INIS)

1991-07-01

This final report summarizes the results of a preliminary study on behalf of Buna AG and Leunawerke AG. With regard to the individual situations the study investigated the conditions for modular HTR-2 reactors to cover on-site process heat and electric power demands. HTR-2 reactor erection and operation were analyzed for their economic efficiency compared with fossil-fuel power plants. Considering the prospective product lines, the technical and economic conditions were developed in close cooperation with Buna AG and Leunawerke AG. The study focused on the technical integration of modular HTR reactors into plants with regard to safety concepts, on planning, acceptance and erection concepts which largely exclude uncalculable scheduling and financial risks, and on comparative economic analyses with regard to fossil-fuel power plants. (orig.) [de

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)

Aspects of the role of scientific-technical expert knowledge in administrative court procedures on licensing of large technical projects

International Nuclear Information System (INIS)

Wagner, H.

1983-01-01

On the basis of atomic energy law, the author explains some specific problems associated with the respective roles of experts (or expert bodies) and courts of law. In legal theory, it is comparatively easy to draw the line between the two functions, but in practice this delimination meets with difficulties. Finally, the author proposes to improve the definitions of the respective functions of experts (expert bodies) and courts of law in procedures dealing with permits of large technical facilities as follows: A highly qualified, independent body of experts in a technically representative composition lays down, in a binding way, the main elements of the safety standard of a specific plant or type of plant. The responsible administrative authority, after having examined all other legal conditions, grants the permit for that plant. There are no objections to such a model in the light either of aspects of constitutional law or of legal policy or constitutional policy, not are there any practical reasons against this approach. The only doubtful aspect is the present political feasibility. (orig.) [de

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

Nuclear plant life cycle management implementation guide. Final report

International Nuclear Information System (INIS)

Sliter, G.E.; Negin, C.A.

1998-11-01

Nuclear power plants, as baseload suppliers of electricity, are major corporate assets. As the nuclear industry enters its fourth decade as a major producer of clean electricity, the structure of the utility industry is undergoing a historical landmark transition from economic deregulation to a competitive, market-driven industry. An integral part of competition is to manage the operation of the key asset, the plant, in the long term, thereby enhancing its long-term profitability. Life cycle management (LCM) is a well-known technical-economic decision-making process for any large industrial facility. LCM optimizes the service life of a facility and maximizes its life-cycle asset value. LCM integrates aging management (maintaining the availability of costly-to-replace components and structures) with asset management (plant valuation and investment strategies that account for economic, performance, regulatory, and environmental uncertainties). LCM involves predicting maintenance, repair, and other capital costs for a nuclear unit far into the future, as well as planning and managing strategic issues such as waste disposal, fuel storage, decommissioning, and public acceptance. This Life Cycle Management Implementation Guide introduces the reader to the LCM concept and its benefits, describes the elements and activities associated with an LCM program (most of which already exist in all plants), gives an overview of asset and aging management, and provides key references related to life cycle management for nuclear power plants. It also summarizes the major elements of life cycle management required for license renewal or, for newer plants, keeping open the option of license renewal

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

Biomass and bio-fuel based poly-generation for off-grid and grid-connected operation. Final technical report

Energy Technology Data Exchange (ETDEWEB)

2012-07-01

The overall objective of this project was to design and build a combined heat and power plant based on an updraft gasifier and a 35 kW electrical output Stirling engine and further to test the flexibility of the plant with regards to fuel and application. In the project a containerized combined heat and power plant including a 200 kW updraft gasifier and a 35 kW electrical output Stirling engine was designed, the specified components were procured, the plant was installed in the three containers and the plant was erected at Amagerforbraendingen ready for the COP15 in November 2009. The potential of operating the Stirling engine in island-mode (without grid connection) was investigated by mathematical modelling. Using an absorption cooling plant connected to the Stirling CHP plant was also investigated. A technical feasibility study was undertaken and it was concluded that from the two available technologies (water/LiBr and Ammonia/water) the appropriate choice is depending on the required cooling temperature. Test runs focussed on investigating the fuel flexibility of two different configurations of Stirling engine CHP plants were carried out - respectively the updraft gasifier plant (the containerized plant and the DTU plant) and the pyrolysis plant (the plant situated at Barritskov). In order to perform these test runs a stable operation is required. On both the containerized plant and the pyrolysis plant this proved to be more challenging than expected and therefore the number of fuels tested was limited to willow chips at the containerized plant and dry wood residues, wood pellets and straw pellets on the pyrolysis plant. For all tested fuels it was possible to operate the plants, however different issues mainly related to the quality of the fuels were encountered. And so it can be concluded that the quality of the fuel is critical for the operation of both the updraft gasifier plant and the pyrolysis plant. A comprehensive desktop evaluation of the feasibility

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…

The research project on technical information basis for aging management in Fukui and Kinki area. Final report

International Nuclear Information System (INIS)

Fujimura, Kimiya; Nagayama, Shigeru; Watarumi, Chikae; Toudou, Tsugihiko

2011-01-01

The Research Project on Technical Information Basis for Aging Management was initiated in FY2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI) as a five-year program effectively, to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging nuclear power plants are regulated. Upon taking part in the technical strategy map for Aging Management and Safe Long Term Operation, the experiences and achievements of the participating organizations were taken into account and the following four topics were chosen. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. 1) The improvement of pipe thinning management in nuclear power plants, 2) The development of inspection techniques to monitor the initiation and propagation of defects, 3) The development of a guideline for evaluating weld repair methods, 4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as a coordinator to make contracts, facilitate execution, and compile annual reports. In FY2010, 11 continuing research subjects were proposed for this project and all were accepted. Of these, 5 subjects were related to the first topic (pipe thinning), 4 subjects to the second topic (inspection technique) and 1 subject to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)

DOE FINAL TECHNICAL REPORT RP

Energy Technology Data Exchange (ETDEWEB)

RUSS PETERMAN

2012-01-01

The City of Georgetown Utility Systems (GUS) patnered with the private sector, the American Public Power Association (APPA) and Southwestern University to design, construct, test and monitor a solar co-generation system directly connected to the GUS electric distribution system. This report consists of the Primary Technical Report and 3 attachments.

Technical support document for the surface disposal of sewage sludge. Final report

International Nuclear Information System (INIS)

1992-11-01

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed

Technical support document for the surface disposal of sewage sludge. Final report

Energy Technology Data Exchange (ETDEWEB)

1992-11-01

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed.

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

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.

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)

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)

Technical assistance contractor Management Plan. Final [report

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Technical Assistance Contractor (TAC) for the Uranium Mill Tailings Remedial Action (UMTRA) Project comprises Jacobs Engineering Group Inc. (JEG) and its major teaming partners [Roy F. Weston, Inc. (RFW), Sergent, Hauskins & Beckwith Agra, Inc. (SHB Agra), and Geraghty & Miller, Inc. (G&M)]. The first three companies have worked together effectively on the UMTRA Project for more than 10 years. With the initiation of the UMTRA Groundwater Project in April 1991, a need arose to increase the TAC`s groundwater technical breadth and depth, so G&M was brought in to augment the team`s capabilities. The TAC contract`s scope is to provide technical, analytical, environmental, engineering, design, inspection, and management support services to the US Department of Energy (DOE) for both surface and groundwater projects. The TAC team continues to support the DOE in completing surface remedial actions and initiating groundwater remediation work for start-up, characterization, design, construction oversight, and remedial operations. A key feature of the TAC`s management approach is the extensive set of communication systems implemented for the UMTRA Project. These systems assist all functional disciplines in performing UMTRA Project tasks associated with management, technical support, administrative support, and financial/project controls.

Experimental Program Final Technical Progress Report: 15 February 2007 to 30 September 2012

Energy Technology Data Exchange (ETDEWEB)

Kinney, Edward R. [University of Colorado, Boulder, CO

2014-09-12

This is the final technical report of the grant DE-FG02-04ER41301 to the University of Colorado at Boulder entitled "Intermediate Energy Nuclear Physics" and describes the results of our funded activities during the period 15 February 2007 to 30 September 2012. These activities were primarily carried out at Fermilab, RHIC, and the German lab DESY. Significant advances in these experiments were carried out by members of the Colorado group and are described in detail.

The final report of ''on-the-job training'' on the CANDU reactor

International Nuclear Information System (INIS)

Kim, D.H.; Koh, B.J.

1983-01-01

This is the final Report for the technical ''on-the-job traning'' for the Wolsung CANDU nuclear power plant which is the first Pressurized Heavy Water Reactor setting up in Korea. The technical ''on-the-job traning'' was established to increase the capability for the nuclear safety evaluation in order to contribute the future safe operation of the CANDU nuclear power plant. The training has been excuted through three level courses as elementary, intermediate and ''on-the-job training'' at Wolsung power plant. The elementary course was introduction to the CANDU basics and fundamentals. The intermediate course was the more advanced course, and the detailed concepts and engineering explanations of the CANDU system had been instructed. The third course was the ''on-the-job training'' at the Wolsung plant site, which was the most emphasized course during the project. (Author)

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.

Technical procedures for ecology: Environmental field program, Deaf Smith County Site, Texas: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including walkover surveys for threatened, endangered, or candidate species; vegetation classification and mapping; reclamation planning; wetland and floodplain determination and characterization of playas; wildlife habitat mapping methods; mammal sampling; bird survey methods; reptile and amphibian survey methods; preexisting environmental; stress and disturbance studies methods; voucher specimens for plants; and voucher specimens to wildlife. 9 refs., 5 figs., 1 tab

Technical Report - FINAL

Energy Technology Data Exchange (ETDEWEB)

Barbara Luke, Director, UNLV Engineering Geophysics Laboratory

2007-04-25

Improve understanding of the earthquake hazard in the Las Vegas Valley and to assess the state of preparedness of the area's population and structures for the next big earthquake. 1. Enhance the seismic monitoring network in the Las Vegas Valley 2. Improve understanding of deep basin structure through active-source seismic refraction and reflection testing 3. Improve understanding of dynamic response of shallow sediments through seismic testing and correlations with lithology 4. Develop credible earthquake scenarios by laboratory and field studies, literature review and analyses 5. Refine ground motion expectations around the Las Vegas Valley through simulations 6. Assess current building standards in light of improved understanding of hazards 7. Perform risk assessment for structures and infrastructures, with emphasis on lifelines and critical structures 8. Encourage and facilitate broad and open technical interchange regarding earthquake safety in southern Nevada and efforts to inform citizens of earthquake hazards and mitigation opportunities

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

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)

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

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)

An Approach to Developing Independent Learning and Non-Technical Skills Amongst Final Year Mining Engineering Students

Science.gov (United States)

Knobbs, C. G.; Grayson, D. J.

2012-01-01

There is mounting evidence to show that engineers need more than technical skills to succeed in industry. This paper describes a curriculum innovation in which so-called "soft" skills, specifically inter-personal and intra-personal skills, were integrated into a final year mining engineering course. The instructional approach was…

Final Technical Report for SISGR: Ultrafast Molecular Scale Chemical Imaging

Energy Technology Data Exchange (ETDEWEB)

Hersam, Mark C. [Northwestern Univ., Evanston, IL (United States). Dept. of Materials Science and Engineering; Guest, Jeffrey R. [Argonne National Lab. (ANL), Argonne, IL (United States). Center for Nanoscale Materials; Guisinger, Nathan P. [Argonne National Lab. (ANL), Argonne, IL (United States). Center for Nanoscale Materials; Hla, Saw Wai [Argonne National Lab. (ANL), Argonne, IL (United States). Center for Nanoscale Materials; Schatz, George C. [Northwestern Univ., Evanston, IL (United States). Dept. of Chemistry; Seideman, Tamar [Northwestern Univ., Evanston, IL (United States). Dept. of Chemistry; Van Duyne, Richard P. [Northwestern Univ., Evanston, IL (United States). Dept. of Chemistry

2017-04-10

The Northwestern-Argonne SISGR program utilized newly developed instrumentation and techniques including integrated ultra-high vacuum tip-enhanced Raman spectroscopy/scanning tunneling microscopy (UHV-TERS/STM) and surface-enhanced femtosecond stimulated Raman scattering (SE-FSRS) to advance the spatial and temporal resolution of chemical imaging for the study of photoinduced dynamics of molecules on plasmonically active surfaces. An accompanying theory program addressed modeling of charge transfer processes using constrained density functional theory (DFT) in addition to modeling of SE-FSRS, thereby providing a detailed description of the excited state dynamics. This interdisciplinary and highly collaborative research resulted in 62 publications with ~ 48% of them being co-authored by multiple SISGR team members. A summary of the scientific accomplishments from this SISGR program is provided in this final technical report.

Technical considerations in snubber reduction programs

International Nuclear Information System (INIS)

Longo, D.L.; Kitz, G.T.

1989-01-01

Snubber reduction has been a much discussed topic for the past several years. The advantages to the owner in terms of reduced radiation exposure, lower operating costs, and better plant maintainability are obvious but difficult to quantify. The costs associated with performing a snubber reduction program can be quantified, but can vary widely depending on how the program is implemented. One approach is to divide the scope of the work into several parts, based on similarities and differences of the plant systems and technical requirements. for example, for this program, the work was divided into three parts: nuclear steam supply system, torus-attached piping, and balance of plant. This approach facilitates addressing the variations in design requirements and the variations in snubber removal priorities that are related to each plant segment. It also allows the experience gained in the first part to be applied to the subsequent parts. This paper describes one utility's experience in successfully completing two parts of a three-part snubber reduction program and focuses on the various technical issues that must be addressed along with those areas where the utility should establish checkpoints that are critical to the success of the overall program. It also describes how the experience from the first two parts will be factored into the final part of the snubber reduction program

Nuclear power plant life management

International Nuclear Information System (INIS)

Rorive, P.; Berthe, J.; Lafaille, J.P.; Eussen, G.

1998-01-01

Several definitions can be given to the design life of a nuclear power plant just as they can be attributed to the design life of an industrial installation: the book-keeping life which is the duration of the provision for depreciation of the plant, the licensed life which corresponds to the duration for which the plant license has been granted and beyond which a new license should be granted by the safety authorities, the design life which corresponds to the duration specified for ageing and fatigue calculations in the design of some selected components during the plant design phase, the technical life which is the duration of effective technical operation and finally the economic life corresponding to the duration of profitable operation of the plant compared with other means of electricity production. Plant life management refers to the measures taken to cope with the combination of licensed, design, technical and economical life. They can include repairs and replacements of components which have arrived to the end of their life due to known degradation processes such as fatigue, embrittlement, corrosion, wear, erosion, thermal ageing. In all cases however, it is of great importance to plan the intervention so as to minimise the economic impact. Predictive maintenance is used together with in-service inspection programs to fulfil this goal. The paper will go over the methodologies adopted in Belgium in all aspects of electrical, mechanical and civil equipment for managing plant life. (author)

Assuring PSA technical adequacy for new advanced light water reactor designs

International Nuclear Information System (INIS)

Lutz, R.J.; Detar, H.L.; Schneider, R.E.

2012-01-01

The Probabilistic Safety Assessment (PSA) for an Advanced Light Water Reactor (ALWR) must exhibit a high level of technical adequacy, or technical quality, in order to be used as a reliable tool for making risk informed decisions concerning design and eventual operation of the plant. During the design phase, decisions on some design features may use the PSA as an input. Also, the PSA may be used as input to other operational decisions during plant design and construction including the development of procedures, development of technical specification limiting conditions for operation and scheduling of preventive maintenance activities. For the existing fleet of light water reactors (LWRs), PSA technical adequacy can be judged from wide ranging acceptance criteria such as the PRA (Probabilistic Risk Assessment) Standard in the United States of America that was developed jointly by the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS). However, the requirements for PRA technical adequacy in this PRA Standard assumes that the plant is built and has operation experience. Some of the requirements cannot be met for ALWRs in the design or construction phase and with no operational history. Key elements of a high level of technical adequacy include procedures, operator interviews, plant walk-downs and equipment reliability histories. The ability to include these key elements into the ALWR PSA to improve technical adequacy will progress as the ALWR progresses from the design stage through the construction stage and finally to the fuel load / pre-operational stage. As the technical adequacy becomes more robust, more confidence can be placed on risk-informed decisions that are made with the PSA. To assist in using the PSA as input to design and operational decisions in the design and construction stages of an ALWR, an addition to the ASME/ANS PRA Standard is being developed. The intent of this addition to the Standard is to provide

Development of a support system to make economic and technical assessments for the issues relating to plant life extension

International Nuclear Information System (INIS)

Takao, T.; Soneda, N.; Sakai, T.

1994-01-01

To realize the life extension of nuclear power plants, overall evaluation for the plant is required, which covers technology, economy such as cost of repair or/and replacement of components, and regal regulations for licensing. A prototype of integrated assessment support system for life extension ''INPLEX'' have developed in order to evaluate the technical and economic issues relating to the plant life extension and to make a life extension scenario. Analysis procedure of INPLEX is as follows. A comparison of the cost between the life extension and the reconstruction is made to see whether the life extension is cost effective or not. Next, components required detailed assessments are selected, and the residual life assessment of these components are made. After those procedures life extension measures are selected and the implementation time schedule is set on the basis of the formulas for predicting the degradation of the components and the component reliability data. Finally the implementation time schedule is optimized from the viewpoint of economy, and the life extension scenario is proposed. INPLEX also has the data base ''PRINS'', in which information and data related to life extension are registered, such as component degradation experiences, degradation management methodologies, degradation mitigation measures, and so on. PRINS can be referred at any time during the operation of INPLEX

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Howe, Gary [RTI International, Research Triangle Park, NC (United States); Albritton, John [RTI International, Research Triangle Park, NC (United States); Denton, David [RTI International, Research Triangle Park, NC (United States); Turk, Brian [RTI International, Research Triangle Park, NC (United States); Gupta, Raghubir [RTI International, Research Triangle Park, NC (United States)

2018-01-31

In September 2010, RTI and the DOE/NETL signed a cooperative agreement (DE-FE000489) to design, build, and operate a pre-commercial syngas cleaning system that would capture up to 90% of the CO₂ in the syngas slipstream, and demonstrate the ability to reduce syngas contaminants to meet DOE’s specifications for chemical production application. This pre-commercial syngas cleaning system is operated at Tampa Electric Company’s (TEC) 250-MWe integrated gasification combined cycle (IGCC) plant at Polk Power Station (PPS), located near Tampa, Florida. The syngas cleaning system consists of the following units: Warm Gas Desulfurization Process (WDP) - this unit processes a syngas flow equivalent of 50 MWe of power (50 MWe equivalent corresponds to about 2.0 MM scfh of syngas on dry basis) to produce a desulfurized syngas with a total sulfur (H₂S+COS) concentration ~ 10 ppmv. Water Gas Shift (WGS) Reactor - this unit converts sufficient CO into CO₂ to enable 90% capture of the CO₂ in the syngas slipstream. This reactor uses conventional commercial shift catalyst technologies. Low Temperature Gas Cooling (LTGC) - this unit cools the syngas for the low temperature activated MDEA process and separates any condensed water. Activated MDEA Process (aMDEA) - this unit employs a non-selective separation for the CO₂ and H₂S present in the raw syngas stream. Because of the selective sulfur removal by the upstream WDP unit, the CO₂ capture target of 90% CO₂ can be achieved with the added benefit that total sulfur concentration in the CO₂ product is < 100 ppmv. An additional advantage of the activated MDEA process is that the non-selective sulfur removal from the treated syngas reduces sulfur in the treated gas to very low sub-ppmv concentrations, which are required for chemical production applications. Testing to date of this pre-commercial syngas cleaning system has shown that the

DIMEC - Final Report

DEFF Research Database (Denmark)

Conrad, Finn

1997-01-01

Final report of the research project DIMEC - Danish InfoMechatronic Control supported by the Danish Technical Research Council, STVF.......Final report of the research project DIMEC - Danish InfoMechatronic Control supported by the Danish Technical Research Council, STVF....

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)

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

Final Technical Report: Hydrogen Codes and Standards Outreach

Energy Technology Data Exchange (ETDEWEB)

Hall, Karen I.

2007-05-12

This project contributed significantly to the development of new codes and standards, both domestically and internationally. The NHA collaborated with codes and standards development organizations to identify technical areas of expertise that would be required to produce the codes and standards that industry and DOE felt were required to facilitate commercialization of hydrogen and fuel cell technologies and infrastructure. NHA staff participated directly in technical committees and working groups where issues could be discussed with the appropriate industry groups. In other cases, the NHA recommended specific industry experts to serve on technical committees and working groups where the need for this specific industry expertise would be on-going, and where this approach was likely to contribute to timely completion of the effort. The project also facilitated dialog between codes and standards development organizations, hydrogen and fuel cell experts, the government and national labs, researchers, code officials, industry associations, as well as the public regarding the timeframes for needed codes and standards, industry consensus on technical issues, procedures for implementing changes, and general principles of hydrogen safety. The project facilitated hands-on learning, as participants in several NHA workshops and technical meetings were able to experience hydrogen vehicles, witness hydrogen refueling demonstrations, see metal hydride storage cartridges in operation, and view other hydrogen energy products.

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

Technical specifications for the provision of heat and steam sources for INPP and Visaginas. Final report

International Nuclear Information System (INIS)

2003-01-01

In October 1999, the National Energy Strategy was approved by the Lithuanian Parliament. The National Energy Strategy included the decision to close Unit-1 of INPP before 2005. Later is has been decided to close Unit 2 before the end of 2009 as well. The closure and decommissioning will have heavy impact on the heat supply for the city of Visaginas. Unit 1 and Unit 2 of INPP supplies hot water and steam to INPP for process purposes and for space heating of residential and commercial buildings. When Unit 1 is permanently shut down, reliable heat and steam sources independent of the power plants own heat and steam generation facilities are required for safety reasons in the event of shutdown of the remaining unit for maintenance or in an emergency. These steam and heat sources must be operational before single unit operation is envisaged. Provision of a reliable independent heat and steam source is therefore urgent. After both reactors are shut down permanently, a steam source will be needed at the plant for radioactive waste storage and disposal. INPP and DEA has performed a feasibility study for the provision of a reliable heat source for Ignalina Nuclear Power Plant and Visaginas, and the modernisation of Visaginas district heating system. The objective of this project is to prepare technical specifications for the provision of new heat and steam sources for INPP and Visaginas, and for rehabilitation of the heat transmission pipeline between INPP, the back-up boiler station and Visaginas City. The results of the study are presented in detail in the reports and technical specifications: 1. Transient analysis for Visaginas DH system, 2. Non-destructive testing of boiler stations, pump stations and transmission lines, 3. Conceptual design, 4. Technical specifications, Package 1 to 6. The study has suggested: 1. Construction of new steam boiler station, 2. Construction of new heat only boiler station, 3. Renovation of existing back-up heat only boiler station, 4

Risk-based technical specifications: Development and application of an approach to the generation of a plant specific real-time risk model

International Nuclear Information System (INIS)

Puglia, B.; Gallagher, D.; Amico, P.; Atefi, B.

1992-10-01

This report describes a process developed to convert an existing PRA into a model amenable to real time, risk-based technical specification calculations. In earlier studies (culminating in NUREG/CR-5742), several risk-based approaches to technical specification were evaluated. A real-time approach using a plant specific PRA capable of modeling plant configurations as they change was identified as the most comprehensive approach to control plant risk. A master fault tree logic model representative of-all of the core damage sequences was developed. Portions of the system fault trees were modularized and supercomponents comprised of component failures with similar effects were developed to reduce the size of the model and, quantification times. Modifications to the master fault tree logic were made to properly model the effect of maintenance and recovery actions. Fault trees representing several actuation systems not modeled in detail in the existing PRA were added to the master fault tree logic. This process was applied to the Surry NUREG-1150 Level 1 PRA. The master logic mode was confirmed. The model was then used to evaluate frequency associated with several plant configurations using the IRRAS code. For all cases analyzed computational time was less than three minutes. This document Volume 2, contains appendices A, B, and C. These provide, respectively: Surry Technical Specifications Model Database, Surry Technical Specifications Model, and a list of supercomponents used in the Surry Technical Specifications Model

Technical support document for land application of sewage sludge. Volume 1. Final report

International Nuclear Information System (INIS)

Jones, A.; Beyer, L.; Rookwood, M.; Pacenka, J.; Bergin, J.

1992-11-01

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the land application of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in land applied sewage sludge. The management practices associated with land application are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through land application are discussed

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.

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.

Sensor guided control and navigation with intelligent machines. Final technical report

Energy Technology Data Exchange (ETDEWEB)

Ghosh, Bijoy K.

2001-03-26

This item constitutes the final report on ''Visionics: An integrated approach to analysis and design of intelligent machines.'' The report discusses dynamical systems approach to problems in robust control of possibly time-varying linear systems, problems in vision and visually guided control, and, finally, applications of these control techniques to intelligent navigation with a mobile platform. Robust design of a controller for a time-varying system essentially deals with the problem of synthesizing a controller that can adapt to sudden changes in the parameters of the plant and can maintain stability. The approach presented is to design a compensator that simultaneously stabilizes each and every possible mode of the plant as the parameters undergo sudden and unexpected changes. Such changes can in fact be detected by a visual sensor and, hence, visually guided control problems are studied as a natural consequence. The problem here is to detect parameters of the plant and maintain st ability in the closed loop using a ccd camera as a sensor. The main result discussed in the report is the role of perspective systems theory that was developed in order to analyze such a detection and control problem. The robust control algorithms and the visually guided control algorithms are applied in the context of a PUMA 560 robot arm control where the goal is to visually locate a moving part on a mobile turntable. Such problems are of paramount importance in manufacturing with a certain lack of structure. Sensor guided control problems are extended to problems in robot navigation using a NOMADIC mobile platform with a ccd and a laser range finder as sensors. The localization and map building problems are studied with the objective of navigation in an unstructured terrain.

Technical and economical feasibility studies and preliminary plan of a heavy water plant by the criogenic distillation method of hydrogen

International Nuclear Information System (INIS)

Dias Vargas, F.

1983-01-01

This paper presents the pre-feasibility study of a heavy water production plant, both from the technical and economical point of view. Criogenic distillation of hydrogen is used as the final enrichment stage. The deuterium source is water treated previously by a process of enrichment based on the water-hydrogen isotopic exchange. The economical analysis is aimed at the study of the feasibility of the installation of a heavy water moderated reaction in Chile. General properties of heavy water are presented and also the various materials of its enrichment at the industrial scale. The plant itself has a first stage based on the water-hydrogen isotopic exchange procesS, where deuterium is extracted from the water by the hydrogen which is subsequently treated in a criogenic distillation stage. An important fact of the plant analysis is the calculation of heat exchangers mainly in relation to the problem posed by tHe hydrogen's low point of liquifaction. The distillation units are also treated and designed. The economic evaluation produces project diScount rates of 15.71% and 21.97%, for 25 tons/year and 40 tons/year of production capacity. The heavy water price used for these evaluation was 600 $/Kg

Capital and operating costs of irradiated natural uranium reprocessing plants

International Nuclear Information System (INIS)

Thiriet, L.; Jouannaud, C.; Couture, J.; Duboz, J.

1966-01-01

This paper presents first a method of analysing natural uranium reprocessing plants investment costs (method similar to LANG and BACH well known in the fuel oil industry) and their operating costs (analysed according to their economic type). This method helps establishing standard cost structures for these plants, allowing thus comparisons between existing or planned industrial facilities. It also helps evaluating the foreseeable consequences of technical progress. Some results obtained are given, concerning: the investment costs sensitivity to the various technical parameters defining the fuel and their comparison according to the country or the economic area taken into account. Finally, the influence of the plants size on their investment costs is shown. (author) [fr

Electricite de France Strategy for its nuclear power plants' decommissioning programme

International Nuclear Information System (INIS)

Knockaert, J.M.; Gatineau, J.P.

1992-01-01

Although final shutdown of the first large PWR Power Stations should not occur before 2015, Electricity of France is nevertheless directly concerned by the decommissioning of its nuclear plants. The shutdown programme of the gas-graphite units is in progress and the medium-power PWR plant (300 MWe) installed at Chooz in the Ardennes will be finally shutdown at the end of 1991. This solution requires EDF to have a policy available which enables it to simultaneously run the double operation 'Plant shutdown-decommissioning' and 'New constructions-increasing available power' from both the technical and financial viewpoints. (author)

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)

Periodic safety reviews of nuclear power plants

International Nuclear Information System (INIS)

Toth, Csilla

2009-01-01

Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

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

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

Technical guidance for siting criteria development

International Nuclear Information System (INIS)

Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.

1982-12-01

Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness

Technical guidance for siting criteria development

Energy Technology Data Exchange (ETDEWEB)

Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

1982-12-01

Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

Intelligent distributed control for nuclear power plants

International Nuclear Information System (INIS)

Klevans, E.H.

1992-01-01

This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Third Annual Technical Progress report summarizes the period from September 1991 to October 1992. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. His philosophy, is to improve public perception of the safety of nuclear power plants by incorporating a high degree of automation where a greatly simplified operator control console minimizes the possibility of human error in power plant operations. To achieve this goal, a hierarchically distributed control system with automated responses to plant upset conditions was pursued in this research. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 stem plant. Emphasized in this Third Annual Technical Progress Report is the continuing development of the in-plant intelligent control demonstration for the final project milestone and includes: simulation validation and the initial approach to experiment formulation

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

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.

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.

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

Final Technical Progress Report: Development of Low-Cost Suspension Heliostat; December 7, 2011 - December 6, 2012

Energy Technology Data Exchange (ETDEWEB)

Bender, W.

2013-01-01

Final technical progress report of SunShot Incubator Solaflect Energy. The project succeeded in demonstrating that the Solaflect Suspension Heliostat design is viable for large-scale CSP installations. Canting accuracy is acceptable and is continually improving as Solaflect improves its understanding of this design. Cost reduction initiatives were successful, and there are still many opportunities for further development and further cost reduction.

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

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

Integrated plant safety assessment. Systematic evaluation program, Big Rock Point Plant (Docket No. 50-155). Final report

International Nuclear Information System (INIS)

1984-05-01

The Systematic Evaluation Program was initiated in February 1977 by the U.S. Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final Integrated Plant Safety Assessment Report has been issued. This report documents the review of the Big Rock Point Plant, which is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. It also addresses a majority of the pending licensing actions for Big Rock Point, which include TMI Action Plan requirements and implementation criteria for resolved generic issues. Equipment and procedural changes have been identified as a result of the review

Construction times and the decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Erramuspe, H.J.

1988-01-01

The construction and the decommissioning periods of nuclear power plants (NPP), are studied, due to their importance in the generation costs. With reference to the construction periods of these plants, a review is made of the situation and technical improvements made in different countries, with the purpose of shortening them. In regard to the decommissioning of NPP, the present and future situations are reviewed in connection with different stages of decommissioning and their related problems, as the residual radioactivity of different components, and the size of the final wastes to be disposed of. The possibilities of plant life extensions are also revised in connection with these problems. Finally, the expected decommissioning costs are analyzed. (Author) [es

NEET-AMM Final Technical Report on Laser Direct Manufacturing (LDM) for Nuclear Power Components

International Nuclear Information System (INIS)

Anderson, Scott; Baca, Georgina; O'Connor, Michael

2015-01-01

Final technical report summarizes the program progress and technical accomplishments of the Laser Direct Manufacturing (LDM) for Nuclear Power Components project. A series of experiments varying build process parameters (scan speed and laser power) were conducted at the outset to establish the optimal build conditions for each of the alloys. Fabrication was completed in collaboration with Quad City Manufacturing Laboratory (QCML). The density of all sample specimens was measured and compared to literature values. Optimal build process conditions giving fabricated part densities close to literature values were chosen for making mechanical test coupons. Test coupons whose principal axis is on the x-y plane (perpendicular to build direction) and on the z plane (parallel to build direction) were built and tested as part of the experimental build matrix to understand the impact of the anisotropic nature of the process.. Investigations are described 316L SS, Inconel 600, 718 and 800 and oxide dispersion strengthed 316L SS (Yttria) alloys.

NEET-AMM Final Technical Report on Laser Direct Manufacturing (LDM) for Nuclear Power Components

Energy Technology Data Exchange (ETDEWEB)

Anderson, Scott [Lockheed Martin Corporation, Denver, CO (United States). Space Systems Company; Baca, Georgina [Lockheed Martin Corporation, Denver, CO (United States). Space Systems Company; O' Connor, Michael [Lockheed Martin Corporation, Denver, CO (United States). Space Systems Company

2015-12-31

Final technical report summarizes the program progress and technical accomplishments of the Laser Direct Manufacturing (LDM) for Nuclear Power Components project. A series of experiments varying build process parameters (scan speed and laser power) were conducted at the outset to establish the optimal build conditions for each of the alloys. Fabrication was completed in collaboration with Quad City Manufacturing Laboratory (QCML). The density of all sample specimens was measured and compared to literature values. Optimal build process conditions giving fabricated part densities close to literature values were chosen for making mechanical test coupons. Test coupons whose principal axis is on the x-y plane (perpendicular to build direction) and on the z plane (parallel to build direction) were built and tested as part of the experimental build matrix to understand the impact of the anisotropic nature of the process.. Investigations are described 316L SS, Inconel 600, 718 and 800 and oxide dispersion strengthed 316L SS (Yttria) alloys.

Critical evaluation of the nonradiological environmental technical specifications. Volume 2. Surry Power Plants, Units 1 and 2

International Nuclear Information System (INIS)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

1976-01-01

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 1 and 2 of the Surry Nuclear Power Plant was carried out for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected from 1973 through 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The two primary methods used for temperature monitoring employ a fixed thermographs network and boat measurements. Review of data indicates that both the application and formulation of the hydrothermal monitoring program are inadequate to fully characterize the operation of the plant and the behavior of the thermal plume. Furthermore, there are no existing data that can be used to adequately verify or disprove the validity of the various Surry plume predictions. The ecological analysis includes validation of impacts predicted in the Final Environmental Statement using the operational monitoring data. Phytoplankton cell concentrations, chlorophyll a, and carbon-14 measurements were used to monitor changes in the primary producers. Densities of consumers (i.e., zooplankton, benthos, and fish) were sed to monitor changes in the primary producers. Models based on operating data were constructed to determine whether changes were occurring at each trophic level. Analysis of the monitoring data suggests that the thermal discharges at Surry are having a negative effect on the phytoplankton and zooplankton but are enhancing the benthic and nekton populations in the discharge area

Project study for the final disposal of intermediate toxicity radioactive wastes (low- and intermediate-level radioactive wastes) in geological formations

International Nuclear Information System (INIS)

1980-08-01

The present report aimed to show variations in the construction- and operation-technical feasibility of a final repository for low- and intermediate-level radioactive wastes. This report represents the summary of a project study given under contract by Nagra with a view to informing a broader public of the technical conception of a final repository. Particular stress was laid on the treatment of the individual system elements of a repository concept during the construction, operation and sealing phases. The essential basis for the project study is the origin, composition and quantity of the wastes to be disposed. The final repository described in this report is foreseen for the reception of the following low- and intermediate-level solid radioactive wastes: wastes from the nuclear power plant operation; secondary wastes from the reprocessing of nuclear fuels; wastes from the decommissioning of nuclear power plants; wastes from research, medicine and industry

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)

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

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

Technical basis for the ITER final design report, cost review and safety analysis (FDR)

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement. Refs, figs, tabs

Technical basis for the ITER final design report, cost review and safety analysis (FDR)

International Nuclear Information System (INIS)

1998-01-01

The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement

Technical review of externalities issues. Final report

International Nuclear Information System (INIS)

Niemeyer, V.

1994-12-01

Externalities has become the catchword for a major experiment in electric utility regulation. Together with increased competition as a means for economic regulation, this experiment represents a potential revolution in how electric utilities are regulated. It is very important for utilities and policy makers to understand the technical issues and arguments driving the externality experiment. This Technical Review presents four papers covering topics in economics that may play important roles in this revolution. The four papers are: Economic Issues in the Application of Externalities to Electricity Resource Selection; Climate Change, the Marginal Cost of Carbon Dioxide Emissions and the Implications for Carbon Dioxide Emissions Adders; Positive Externalities and Benefits from Electricity; and Socioeconomic Effects of Externality Adders for Electric Utility Emissions

Impact of different national biomass policies on investment costs of biomass district heating plants. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-04-01

The BIO-COST project - co-ordinated by E.V.A. - was funded by the European Commission's THERMIE Type B Programme. The objective of BIO-COST was to analyse the impact of national biomass policies on the investment costs of biomass district heating (DH) plants. The European comparison should help identifying measures to reduce investment costs for biomass DH plants and/or components down to a 'best practice' level. The investigation is based on the comparison of 20 biomass DH plants by country, with Denmark and Sweden having mainly high energy taxes as driver, while Austria and France rely mainly on subsidy systems. The results of BIO-COST show, that governmental policies can have a big impact especially on grid and buildings costs, effecting of course the overall costs of the plant enormously. Emission standards have their effects especially on the costs for technical equipment, however, this fact was not reflected in the BIO-COST data. The results do not show a clear advantage of either the energy tax approach or the subsidy approach: The French subsidy approach leads to fairly low cost levels compared to the Danish tax approach, while the Swedish tax approach seems to yield the lowest cost level. On the other hand the Austrian subsidy approach seems to intercrease investment costs. In principle both the tax as the subsidy approach can lead to the same effect: a project is calculated in such a way, that it just meets economic breakeven. This is typically the case when the project is not carried out by a private enterprise but by an operator aiming at enhanced public welfare (e.g. co-operative, municipality). In this case a subsidy model might yield more possibilities to encourage an economically efficient development, than a tax. Instead of giving subsidies as a fixed percentage of investments they could be adjusted to the actual needs of the project as proven by a standardised calculation. Of course this can create the incentive to expect higher

Risk management through dynamic technical specifications

International Nuclear Information System (INIS)

Klopp, George T.; Petersen, Thomas A.

2004-01-01

The wide deployment of plant specific probabilistic risk assessments for nuclear power plants has provided the means to effect a fresh risk management perspective and a fresh, risk based, regulatory outlook on nuclear power. There has been a great deal of conversation on risk based regulation within the U. S. nuclear power industry but, curiously, very little on effective risk management. This paper proposes a means to link the two subjects through the plant Technical Specifications. A revised concept for Technical Specifications is suggested which is based on deterministic analyses and probabilistic risk assessments for each plant. The revised Technical Specifications would consider, on a real-time basis, the exact state of the plant in terms of the status of key components and systems. It would depict current plant risk levels and compare those levels to the desired and limiting (alert/action) levels. It would advise the plant operator on the risk impact of proposed actions through a simple query system and illustrate the impact of such actions on plant status relative to designated risk values. The basis for the proposed approach lies in realistic deterministic plant analyses and probabilistic risk assessment (PRA) deployment tools being developed, in parallel, by a number of parties in the U.S. today. These PRAs are based primarily on the existing plant responses to Generic Letter 88-20, 'Individual Plant Examinations' (IPEs). Each of these tools allows the plant operator to input, on a real-time basis, the status of key equipment and systems. The tools then provide explicit illustrations of dependency effects; updated, 'real-time' risk status indications such as core damage frequency; and, in some cases, allow the operator to assess the risk impact of removing from service selected components for maintenance or testing. These systems generally operate on personal computers and provide nearly instantaneous responses to plant queries. Moving from these tools to

Trojan technical specification verification project

International Nuclear Information System (INIS)

Bates, L.; Rickenback, M.

1991-01-01

The Trojan Technical Specification Verification (TTSV) project at the Trojan plant of Portland General Electric Company was motivated by the recognition that many numbers in the Trojan technical specifications (TTS) potentially lacked the consideration of instrument- and/or process-related errors. The plant setpoints were known to consider such errors, but many of the values associated with the limiting conditions for operation (LCO) did not. In addition, the existing plant instrument error analyses were based on industry values that do not reflect the Trojan plant-specific experience. The purpose of this project is to ensure that the Trojan plant setpoint and LCO values include plant-specific instrument error

Evaluation of effects of phenol recovery on biooxidation and tertiary treatment of SRC-I wastewater. Final technical report

Energy Technology Data Exchange (ETDEWEB)

Mitchell, J.W.; Watt, J.C.; Cowan, W.F.; Schuyler, S.E.

1983-09-01

Addition of phenol recovery to the wastewater treatment scheme in the Baseline Design for the SRC-I Demonstration Plant was evaluated as a major post-Baseline effort. Phenol recovery affects many downstream processes, but this study was designed to assess primarily its effects on biooxidation and subsequent tertiary treatment. Two parallel treatment schemes were set up, one to treat dephenolated wastewaters and the other for processed nondephenolated wastewaters, a simulation of the Baseline Design. The study focused on comparisons of five areas: effluent quality; system stability; the need for continuous, high-dose powdered activated carbon (PAC) augmentation to the bioreactor; minimum bioreactor hydraulic residence time (HRT); and tertiary treatment requirements. The results show that phenol recovery improves the quality of the bioreactor effluent in terms of residual organics and color. With phenol recovery, PAC augmentation is not required; without phenol recovery, PAC is needed to produce a comparable effluent. Dephenolization also enhances the stability of biooxidation, and reduces the minimum HRT required. With tertiary treatment, both schemes can meet the effluent concentrations published in the SRC-I Final Envivornmental Impact Statement, as well as the anticipated effluent limits. However, phenol recovery does provide a wider safety margin and could eliminate the need for some of the tertiary treatment steps. Based solely on the technical merits observed in this study, phenol recovery is recommended. The final selection should, however, also consider economic tradeoffs and results of other studies such as toxicology testing of the effluents. 34 references, 30 figures and 26 tables.

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

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.

Technical study gas storage. Final report

International Nuclear Information System (INIS)

Borowka, J.; Moeller, A.; Zander, W.; Koischwitz, M.A.

2001-01-01

This study will answer the following questions: (a) For what uses was the storage facility designed and for what use is it currently applied? Provide an overview of the technical data per gas storage facility: for instance, what is its capacity, volume, start-up time, etc.; (b) How often has this facility been used during the past 10 years? With what purpose was the facility brought into operation at the time? How much gas was supplied at the time from the storage facility?; (c) Given the characteristics and the use of the storage facility during the past 10 years and projected gas consumption in the future, how will the storage facility be used in the future?; (d) Are there other uses for which the gas storage facility can be deployed, or can a single facility be deployed for numerous uses? What are the technical possibilities in such cases? Questions (a) and (b) are answered separately for every storage facility. Questions (c) and (d) in a single chapter each (Chapter 2 and 3). An overview of the relevant storage data relating to current use, use in the last 10 years and use in future is given in the Annex

Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 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 both EG and G and 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 was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab

Plant for retention of 14C in reprocessing plants for LWR fuel elements

International Nuclear Information System (INIS)

Braun, H.; Gutowski, H.; Bonka, H.; Gruendler, D.

1983-01-01

The 14 C produced from nuclear power plants is actually totally emitted from nuclear power plants and reprocessing plants. Using the radiation protection principles proposed in ICRP 26, 14 C should be retained at heavy water moderated reactors and reprocessing plants due to a cost-benefit analysis. In the frame of a research work to cost-benefit analysis, which was sponsored by the Federal Minister of the Interior, an industrial plant for 14 C retention at reprocessing plants for LWR fuel elements has been planned according to the double alkali process. The double alkali process has been chosen because of the sufficient operation experience in the conventional chemical technique. In order to verify some operational parameters and to gain experiences, a cold test plant was constructed. The experiment results showed that the double alkali process is a technically suitable method with high operation security. Solidifying CaCO 3 with cement gives a product fit for final disposal

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

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

Environmental assessment for final rule on nuclear power plant license renewal

International Nuclear Information System (INIS)

1991-12-01

The Atomic Energy Act and Nuclear Regulatory Commission (NRC) regulations provide for the renewal of nuclear power plant operating licenses beyond their initial 40-year term. The Act and NRC regulations, however, do not specify the procedures, criteria, and standards that must be satisfied in order to renew a license. The NRC is promulgating a rule (10 CFR Part 54) to codify such requirements prior to the receipt of applications for license renewal. The NRC has assessed the possible environmental effects of promulgating requirements in 10 CFR Part 54 now rather than employing such requirements in an ad hoc manner in individual licensing actions. The final part 54 rule requires the development of information and analyses to identify aging problems of systems, structures, and components unique to license renewal that will be of concern during the period of extended operation and will not be controlled by existing effective programs. In general, licensee activities for license renewal may involve replacement, refurbishment, inspection, testing, or monitoring. Such actions will be generally be within the range of similar actions taken for plants during the initial operating term. These actions would be primarily confined within the plants with potential for only minor disruption to the environment. It is unlikely that these actions would change the operating conditions of plants in ways that would change the environmental effects already being experienced. Relicensing under existing regulations would also be primarily focused on aging degradation and would likely result in requirements similar to those that will result from relicensing under the final rule

78 FR 29239 - Final Priority; Technical Assistance To Improve State Data Capacity-National Technical Assistance...

Science.gov (United States)

2013-05-20

... Assistance To Improve State Data Capacity--National Technical Assistance Center To Improve State Capacity To... Education and Rehabilitative Services announces a priority under the Technical Assistance to Improve State... (FY) 2013 and later years. We take this action to focus attention on an identified national need to...

Feasibility study of a Green Power Plant. Final report. [Offshore pumped hydro storage

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-03-15

This project is a technical evaluation and a feasibility study of a concept called the Green Power Plant (GPP), developed by Seahorn Energy Aps. The Green Power Plant is an offshore pumped hydro storage facility constructed from prefabricated elements and with integrated renewable energy production. Pumped hydro storage is a known technology with a proven roundtrip energy storage efficiency of 80%. The focus of the GPP project is on simplifying and industrializing the construction of the reservoir wall, thereby achieving a cost efficient solution. The reservoir structure is dependent on the site on which the reservoir is established, thus Kriegers Flak in the Baltic Sea has been chosen as basis for the technical evaluation. As soil conditions vary, the technical evaluations have been based on a general soil profile. A water depth of 25m has been chosen as basis for the evaluation. A reservoir with a diameter of 2 km has been evaluated as baseline scenario. Feasibility of the GPP was evaluated based on the cost and income estimates. For the baseline scenario an internal rate of return of 6.6% was found for a period of 35 years. A sensitivity analysis reveals internal rates of return over 35 years varying from 4.9% to 10.9%. Especially larger reservoir diameters increase profitability of the GPP. The results from this project will be utilized in raising funds for further development of the GPP concept. Seahorn Energy Aps aims at optimizing the wind turbine integration, the steel pile wall structure and the pump-turbine integration in a future project towards construction of a demonstration facility. (LN)

Assessment of social values in thermal plant siting

International Nuclear Information System (INIS)

Anon.

1976-01-01

The objective of the project is to develop a method for combining social values with techno-economic data for better decision making in thermal nuclear power plant siting. Quantified technical impact data which is socially weighted will allow for the optimal choice of site/design alternatives. In this phase, a study of community leadership in energy/environment issues was conducted in a town familiar with a (nuclear) thermal power plant. Secondly, a linear composite analysis of the measurement problems associated with combining diverse scales of impacts was completed. Third, a revision of the social values instrument used in a previous phase of the study was initiated. Finally, liaison activities with utilities were undertaken. Quantification of three of the technical impact factors is currently underway

Ageing management technical information investigations

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

In February 2013, there are 50 units of commercial nuclear power plants (NPPs) in Japan. We enter into a period that 20 units of them are operating for more than 30 years. Currently, regulation imposes utilities to conduct ageing technical evaluations of each unit before operation of 30 years from the commissioning, to develop the long term maintenance management policy for next 10 years and to submit to the regulatory authority the policy with the report on ageing management technical evaluation (AMTE) for each NPP. It is necessary for regulatory side to develop technical information bases incorporating latest technical knowledge as operating experiences in domestic and abroad on ageing of the plants necessary to conduct reviews of AMTE for each unit. Based on these standpoints, technical information bases investigations have been conducted from the viewpoints of material degradation of ageing NPPs. In order to develop scientific regulator judgment bases related to ageing management (AM) and long-term operation (LTO), investigations on latest information on ageing management in domestic and abroad are conducted and a set of documents including technical evaluation review manuals necessary to conduct AMTE are prepared. To utilize the results of the investigations for ageing technical evaluation, database including latest information related to AM and LTO are developed, ran and operated. In addition, investigations related to Fugen nuclear plant, under decommissioning plants, investigations on mechanism of stress corrosion cracking (SCC), thermal ageing and preventive technologies for SCC, detection and diagnosis technology for ageing degradation and condition monitoring technology are performed to validate and confirm effectiveness of the technologies. (author)

Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

Brown, R. C.; McCarley, T. M.

2006-05-04

The overall goal of this project was to establish an education and training program in biobased products at Iowa State University (ISU). In particular, a graduate program in Biorenewable Resources and Technology (BRT) was to be established as a way of offering students advanced study in the use of plant- and crop-based resources in the production of biobased products. The program was to include three fundamental elements: an academic program, a research program, and industrial interactions. The academic program set out to introduce a new graduate major in Biorenewable Resources and Technology. Unlike other schools, which only offer certificates or areas of emphasis in biobased products, Iowa State University offers both M.S. and Ph.D degrees through its graduate program. Core required courses in Biorenewable Resources and Technology include a foundation course entitled Fundamentals of Biorenewable Resources (BRT 501); a seminar course entitled Biobased Products Seminar (BRT 506); a laboratory course, and a special topics laboratory course. The foundation course is a three-credit course introducing students to basic concepts in biorenewable resources and technology. The seminar course provides students with an opportunity to hear from nationally and internationally recognized leaders in the field. The laboratory requirement is a 1-credit laboratory course or a special topics laboratory/research experience (BRT 591L). As part of student recruitment, quarter-time assistantships from DOE funds were offered to supplement assistantships provided by faculty to students. Research was built around platform teams in an effort to encourage interdisciplinary research and collaborative student learning in biorenewable resources. A platform is defined as the convergence of enabling technologies into a highly integrated system for transforming a specific feedstock into desired products. The platform teams parallel the way industry conducts research and product development

Regulatory analysis for final rule on nuclear power plant license renewal

International Nuclear Information System (INIS)

1991-12-01

This regulatory analysis provides the supporting information for the final rule (10 CFR Part 54) that defines the Nuclear Regulatory Commission's requirements for renewing the operating licenses of commercial nuclear power plants. A set of four specific alternatives for the safety review of license renewal applications is defined and evaluated. These are: Alternative A-current licensing basis; Alternative B-extension of Alternative A to require assessment and managing of aging; Alternative C -- extension of Alternative B to require assessment of design differences against selected new-plant standards using probabilistic risk assessment; and Alternative D -- extension of Alternative B to require compliance with all new-plant standards. A quantitative comparison of the four alternatives in terms of impact-to-value ratio is presented, and Alternative B is the most cost-beneficial safety review alternative

Final waste classification and waste form technical position papers

International Nuclear Information System (INIS)

1983-05-01

The waste classification technical position paper describes overall procedures acceptable to NRC staff which may be used by licensees to determine the presence and concentrations of the radionuclides listed in section 61.55, and thereby classifying waste for near-surface disposal. This technical position paper also provides guidance on the types of information which should be included in shipment manifests accompanying waste shipments to near-surface disposal facilities. The technical position paper on waste form provides guidance to waste generators on test methods and results acceptable to NRC staff for implementing the 10 CFR Part 61 waste form requirements. It can be used as an acceptable approach for demonstrating compliance with the 10 CFR Part 61 waste structural stability criteria. This technical position paper includes guidance on processing waste into an acceptable stable form, designing acceptable high-integrity containers, packaging cartridge filters, and minimizing radiation effects on organic ion-exchange resins. The guidance in the waste form technical position paper may be used by licensees as the basis for qualifying process control programs to meet the waste form stability requirements, including tests which can be used to demonstrate resistance to degradation arising from the effects of compression, moisture, microbial activity, radiation, and chemical changes. Generic test data (e.g., topical reports prepared by vendors who market solidification technology) may be used for process control program qualification where such generic data is applicable to the particular types of waste generated by a licensee

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

Energy Technology Data Exchange (ETDEWEB)

DiNunzio, Camillo A. [Framatome ANP DE& S, Marlborough, MA (United States); Gupta, Abhinav [Univ. of North Carolina, Raleigh, NC (United States); Golay, Michael [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Luk, Vincent [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Turk, Rich [Westinghouse Electric Company Nuclear Systems, Windsor, CT (United States); Morrow, Charles [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jin, Geum-Taek [Korea Power Engineering Company Inc., Yongin-si, Gyeonggi-do (Korea, Republic of)

2002-11-30

This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

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

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

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

Harmonization of the licensing process for digital instrumentation and control systems in nuclear power plants. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Instrumentation

International Nuclear Information System (INIS)

2002-12-01

This report was prepared in response to the recommendation of the Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI). This recommendation was based on the recognition of the present diversity in national practices in licensing digital Instrumentation and control (I and C). The goal of this report is to promote harmonization of I and C licensing requirements in the Member States. It applies to I and C modernization, retrofits, upgrades, replacement, new installation, and other aspects of digital I and C in both existing and new nuclear power plants. It should be pointed out that a single publication, like this report, can only take the first step towards initiating a process leading to licensing requirements, which are more harmonized. It is therefore hoped that that this report will get a broad readership among those who can influence requirements that are set on digital I and C. This report provides general and high level recommendations to assist senior officials at utilities, vendor organizations, regulatory bodies, and their support organizations who are involved in the licensing of digital I and C. It is also intended to be read by persons participating in technical committees which are writing standards. The authors of this report believe that harmonization can be achieved through a consideration of the technical and scientific basis of high integrity digital I and C systems. It is also believed that many benefits can be reached in resolving various issues of a technical and engineering nature, which presently are creating controversies in the licensing of digital I and C in NPP safety applications. This publication is based on a consideration of the licensing process of I and C in a top down fashion to discuss generic principles to be applied when assessing digital I and C in NPP safety applications. This report gives an overview of the confidence building process in which evidence is created that digital I and C fulfils

Technical basis for instrumentation and control design improvements in WWER-440/230 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-01-01

Instrumentation and control (I and C) has been recognized as an area which requires substantial improvements in WWER NNPs, particularly for model 230 plants. Under contract with the IAEA the Spanish company Empresarios Agrupados (EA) developed a basic document proposing a technical basis for improvements related to the following most significant aspects of I and C: criteria for safety classification; remote shutdown panel; I and C support to operation and control room design; instrumentation set point margins; accident monitoring instrumentation. This publication is derived from the original report of EA which was circulated by the IAEA for review by staff members and experts from various Member States. It was finally agreed upon at a Consultants' meeting convened by the IAEA in Vienna in May 1994 with the participation of experts from France, Germany and Spain. The guidance expressed in this report is based on the IAEA/NUSS standards, safety guides and practices, and on regulations in use in various Member States. It is proposed as a way of carrying out the necessary studies to improve safety by upgrading the vital part of instrumentation an control in WWER-440 model 230 nuclear power plants. 28 refs, 3 figs

The Limpopo Non-Metropolitan Drinking Water Supplier Response to a Diagnostic Tool for Technical Compliance.

Science.gov (United States)

Nefale, Avhashoni D; Kamika, Ilunga; Obi, Chikwelu L; Momba, Maggy Nb

2017-07-19

Water services providers should supply water that is fit for human consumption, taking into account multi-barrier approaches and technical aspects such as design aspects, operation monitoring, final water quality compliance monitoring, plant monitoring practices, maintenance, and risk management practices. Against this background, this study focused on applying the diagnostic tool for technical compliance as well as assessing the compliance of water treatment plants with management norms. Six plants in the Vhembe District Municipality were selected; the Vondo, Malamulele, Mutshedzi, and Mutale plants (conventional), and the Dzingahe and Tshedza package plants. During the first assessment, four (Malamulele, Mutshedzi, Mutale and Dzingahe) plants scored between 44% and 49% and achieved Class 3 certification, revealing serious challenges requiring immediate intervention. Two water plants (Vondo and Tshedza, scoring 53% and 63%, respectively) were in the Class 2 category, revealing serious challenges requiring attention and improvement. During the second assessment, all plants scored between 63% and 87% (Class 2 category). The greatest improvement (30%) was noted for the Dzingahe and Tshedza plants, followed by the Malamulele plant, while the Mutale, Vondo, and Mutshedzi plants improved their scores by 20%, 17% and 14%, respectively. After corrective actions and re-measurement, no plant complied. It is recommended that Water Services Providers (WSPs) regularly apply the diagnostic tools and water safety plans as developed in order to comply with applicable standards.

The Limpopo Non-Metropolitan Drinking Water Supplier Response to a Diagnostic Tool for Technical Compliance

Directory of Open Access Journals (Sweden)

Avhashoni D. Nefale

2017-07-01

Full Text Available Water services providers should supply water that is fit for human consumption, taking into account multi-barrier approaches and technical aspects such as design aspects, operation monitoring, final water quality compliance monitoring, plant monitoring practices, maintenance, and risk management practices. Against this background, this study focused on applying the diagnostic tool for technical compliance as well as assessing the compliance of water treatment plants with management norms. Six plants in the Vhembe District Municipality were selected; the Vondo, Malamulele, Mutshedzi, and Mutale plants (conventional, and the Dzingahe and Tshedza package plants. During the first assessment, four (Malamulele, Mutshedzi, Mutale and Dzingahe plants scored between 44% and 49% and achieved Class 3 certification, revealing serious challenges requiring immediate intervention. Two water plants (Vondo and Tshedza, scoring 53% and 63%, respectively were in the Class 2 category, revealing serious challenges requiring attention and improvement. During the second assessment, all plants scored between 63% and 87% (Class 2 category. The greatest improvement (30% was noted for the Dzingahe and Tshedza plants, followed by the Malamulele plant, while the Mutale, Vondo, and Mutshedzi plants improved their scores by 20%, 17% and 14%, respectively. After corrective actions and re-measurement, no plant complied. It is recommended that Water Services Providers (WSPs regularly apply the diagnostic tools and water safety plans as developed in order to comply with applicable standards.

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

OTEC Advanced Composite Cold Water Pipe: Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Dr. Alan Miller; Matthew Ascari

2011-09-12

Ocean Thermal Energy Conversion can exploit natural temperature gradients in the oceans to generate usable forms of energy (for example, cost-competitive baseload electricity in tropical regions such as Hawaii) free from fossil fuel consumption and global warming emissions.The No.1 acknowledged challenge of constructing an OTEC plant is the Cold Water Pipe (CWP), which draws cold water from 1000m depths up to the surface, to serve as the coolant for the OTEC Rankine cycle. For a commercial-scale plant, the CWP is on the order of 10m in diameter.This report describes work done by LMSSC developing the CWP for LM MS2 New Ventures emerging OTEC business. The work started in early 2008 deciding on the minimum-cost CWP architecture, materials, and fabrication process. In order to eliminate what in previous OTEC work had been a very large assembly/deployment risk, we took the innovative approach of building an integral CWP directly from theOTEC platform and down into the water. During the latter half of 2008, we proceeded to a successful small-scale Proof-of-Principles validation of the new fabrication process, at the Engineering Development Lab in Sunnyvale. During 2009-10, under the Cooperative Agreement with the US Dept. of Energy, we have now successfully validated key elements of the process and apparatus at a 4m diameter scale suitable for a future OTEC Pilot Plant. The validations include: (1) Assembly of sandwich core rings from pre-pultruded hollow 'planks,' holding final dimensions accurately; (2) Machine-based dispensing of overlapping strips of thick fiberglass fabric to form the lengthwise-continuous face sheets, holding accurate overlap dimensions; (3) Initial testing of the fabric architecture, showing that the overlap splices develop adequate mechanical strength (work done under a parallel US Naval Facilities Command program); and (4) Successful resin infusion/cure of 4m diameter workpieces, obtaining full wet-out and a non-discernable knitline

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

Energy Technology Data Exchange (ETDEWEB)

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M. [Sandia National Labs., Albuquerque, NM (United States); Beyeler, W. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S. [Hawaii Univ., Hilo, HI (United States); Rudeen, D. [New Mexico Engineering Research Inst., Albuquerque, NM (United States)

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis.

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

International Nuclear Information System (INIS)

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M.; Beyeler, W.; Hora, S.; Rudeen, D.

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis

Technical evaluation of the G.E. Transportable Modular AZTECH Plant topical report

International Nuclear Information System (INIS)

Henscheid, J.W.; Stalker, A.E.

1985-12-01

This report summarizes EG and G Idaho's review of the General Electric Company's topical report on their Transportable Modular AZTECH Plant. The review evaluated compliance with pertinent codes, standards and regulations. The initial review was discussed with G.E. and all outstanding issues resolved before this final evaluation was made

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

Management of aging in technical facilities of E.ON Kernkraft plants; Alterungsmanagement bei technischen Einrichtungen in Anlagen der E.ON Kernkraft GmbH

Energy Technology Data Exchange (ETDEWEB)

Reese, Sven H.; Brast, Gerhard [E.ON Kernkraft GmbH, Hannover (Germany); Schoeckle, Friedrich [AMTEC Messtechnischer Service GmbH, Lauffen/N (Germany)

2009-11-15

The publication explains, by means of specific measures, the management of aging in technical facilities as practiced in the plants of E.ON Kernkraft GmbH. First, the historical background is outlined and the reasons for introducing management of aging in order to limit and control factors influencing the lifetime of nuclear power plants are described. This is followed by a definition of management of aging in important safety-related facilities as against lifetime management of technical systems relevant to plant availability. This is the context in which the scope of the survey of continuous management of aging is defined in respect of physical aging. A classification is then made in accordance with the staggered requirements to be met in the quality of technical facilities. On the basis of the quality to be assured, the different component groups are assigned corresponding operational measures and explained. These continuous measures extend from failure-oriented maintenance to preventive maintenance to the integrity concept for technical installations. To document the findings and evaluate the effectiveness of the measures taken, the integration of the process is described and reference is made to continuous optimization according to PDCA principles. The explicit introduction of the process of management of aging creates a platform which allows a documentation to be accumulated of the manifold and comprehensive measures taken to control phenomena of aging in technical installations. (orig.)

Amino acid-sensing ion channels in plants

Energy Technology Data Exchange (ETDEWEB)

Spalding, Edgar P. [Univ. of Wisconsin, Madison, WI (United States)

2014-08-12

The title of our project is “Amino acid-sensing ion channels in plants”. Its goals are two-fold: to determine the molecular functions of glutamate receptor-like (GLR) proteins, and to elucidate their biological roles (physiological or developmental) in plants. Here is our final technical report. We were highly successful in two of the three aims, modestly successful in the third.

Alumina reinforced tetragonal zirconia (TZP) composites. Final technical report, July 1, 1993--December 31, 1996

International Nuclear Information System (INIS)

Shetty, D.K.

1997-01-01

This final technical report summarizes the significant research results obtained during the period July 1, 1993 through December 31, 1996 in the DOE-supported research project entitled, open-quotes Alumina Reinforced Tetragonal Zirconia (TZP) Compositesclose quotes. The objective of the research was to develop high-strength and high-toughness ceramic composites by combining mechanisms of platelet, whisker or fiber reinforcement with transformation toughening. The approach used included reinforcement of Celia- or yttria-partially-stabilized zirconia (Ce-TZP or Y-TZP) with particulates, platelets, or continuous filaments of alumina

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

International Nuclear Information System (INIS)

DiNunzio, Camillo A.; Gupta, Abhinav; Golay, Michael; Luk, Vincent; Turk, Rich; Morrow, Charles; Geum-Taek Jin

2002-01-01

OAK-B135 This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies

Underground siting of nuclear power plants

International Nuclear Information System (INIS)

Bender, F.

1982-01-01

The symposium gave the opportunity for an international exchange of views on the concepts of underground nuclear power plants, which are presently world wide under consideration. The results of investigations into the advantages and disadvantages with regard to the technical safety aspects of the underground plants in comparison to plants on the surface led to open and sometimes controversal discussions. As a result of the symposium (32 contributions) a general agreement can be stated on the judgement concerning the advantages and the disadvantages of underground nuclear power plants (nnp). The advantages are: increased protection against external events; delayed release of fission products in accident situations, if the closures operate properly. The disadvantages are: increased costs of the construction of underground and restrictions to such sites where either large caverns or deep pits can be constructed, which also requires that certain technical problems must be solved beforehand. Also, additional safety certificates related to the site will be required within the licensing procedures. The importance of these advantages and disadvantages was in some cases assessed very differently. The discussions also showed, that there are a number of topics where some questions have not been finally answered yet. (orig./HP) [de

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

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.)

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

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

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

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Velasco, Mayda [Northwestern University

2013-11-01

This work is focused on the design and construction of novel beam diagnostic and instrumentation for charged particle accelerators required for the next generation of linear colliders. Our main interest is in non-invasive techniques. The Northwestern group of Velasco has been a member of the CLIC Test Facility 3 (CTF3) collaboration since 2003, and the beam instrumentation work is developed mostly at this facility1. This 4 kW electron beam facility has a 25-170 MeV electron LINAC. CTF3 performed a set of dedicated measurements to finalize the development of our RF-Pickup bunch length detectors. The RF-pickup based on mixers was fully commissioned in 2009 and the RF-pickup based on diodes was finished in time for the 2010-11 data taking. The analysis of all the data taken in by the summer of 2010 was finish in time and presented at the main conference of the year, LINAC 2010 in Japan.

Technical, economic and environmental potential of co-firing of biomass in coal and natural gas fired power plants in the Netherlands

International Nuclear Information System (INIS)

Van Ree, R.; Korbee, R.; Eenkhoorn, S.; De Lange, T.; Groenendaal, B.

2000-01-01

In this paper the technical, economic, and environmental potential of co-firing of biomass in existing Dutch coal and natural gas fired power plants, and industrial combined-cycles (CC), is addressed. Main criteria that are considered are: the availability and contractibility of biomass for energy purposes; the (technical) operation of the conventional fossil fuel based processes may not be disturbed; the gaseous and liquid plant emissions have to comply to those applicable for power plants/CCs, the commercial applicability of the solid residues may not be negatively influenced; applicable additional biomass conversion technologies must be commercially available; the necessary additional investment costs must be acceptable from an economic point of view, and the co-firing option must result in a substantial CO 2 -emission reduction. The main result of the study described in the paper is the presentation of a clear and founded indication of the total co-firing potential of biomass in existing power plants and industrial CCs in the Netherlands. This potential is determined by considering both technical, economic, and environmental criteria. In spite of the fact that the co-firing potential for the specific Dutch situation is presented, the results of the criteria considered are more generally applicable, and therefore are also very interesting for potential co-firing initiatives outside of the Netherlands

Development of technics for separation and sorting system of different parts of field plants; Peltokasvien eri osien erottelu- ja lajittelutekniikoiden kehittaeminen

Energy Technology Data Exchange (ETDEWEB)

Lindh, T.; Kallio, E.; Taipale, R.; Leinonen, A.

1996-12-31

The aim of the research is to construct a segregation concept for an integrated method, by which it is possible to produce fiber fraction for pulping industry and byproduct fraction for energy production of the field plants to be processed. The starting point of the concept development was, that the method consists of the plant material processing phase, in which different plant components are segregated from each other, and a sorting phase in which the plant components are divided into different fractions on the basis of the use. Following topics were studied in the first year of this two year research: properties of spring-harvested reed canary grass and the component of it from the point of view of segregation, mechanical dry-processing methods for segregation of plant components from each other and sorting methods, by which the pulp fraction and by-product fraction are separated from each other. Chopping, crushing and milling have been studied as alternatives for processing. The particle size distribution of the produced material has been estimated. Sorting tests, based on air classification, have been made. Property analyses, such as ash content, have been made for different particle classes, by which the most suitable particle size class for sorting was determined. Processing and sorting research of chopped reed canary grass will be continued in 1996. Technical/economical analyses will be made of the costs of the separator by taking the alternatives, in which the separator unit operates at the farm or at the mill, into account. The final separation concept will be made using the results obtained in the experimental researches and cost analyses

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

State child health; revisions to the regulations implementing the State Children's Health Insurance Program. Interim final rule with comment period; revisions, delay of effective date, and technical amendments to final rule.

Science.gov (United States)

2001-06-25

Title XXI authorizes the State Children's Health Insurance Program (SCHIP) to assist State efforts to initiate and expand the provision of child health assistance to uninsured, low-income children. On January 11, 2001 we published a final rule in the Federal Register to implement SCHIP that has not gone into effect. This interim final rule further delays the effective date, revises certain provisions and solicits public comment, and makes technical corrections and clarifications to the January 2001 final rule based on further review of the comments received and applicable law. Only the provisions set forth in this document have changed. All other provisions set forth in the January 2001 final rule will be implemented without change.

Gradual instrumentation and control upgrades in U.S. nuclear power plants

International Nuclear Information System (INIS)

Welk, S.

1997-01-01

Since the late 1980s, US nuclear power plants have been struggling with the technical and licensing realities associated with installing digital protection and control systems into existing facilities. The industry, regulators and equipment vendors are finally reaching agreements regarding acceptable practices and requirements. The present paper explains the philosophy for gradual instrumentation and control replacements being pursued and the technical issues being addressed. It also describes some of the future challenges facing the industry. (author)

Ocean Thermal Energy Conversion Life Cycle Cost Assessment, Final Technical Report, 30 May 2012

Energy Technology Data Exchange (ETDEWEB)

Martel, Laura [Lockheed Martin, Manassas, VA (United States); Smith, Paul [John Halkyard and Associates: Glosten Associates, Houston, TX (United States); Rizea, Steven [Makai Ocean Engineering, Waimanalo, HI (United States); Van Ryzin, Joe [Makai Ocean Engineering, Waimanalo, HI (United States); Morgan, Charles [Planning Solutions, Inc., Vancouver, WA (United States); Noland, Gary [G. Noland and Associates, Inc., Pleasanton, CA (United States); Pavlosky, Rick [Lockheed Martin, Manassas, VA (United States); Thomas, Michael [Lockheed Martin, Manassas, VA (United States); Halkyard, John [John Halkyard and Associates: Glosten Associates, Houston, TX (United States)

2012-05-30

The Ocean Thermal Energy Conversion (OTEC) Life Cycle Cost Assessment (OLCCA) is a study performed by members of the Lockheed Martin (LM) OTEC Team under funding from the Department of Energy (DOE), Award No. DE-EE0002663, dated 01/01/2010. OLCCA objectives are to estimate procurement, operations and maintenance, and overhaul costs for two types of OTEC plants: -Plants moored to the sea floor where the electricity produced by the OTEC plant is directly connected to the grid ashore via a marine power cable (Grid Connected OTEC plants) -Open-ocean grazing OTEC plant-ships producing an energy carrier that is transported to designated ports (Energy Carrier OTEC plants) Costs are developed using the concept of levelized cost of energy established by DOE for use in comparing electricity costs from various generating systems. One area of system costs that had not been developed in detail prior to this analysis was the operations and sustainment (O&S) cost for both types of OTEC plants. Procurement costs, generally referred to as capital expense and O&S costs (operations and maintenance (O&M) costs plus overhaul and replacement costs), are assessed over the 30 year operational life of the plants and an annual annuity calculated to achieve a levelized cost (constant across entire plant life). Dividing this levelized cost by the average annual energy production results in a levelized cost of electricity, or LCOE, for the OTEC plants. Technical and production efficiency enhancements that could result in a lower value of the OTEC LCOE were also explored. The thermal OTEC resource for Oahu, Hawaii and projected build out plan were developed. The estimate of the OTEC resource and LCOE values for the planned OTEC systems enable this information to be displayed as energy supplied versus levelized cost of the supplied energy; this curve is referred to as an Energy Supply Curve. The Oahu Energy Supply Curve represents initial OTEC deployment starting in 2018 and demonstrates the

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

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

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.

Final priority. Rehabilitation Training: Job-Driven Vocational Rehabilitation Technical Assistance Center. Final priority.

Science.gov (United States)

2014-08-19

The Assistant Secretary for Special Education and Rehabilitative Services announces a priority under the Rehabilitation Training program to establish a Job-Driven Vocational Rehabilitation Technical Assistance Center (JDVRTAC). The Assistant Secretary may use this priority for competitions in fiscal year (FY) 2014 and later years. We take this action to focus on training in an area of national need. Specifically, this priority responds to the Presidential Memorandum to Federal agencies directing them to take action to address job-driven training for the Nation's workers. The JDVRTAC will provide technical assistance (TA) to State vocational rehabilitation (VR) agencies to help them develop for individuals with disabilities training and employment opportunities that meet the needs of today's employers.

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)

Final priority; Technical Assistance on State Data Collection--IDEA Data Management Center. Final priority.

Science.gov (United States)

2014-08-05

The Assistant Secretary for the Office of Special Education and Rehabilitative Services (OSERS) announces a priority under the Technical Assistance on State Data Collection program. The Assistant Secretary may use this priority for competitions in fiscal year (FY) 2014 and later years. We take this action to fund a cooperative agreement to establish and operate an IDEA Data Management Center (Center) that will provide technical assistance (TA) to improve the capacity of States to meet the data collection requirements of the Individuals with Disabilities Education Act (IDEA).

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

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)

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)

Imagining Technicities

DEFF Research Database (Denmark)

Liboriussen, Bjarke; Plesner, Ursula

2011-01-01

to the elements of taste and skill. In the final analysis those references were synthesized as five imagined technicities: the architect, the engineer, the client, the Chinese, and the Virtual World native. Because technicities are often assumed and rarely discussed as actants who influence practice, their role......, this article focuses on innovative uses of virtual worlds in architecture. We interviewed architects, industrial designers and other practitioners. Conceptually supported by an understanding of technicity found in Cultural Studies, the interviews were then coded with a focus on interviewees’ references...... in cooperation and development of ICTs seems to pass unnoticed. However, since they are aligned into ICTs, technicities impact innovation....

Study on reactor vessel replacement (RVR) for 1100 MW class BWR plants in Japan

International Nuclear Information System (INIS)

Mizutani, J.; Kawamura, S.; Aoki, M.; Mori, T.

2001-01-01

Plant Life Management (PLM) is being studied in Japan, and reactor vessel replacement (RVR) is being considered as one option. Since reactor internals, except for reusable parts, and the reactor pressure vessel (RPV) are replaced, the RVR provides an effective technology for extending the service life of nuclear power plants substantially. At ICONE 7, we reported on the technical viability of the RVR for BWR4-type 800 MWe class plants. This time, we rationalized the RVR method through a study for BWR5-type 1100 MWe class plants to reduce the RVR duration and evaluated the technical viability and the economic efficiency of the method. In addition, we discuss how to dispose of the RPV to complete a scenario of the process from the RVR to its final disposal. (author)

Palisades technical specification conversion from custom to new industry standard

International Nuclear Information System (INIS)

Foley, D.J.; Young, B.

1990-01-01

Consumers Power Company's (CPCo) Palisades plant is in the process of converting from custom technical specifications to the new industry standard, Restructured Standard Technical Specifications (RSTS). Custom technical specifications were the precursor to standard technical specifications, being issued to plants built prior to 1972. In May 1989, each of the four light water reactor owners' groups completed topical reports presenting their version of Restructured Standard Technical Specifications to the Nuclear Regulatory Commission (NRC). After approval of the owners' groups versions of the RSTs by the NRC, individual operating reactors will begin to make the conversion to the RSTS. Each owners' group has designated a lead plant, which will be the first of that vendor type to convert. All of the lead plants currently operate under standard technical specifications. The content of the RSTS was determined by comparing the standard technical specifications with selection criteria specified in the Commissions Interim Policy Statement

Compliance with technical codes becomes obligatory for receipt of feed-in tariff and ancillary services bonus for wind power plants in Germany

Energy Technology Data Exchange (ETDEWEB)

Boemer, Jens. C. [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Delft Univ. of Technology (Netherlands). Electrical Power Systems Group; Burges, Karsten [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Kumm, Thomas [VDE, Network Technology and Operation Forum (FNN), Berlin (Germany); Poeller, Markus [DIgSILENT GmbH, Gomaringen (Germany)

2009-07-01

The German government aims at a share of electricity generation based on renewable sources (RES-E) of more than 30% by 2020. A major part of this share will be reached by the use of wind power plants (WPP). Therefore, when amending the Renewable Energy Sources Act (EEG) in June 2008, the German government acknowledged the importance of enhanced technical requirements for WPP and announced the development of a respective technical ordinance. For all WPP that go into operation after June 2010, full grid code-compliance becomes a precondition for privileged network access, receipt of feed-in tariff, and extra payments (''ancillary services bonus''). The basis for the technical requirements in the EEG has been laid down by Medium-Voltage (MV)-Directive 2008 and the TransmissionCode 2007. However, the work of the authors - consulting the German government during the development of the technical ordinance - showed that the TransmissionCode 2007 needed careful review and some clarifying specifications were proposed. Eventually, the so called ''Ancillary Services Ordinance'' for wind power plants went into power in July 2009. The interrelation between all three grid codes as well as their specifications and implications for renewable energy sources generators, with special regard to wind power plants, are presented in this paper. (orig.)

Economics of hybrid photovoltaic power plants

Energy Technology Data Exchange (ETDEWEB)

Breyer, Christian

2012-08-16

plants, wind power, solar thermal power (STEG) and hydro power plants. For the 2010s, detailed global demand curves are derived for hybrid PV-Fossil power plants on a per power plant, per country and per fuel type basis. The fundamental technical and economic potentials for hybrid PV-STEG, hybrid PV-Wind and hybrid PV-Hydro power plants are considered. The global resource availability for PV and wind power plants is excellent, thus knowing the competitive or complementary characteristic of hybrid PV-Wind power plants on a local basis is identified as being of utmost relevance. The complementarity of hybrid PV-Wind power plants is confirmed. As a result of that almost no reduction of the global economic PV market potential need to be expected and more complex power system designs on basis of hybrid PV-Wind power plants are feasible. The final target of implementing renewable power technologies into the global power system is a nearly 100% renewable power supply. Besides balancing facilities, storage options are needed, in particular for seasonal power storage. Renewable power methane (RPM) offers respective options. A comprehensive global and local analysis is performed for analysing a hybrid PV-Wind-RPM combined cycle gas turbine power system. Such a power system design might be competitive and could offer solutions for nearly all current energy system constraints including the heating and transportation sector and even the chemical industry. Summing up, hybrid PV power plants become very attractive and PV power systems will very likely evolve together with wind power to the major and final source of energy for mankind.

Economics of hybrid photovoltaic power plants

Energy Technology Data Exchange (ETDEWEB)

Breyer, Christian

2012-08-16

coal fired power plants, wind power, solar thermal power (STEG) and hydro power plants. For the 2010s, detailed global demand curves are derived for hybrid PV-Fossil power plants on a per power plant, per country and per fuel type basis. The fundamental technical and economic potentials for hybrid PV-STEG, hybrid PV-Wind and hybrid PV-Hydro power plants are considered. The global resource availability for PV and wind power plants is excellent, thus knowing the competitive or complementary characteristic of hybrid PV-Wind power plants on a local basis is identified as being of utmost relevance. The complementarity of hybrid PV-Wind power plants is confirmed. As a result of that almost no reduction of the global economic PV market potential need to be expected and more complex power system designs on basis of hybrid PV-Wind power plants are feasible. The final target of implementing renewable power technologies into the global power system is a nearly 100% renewable power supply. Besides balancing facilities, storage options are needed, in particular for seasonal power storage. Renewable power methane (RPM) offers respective options. A comprehensive global and local analysis is performed for analysing a hybrid PV-Wind-RPM combined cycle gas turbine power system. Such a power system design might be competitive and could offer solutions for nearly all current energy system constraints including the heating and transportation sector and even the chemical industry. Summing up, hybrid PV power plants become very attractive and PV power systems will very likely evolve together with wind power to the major and final source of energy for mankind.

Technical and economic evaluation of controlled disposal options for very low level radioactive wastes

International Nuclear Information System (INIS)

Robinson, P.J.; Vance, J.N.

1990-08-01

Over the past several years, there has been considerable interest by the nuclear industry in the Nuclear Regulatory Commission (NRC) explicitly defined an activity level in plant waste materials at which the radiological impacts would be so low as to be considered Below Regulatory Concern (BRC). In January 1989, Electric Power Research Institute (EPRI) completed an extensive industry research effort to develop the technical bases for establishing criteria for the disposal of very low activity wastes in ordinary disposal facilities. The Nuclear Management and Resources Council (NUMARC), with assistance from the Edison Electric Institute (EEI) and the Electric Power Research Institute (EPRI), drafted a petition titled: ''Petition for Rulemaking Regarding Disposal of Below Regulatory Concern Radioactive Wastes from Commercial Nuclear Power Plants.'' Subsequent to the industry making a final decision for submittal of the drafted BRC petition, EPRI was requested to evaluate the technical and economic impact of six BRC options. These options are: take no action in pursuing a BRC waste exemption, petition the NRC for authorization to disposal of any BRC waste in any ordinary disposal facility, limit disposal of BRC waste to the nuclear power plant site, limit disposal of BRC waste to the nuclear power plant site and other utility owned property, petition for a mixed waste exemption, and petition for single waste stream exemptions in sequence (i.e. soil, followed by sewage sludge, etc.). The petition and technical bases were written to support the disposal of any BRC waste type in any ordinary disposal facility. These documents do not provide all of the technical and economic information needed to completely assessment the BRC options. This report provides the technical and economic basis for a range of options concerning disposal of very low activity wastes. 3 figs., 20 tabs

Aggregated Dispatch of Distributed Generation Units: Final Report

Energy Technology Data Exchange (ETDEWEB)

2004-09-01

This final report describes a project to demonstrate the technical and economic feasibility of aggregating distributed generating resources in New York State. This project demonstrates a system that allows distributed generation (DG) to participate in competitive markets in much the same way as large central-station power plants. This approach involves aggregating the distributed demand-side resources into a single transaction entity consistent with the requirements of the New York Independent System Operator (NYISO). This single entity then buys or sells capacity and energy (i.e., curtailment) in NYISO markets.

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)

Puget Sound Tidal Energy In-Water Testing and Development Project Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Collar, Craig W

2012-11-16

Tidal energy represents potential for the generation of renewable, emission free, environmentally benign, and cost effective energy from tidal flows. A successful tidal energy demonstration project in Puget Sound, Washington may enable significant commercial development resulting in important benefits for the northwest region and the nation. This project promoted the United States Department of Energy's Wind and Hydropower Technologies Program's goals of advancing the commercial viability, cost-competitiveness, and market acceptance of marine hydrokinetic systems. The objective of the Puget Sound Tidal Energy Demonstration Project is to conduct in-water testing and evaluation of tidal energy technology as a first step toward potential construction of a commercial-scale tidal energy power plant. The specific goal of the project phase covered by this award was to conduct all activities necessary to complete engineering design and obtain construction approvals for a pilot demonstration plant in the Admiralty Inlet region of the Puget Sound. Public Utility District No. 1 of Snohomish County (The District) accomplished the objectives of this award through four tasks: Detailed Admiralty Inlet Site Studies, Plant Design and Construction Planning, Environmental and Regulatory Activities, and Management and Reporting. Pre-Installation studies completed under this award provided invaluable data used for site selection, environmental evaluation and permitting, plant design, and construction planning. However, these data gathering efforts are not only important to the Admiralty Inlet pilot project. Lessons learned, in particular environmental data gathering methods, can be applied to future tidal energy projects in the United States and other parts of the world. The District collaborated extensively with project stakeholders to complete the tasks for this award. This included Federal, State, and local government agencies, tribal governments, environmental groups, and

District heating and cooling system for communities through power plant retrofit and distribution network. Final report, Phase I

Energy Technology Data Exchange (ETDEWEB)

1979-06-01

The technical and economic feasibility of retrofitting thermal power plants in Minnesota to accommodate both heat and power generation for district heating was examined and is discussed. Three communities were identified as viable sites for co-generation district heating. (LCL)

Technical data. Final technical report, November 1980-May 1982. [Proposed WyCoalGas project, Converse County, Wyoming

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

This volume includes a description of the railway to transport the coal; possible unbalance in the electrical power supply is considered in detail, as well as communications, signalling, etc. The railway will also be used to transport ashes and sludges for waste disposal. Coal fines in the coal supply will be burned to generate power. A very brief description of the coal gasification plant and its components is accompanied by a printout of the dates final engineering is to be completed. Permit applications are listed and socio-economic factors are discussed. The financing plan is discussed in some detail: basically, a loan guarantee from the Synthetic Fuels Corporation; equity provided by investment tax credit, deferred taxes, AFUDC and the sponsors; price support; and gas purchase agreement (this whole section includes several legal details.). (LTN)

Design and technical status of the EU contribution to ITER

International Nuclear Information System (INIS)

Gasparotto, Maurizio; Federici, Gianfranco; Casci, Federico Riccardo

2009-01-01

Europe is involved in the procurement of most of the high-technology items for the ITER device (e.g. parts of the superconducting Toroidal (TF) and Poloidal Field (PF) coils, the vacuum vessel (VV), the in-vessel components, the remote handling, the additional heating systems, the tritium plant and cryoplant and finally parts of the diagnostics). In many cases the technologies required to manufacture these components are well established, in others there is still ongoing design and R and D work to select and optimise the final design solutions and to consolidate the underlying technologies as, for example, in the areas of heating and current drive, plasma diagnostics, shield blanket and first wall, remote handling, etc. A design review has recently been conducted by the ITER Organisation, with the support of the Domestic Agencies (DAs) established by the countries participating to ITER, to address the remaining outstanding technical issues and understand the associated implications for design, machine performance, schedule and cost. This paper provides an update of the design and technical status of EU contributions to ITER.

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.)

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

Some aspects of increasing the quality of personnel training for nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Jacko, J.; Frimmelova, A.

1989-01-01

Nuclear power plant personnel in Czechoslovakia is subject to periodical training in accordance with the Unified System of Nuclear Facility Personnel Training. This training is the responsibility of the Educational and Training Centre of the Nuclear Plant Research Institute in Trnava. Nuclear plant personnel is divided into 7 groups as follows: A - supervisory technical-administrative management staff; B - selected operating personnel such as shift supervisors, unit supervisors, reactor operators and secondary circuit operators; C - engineering-technical personnel of technical and maintenance departments; D - managing shift-operating staff; E - workers at technical plant departments; F - operational shift workers and servicemen; and G - maintenance personnel. These groups are respected in the training, which includes basic training, re-training and additional training. The basic training comprises 8 stages: general theoretical education; specialized theoretical education; on-the-job training in a plant designated for training; training on a simulator (group B); preparing for and taking final examinations for the certificate; doubling in the NPP designated for training (groups B, D, F); preparation in the NPP of future employment; preparing for and taking the state examination for obtaining the license (group B). Details of the management of the training process, experience gained during the implementation of the training and challenges for future improvement of the system are outlined. (P.A.)

Technical specification optimization program - engineered safety features

International Nuclear Information System (INIS)

Andre, G.R.; Jansen, R.L.

1986-01-01

The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

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

Proposed design modifications and technical specification changes on grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2 (Docket Nos. 50-266 and 50-301). Technical evaluation report

International Nuclear Information System (INIS)

White, R.L.

1981-01-01

This report documents the technical evaluation of the proposed design mofifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

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

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

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)

Uncertainty Quantification in the Reliability and Risk Assessment of Generation IV Reactors: Final Scientific/Technical Report

International Nuclear Information System (INIS)

Vierow, Karen; Aldemir, Tunc

2009-01-01

The project entitled, 'Uncertainty Quantification in the Reliability and Risk Assessment of Generation IV Reactors', was conducted as a DOE NERI project collaboration between Texas A and M University and The Ohio State University between March 2006 and June 2009. The overall goal of the proposed project was to develop practical approaches and tools by which dynamic reliability and risk assessment techniques can be used to augment the uncertainty quantification process in probabilistic risk assessment (PRA) methods and PRA applications for Generation IV reactors. This report is the Final Scientific/Technical Report summarizing the project.

Uncertainty Quantification in the Reliability and Risk Assessment of Generation IV Reactors: Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

Vierow, Karen; Aldemir, Tunc

2009-09-10

The project entitled, “Uncertainty Quantification in the Reliability and Risk Assessment of Generation IV Reactors”, was conducted as a DOE NERI project collaboration between Texas A&M University and The Ohio State University between March 2006 and June 2009. The overall goal of the proposed project was to develop practical approaches and tools by which dynamic reliability and risk assessment techniques can be used to augment the uncertainty quantification process in probabilistic risk assessment (PRA) methods and PRA applications for Generation IV reactors. This report is the Final Scientific/Technical Report summarizing the project.

When a plant shuts down: The psychology of decommissioning

International Nuclear Information System (INIS)

Schulz, J.; Crawford, A.C.

1993-01-01

Within the next decade, 10 to 25 nuclear plants in the United States may be taken off line. Many will have reached the end of their 40-year life cycles, but others will be retired because the cost of operating them has begun to outweigh their economic benefit. Such was the case at Fort St. Vrain, the first decommissioning of a US commercial plant under new Nuclear Regulatory Commission (NRC) regulations. Two major problems associated with decommissioning plants have been obvious: (1) the technical challenges and costs of decommissioning, and (2) the cost of maintaining and finally decommissioning a plant after a safe storage (SAFSTOR) period of approximately 60 years. What has received little attention is the challenge that affects not only the people who make a plant work, but the quality of the solutions to these problems: how to maintain effective organizational performance during the process of downsizing and decommissioning and/or SAFSTOR. The quality of technical solutions for closing a plant, as well as how successfully the decommissioning process is held within or below budget, will depend largely on how effectively the nuclear organization functions as a social unit. Technical and people issues are bound together. The difficulty is how to operate a plant effectively when plant personnel have no sense of long-term security. As the nuclear power industry matures and the pace for closing operating plants accelerates, the time has come to prepare for the widespread decommissioning of plants. The industry would be well served by conducting a selective, industry-wide evaluation of plants to assess its overall readiness for the decommissioning process. A decommissioning is not likely to be trouble free, but with a healthy appreciation for the human side of the process, it will undoubtedly go more smoothly than if approached as a matter of dismantling a machine

Lead plant application of leak-before-break to high energy piping. Final report, January 1989

International Nuclear Information System (INIS)

1989-01-01

This report presents the experience gained during a successful application of a leak-before-break program by Duquesne Light Company. This program was directed at the high energy nuclear piping at Beaver Valley Power Station - Unit 2. This experience can be applied to other nuclear plant leak-before-break efforts in order to minimize the number of pipe whip restraints, jet impingement shields, snubbers, and to discount the consideration of remaining pipe rupture dynamic effects. The chronology of events leading to Nuclear Regulatory Commission approval of the Beaver Valley Power Station - Unit 2 lead plant effort is described. The final report and pertinent sections of the final Safety Evaluation Report are also included. (author)

78 FR 71676 - NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Final Report”

Science.gov (United States)

2013-11-29

... Testing at Nuclear Power Plants, Final Report'' AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... entitled: NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at Nuclear Power Plants,'' and... Restraints (Snubbers) at Nuclear Power Plants.'' In the previous Revisions 0 and 1 of NUREG-1482, the NRC...

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

Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

International Nuclear Information System (INIS)

1997-07-01

This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs

Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs.

Security Hardened Cyber Components for Nuclear Power Plants: Phase I SBIR Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Franusich, Michael D. [SpiralGen, Inc., Pittsburgh, PA (United States)

2016-03-18

SpiralGen, Inc. built a proof-of-concept toolkit for enhancing the cyber security of nuclear power plants and other critical infrastructure with high-assurance instrumentation and control code. The toolkit is based on technology from the DARPA High-Assurance Cyber Military Systems (HACMS) program, which has focused on applying the science of formal methods to the formidable set of problems involved in securing cyber physical systems. The primary challenges beyond HACMS in developing this toolkit were to make the new technology usable by control system engineers and compatible with the regulatory and commercial constraints of the nuclear power industry. The toolkit, packaged as a Simulink add-on, allows a system designer to assemble a high-assurance component from formally specified and proven blocks and generate provably correct control and monitor code for that subsystem.

[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.

Geothermal Risk Reduction via Geothermal/Solar Hybrid Power Plants. Final Report

Energy Technology Data Exchange (ETDEWEB)

Wendt, Daniel [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mines, Greg [Idaho National Lab. (INL), Idaho Falls, ID (United States); Turchi, Craig [National Renewable Energy Lab. (NREL), Golden, CO (United States); Zhu, Guangdong [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-11-01

There are numerous technical merits associated with a renewable geothermal-solar hybrid plant concept. The performance of air-cooled binary plants is lowest when ambient temperatures are high due to the decrease in air-cooled binary plant performance that occurs when the working fluid condensing temperature, and consequently the turbine exhaust pressure, increases. Electrical power demand is generally at peak levels during periods of elevated ambient temperature and it is therefore especially important to utilities to be able to provide electrical power during these periods. The time periods in which air-cooled binary geothermal power plant performance is lowest generally correspond to periods of high solar insolation. Use of solar heat to increase air-cooled geothermal power plant performance during these periods can improve the correlation between power plant output and utility load curves. While solar energy is a renewable energy source with long term performance that can be accurately characterized, on shorter time scales of hours or days it can be highly intermittent. Concentrating solar power (CSP), aka solar-thermal, plants often incorporate thermal energy storage to ensure continued operation during cloud events or after sunset. Hybridization with a geothermal power plant can eliminate the need for thermal storage due to the constant availability of geothermal heat. In addition to the elimination of the requirement for solar thermal storage, the ability of a geothermal/solar-thermal hybrid plant to share a common power block can reduce capital costs relative to separate, stand-alone geothermal and solar-thermal power plant installations. The common occurrence of long-term geothermal resource productivity decline provides additional motivation to consider the use of hybrid power plants in geothermal power production. Geothermal resource productivity decline is a source of significant risk in geothermal power generation. Many, if not all, geothermal resources

Review of technical issues related to the failure of Rosemount pressure transmitters due to fill oil loss. Final report

International Nuclear Information System (INIS)

James, R.W.; Gaertner, J.P.; Burns, E.T.; Horn, A.; Lee, L.K.

1994-08-01

Rosemount pressure transmitters are extensively used in both safety and non-safety applications in US nuclear power plants. They are used to measure pressure, flow, and water level. Rosemount pressure transmitter models 1151, 1152, 1153A, 1153, and 1154 use a fill oil to hydraulically transmit process pressure exerted on outer isolating diaphragms to internal diaphragms. The resulting deflection of the internal diaphragms changes the distance between them and a central diaphragm separating the transmitter interior into two volumes. The change in distance is measured as a change in electrical capacitance between the isolating diaphragms and the central diaphragm and can be related to differential pressure. The fill oil also functions as a dielectric. It has been well established that this fill oil can potentially leak over time, decreasing transmitter accuracy and increasing transmitter response time. Ultimately, the transmitter can fail. An extensive effort has been expended by the nuclear power industry collectively to analyze this issue and develop technically sound and reasonable requirements to mitigate the effects of oil loss in Rosemount pressure transmitters. Despite this, technical concerns have still been raised regarding the technical validity of the past analyses of this problem and its scope. In May 1993, the NRC created an internal group to comprehensively review the Rosemount issue and the NRC's action in addressing it to ensure that all available technical information has been considered. Because this issue remains of active technical interest and because the past work on this subject has been done by many different groups and organizations, EPRI has prepared this report to thoroughly document the current technical understanding of this issue, to perform additional analysis, and to identify any appropriate additional technical research activities regarding oil loss in Rosemount pressure transmitters

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.)

Programs of Study as a State Policy Mandate: A Longitudinal Study of the South Carolina Personal Pathways to Success Initiative. Final Technical Report: Major Findings and Implications

Science.gov (United States)

Hammond, Cathy; Drew, Sam F.; Withington, Cairen; Griffith, Cathy; Swiger, Caroline M.; Mobley, Catherine; Sharp, Julia L.; Stringfield, Samuel C.; Stipanovic, Natalie; Daugherty, Lindsay

2013-01-01

This is the final technical report from the National Research Center for Career and Technical Education's (NRCCTE's) five-year longitudinal study of South Carolina's Personal Pathway to Success initiative, which was authorized by the state's Education and Economic Development Act (EEDA) in 2005. NRCCTE-affiliated researchers at the National…

Volume reduction and conditioning campaigns, upon low level solid waste drums, realised in ENEA centres of Trisaia (ITREC plant) and Saluggia (EUTREX plant)

International Nuclear Information System (INIS)

Gili, M.

1995-09-01

The volume reduction and conditioning campaigns, upon low level solid waste drums, realized between 1989 and 1993 in the ENEA (Italian Agency for New Technologies, Energy and the Environment) centres of Trisaia (ITREC plant) and Saluggia (EUREX plant), by the mean of supercompactation, and cement immobilization inside over packs, are hereby described. The operational techniques and the equipments used, the whole volume reduction factors obtained and some final considerations over this solid rad wastes treatment procedure are shown. This method, where correctly operated and coupled to an accurate radiological characterization, permits to save space for the waste storage in the short period and to obtain final manufacts, certified suitable for shallow burial disposal, according to italian technical guide n. 26

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

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

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

Risk-based technical specifications program: Site interview results

International Nuclear Information System (INIS)

Andre, G.R.; Baker, A.J.; Johnson, R.L.

1991-08-01

The Electric Power Research Institute and Pacific Gas and Electric Company are sponsoring a program directed at improving Technical Specifications using risk-based methods. The major objectives of the program are to develop risk-based approaches to improve Technical Specifications and to develop an Interactive Risk Advisor (IRA) prototype. The IRA is envisioned as an interactive system that is available to plant personnel to assist in controlling plant operation. Use of an IRA is viewed as a method to improve plant availability while maintaining or improving plant safety. In support of the program, interviews were conducted at several PWR and BWR plant sites, to elicit opinions and information concerning risk-based approaches to Technical Specifications and IRA requirements. This report presents the results of these interviews, including the functional requirements of an IRA. 2 refs., 6 figs., 2 tabs

Technical considerations associated with spent fuel acceptance. Final report

International Nuclear Information System (INIS)

Supko, E.M.

1996-06-01

This study was initiated by the Electric Power Research Institute (EPRI) to identify technical considerations associated with spent fuel acceptance and implementation of a waste management system that includes the use of transportable storage systems, and to serve as an opening dialogue among Standard Contract Holders and the department of Energy's Office of Civilian Radioactive Waste management (OCRWM) prior to the development of waste acceptance criteria or issuance of a Notice of Proposed Rulemaking by OCRWM to amend the Standard Contract. The original purpose of the Notice of Proposed Rulemaking was to address changes to the Standard Contract to implement a multi-purpose canister based system and to address other issues that were not adequately addressed in the standard contract. Even if DOE does not develop a multi-purpose canister based system for waste acceptance, it will still be necessary to develop waste acceptance criteria in order to accept spent fuel in transportable storage systems that are being deployed for at-reactor storage. In this study, technical issues associated with spent fuel acceptance will be defined and potential options and alternatives for resolution of technical considerations will be explored

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

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Held, Isaac [Princeton Univ., NJ (United States); Balaji, V. [Princeton Univ., NJ (United States); Fueglistaler, Stephan [Princeton Univ., NJ (United States)

2016-09-19

We have constructed and analyzed a series of idealized models of tropical convection interacting with large-scale circulations, with 25-50km resolution and with 1-2km cloud resolving resolution to set the stage for rigorous tests of convection closure schemes in high resolution global climate models. Much of the focus has been on the climatology of tropical cyclogenesis in rotating systems and the related problem of the spontaneous aggregation of convection in non-rotating systems. The PI (Held) will be delivering the honorary Bjerknes lecture at the Fall 2016 AGU meeting in December on this work. We have also provided new analyses of long-standing issues related to the interaction between convection and the large-scale circulation: Kelvin waves in the upper troposphere and lower stratosphere, water vapor transport into the stratosphere, and upper tropospheric temperature trends. The results of these analyses help to improve our understanding of processes, and provide tests for future high resolution global modeling. Our final goal of testing new convections schemes in next-generation global atmospheric models at GFDL has been left for future work due to the complexity of the idealized model results meant as tests for these models uncovered in this work and to computational resource limitations. 11 papers have been published with support from this grant, 2 are in review, and another major summary paper is in preparation.

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.

The application of plant information system on third Qinshan nuclear power plant

International Nuclear Information System (INIS)

Liu Wangtian

2005-01-01

Plant overall control has been applied in Qinshan Nuclear Power Plant, which enhances the security of plant operation, but it is not enough to improve the technical administration level. In order to integrate the overall information and to improve the technical administration level more. Third Qinshan Nuclear Power Plant applies the plant information system. This thesis introduces the application of plant information system in Third Qinshan Nuclear Power Plant and the effect to the plant after the system is carried into execution, in addition, it does more analysis and exceptions for application of plant information system in the future. (authors)

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

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

Opening remarks: regulatory initiatives toward improved technical specifications

International Nuclear Information System (INIS)

Edison, G.E.

1985-01-01

In order to deal with the numerous problems that have evolved over the years with nuclear power plant technical specifications, the Nuclear Regulatory Commission has undertaken some initiatives for improvement: 1) new operating licenses, 2) change to existing operating reactor technical specifications, 3) a broad-scoped reconsideration of the content of technical specifications, and 4) rule changes. It is believed that reliability and risk assessment techniques can be used in conjunction with manufacturer's recommendations and engineering judgment to better define the appropriate scope and depth for technical specification resulting in focusing attention on high risk-worth systems and avoidance of plant shutdown transients both intentionally and unintentionally through provisions of technical specifications

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.

Integrated risk - healthy technical conscience

Energy Technology Data Exchange (ETDEWEB)

Freeman, P. [Institute of Nuclear Power Operations, Atlanta, GA (United States)

2015-07-01

The personal obligation leaders and individuals internalize and exercise to ensure plant operation, maintenance, and engineering activities are conducted in a manner consistent with plant design, emergency response strategies, technical requirements and that preserve operating, design and safety margins. Technical errors are increasing, both in number and significance. Causes are common at many utilities. The majority of these engineering human performance weaknesses have not had immediate impact on station reliability and safety (not self-revealing). In some recent projects, the same weaknesses affected a station's viability.

A Novel Slurry-Based Biomass Reforming Process Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Emerson, Sean C. [United Technologies Research Center, East Hartford, CT (United States); Davis, Timothy D. [United Technologies Research Center, East Hartford, CT (United States); Peles, A. [United Technologies Research Center, East Hartford, CT (United States); She, Ying [United Technologies Research Center, East Hartford, CT (United States); Sheffel, Joshua [United Technologies Research Center, East Hartford, CT (United States); Willigan, Rhonda R. [United Technologies Research Center, East Hartford, CT (United States); Vanderspurt, Thomas H. [United Technologies Research Center, East Hartford, CT (United States); Zhu, Tianli [United Technologies Research Center, East Hartford, CT (United States)

2011-09-30

to hydrogen, methane, and carbon dioxide was repeatedly demonstrated in batch reactors varying in size from 50 mL to 7.6 L. The different wood sources (e.g., swamp maple, poplar, and commercial wood flour) were converted in the presence of a heterogeneous catalyst and base at relatively low temperatures (e.g., 310°C) at sub-critical pressures sufficient to maintain the liquid phase. Both precious metal and base metal catalysts were found to be active for the liquid phase hydrolysis and reforming of wood. Pt-based catalysts, particularly Pt-Re, were shown to be more selective toward breaking C-C bonds, resulting in a higher selectivity to hydrogen versus methane. Ni-based catalysts were found to prefer breaking C-O bonds, favoring the production of methane. The project showed that increasing the concentration of base (base to wood ratio) in the presence of Raney Ni catalysts resulted in greater selectivity toward hydrogen but at the expense of increasing the production of undesirable organic acids from the wood, lowering the amount of wood converted to gas. It was shown that by modifying Ni-based catalysts with dopants, it was possible to reduce the base concentration while maintaining the selectivity toward hydrogen and increasing wood conversion to gas versus organic acids. The final stage of the project was the construction and testing of a demonstration unit for H2 production. This continuous flow demonstration unit consisted of wood slurry and potassium carbonate feed pump systems, two reactors for hydrolysis and reforming, and a gas-liquid separation system. The technical challenges associated with unreacted wood fines and Raney Ni catalyst retention limited the demonstration unit to using a fixed bed Raney Ni catalyst form. The lower activity of the larger particle Raney Ni in turn limited the residence time and thus the wood mass flow feed rate to 50 g min-1 for a 1 wt% wood slurry. The project demonstrated continuous H2 yields with unmodified, fixed bed

Final technical report; Mercury Release from Organic matter (OM) and OM-Coated Mineral Surfaces

Energy Technology Data Exchange (ETDEWEB)

Aiken, George

2014-10-02

This document is the final technical report for a project designed to address fundamental processes controlling the release of mercury from flood plain soils associated with East Fork Poplar Creek, Tennessee near the U.S. Department of Energy Oak Ridge facility. The report summarizes the activities, findings, presentations, and publications resulting from an award to the U.S. Geological that were part of a larger overall effort including Kathy Nagy (University of Illinois, Chicago, Ill) and Joseph Ryan (University of Colorado, Boulder, CO). The specific charge for the U.S.G.S. portion of the study was to provide analytical support for the larger group effort (Nagy and Ryan), especially with regard to analyses of Hg and dissolved organic matter, and to provide information about the release of mercury from the floodplain soils.

Final environmental impact statement. Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1980-10-01

This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described

LHC Report: finalizing the shutdown activities

CERN Multimedia

CERN Bulletin

2011-01-01

The maintenance work and other activities scheduled for the LHC technical stop have now been completed and the electrical, quality assurance and powering tests are in full swing.   These hardware tests, or hardware re-commissioning as it is known in the CERN Control Centre, are complete for Sectors 5-6 and 6-7. The re-commissioning process is almost complete in Sectors 7-8 and 8-1, but a problem with the emergency stop safety system last week, and the failure of a turbine in the cryogenic plant at Point 8, mean that the final part of the re-commissioning for these two sectors has been delayed and will be completed this week. Preparations for the re-commissioning in the other 4 sectors are going well, and everything is on schedule for the LHC to restart with beam as planned on 18 February. At the SPS, all the technical stop work and magnet changes have been completed and the machine has been handed over to the Operations Group for the usual set of hardware tests and preparations for beam operation. ...

Design principle of TVO's final repository and preliminary adaptation to site specific conditions

International Nuclear Information System (INIS)

Salo, J-P.; Reikkola, R.

1995-01-01

Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs

Feasibility assessment of a risk-based approach to technical specifications

International Nuclear Information System (INIS)

Atefi, B.; Gallagher, D.W.

1991-05-01

To assess the potential use of risk and reliability techniques for improving the effectiveness of the technical specifications to control plant operational risk, the Technical Specifications Branch of the Nuclear Regulatory Commission initiated an effort to identify and evaluate alternative risk-based approaches that could bring greater risk perspective to these requirements. In the first phase four alternative approaches were identified and their characteristics were analyzed. Among these, the risk-based approach to technical specifications is the most promising approach for controlling plant operational risk using technical specifications. The second phase of the study concentrated on detailed characteristics of the real time risk-based approach. It is concluded that a real time risk-based approach to technical specifications has the potential to improve both plant safety and availability. 33 figs., 5 figs., 6 tabs

Final disposal of decommissioning wastes in the Federal Republic of Germany

Energy Technology Data Exchange (ETDEWEB)

Brewitz, W; Stippler, R

1981-01-01

The waste disposal concept of the Federal Republic of Germany for nuclear power plants provides for the final disposal of radioactive waste in deep geological formations and mines. The radiological safety of such a repository depends on a system of multiple barriers of which the geological barrier is the most important one. The isolation concept must guarantee the waste to decay below the limiting values of the German Radiation Protection Regulation within the repository. The expected total decommissioning waste masses from 12 nuclear power plants operating in the Federal Republic of Germany amounts to approxiametly 85000 Mg. For the final disposal of these wastes there are, under present aspects, two mines being considered as repositories. The pilot repository in the Asse II salt mine is in the state of licensing. The adandoned iron ore mine Konrad is being investigated for its feasibility and licensing will probably be initiated in 1982. Capacity and efficiency calculations have proved that both mines have got the technical requirements needed for the disposal of decommissioning and operating wastes from existent as well as from future built nuclear power plants.

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

Dual-purpose power plants, experiences with exhaust gas purification plants

International Nuclear Information System (INIS)

Dietrich, R.

1993-01-01

From 1984 to 1988, the research and development project ''pollutant reduction for exhaust gases from heat production systems'' sponsored by the Federal Ministry of Research and Technology (BMFT) has been carried out by TUeV in Bavaria. This project was to show the state of exhaust gas technology for small and medium-sized plants (boilers and motoric heat generators). When publishing the final report, no positive balance could be given. Based on the results, the succession project ''Exhaust gas purification plants in field test'' (ARIF) has been started. This project has the following objectives: -Measuring technical investigation of the exhaust gas purification of motoric driven heat generator systems in field test. - Suitability of hand measuring devices for emissions for a discontinuous control of the exhaust gas purification plat by the operator. - Control of new methods regarding pollutant reduction for motoric and conventional heat generators. (orig.) [de

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

More efficient resource utilization of geothermal plants. Technical possibilities and their assessment; Effizientere Ressourcenausnutzung geothermischer Anlagen. Technische Moeglichkeiten und deren Bewertung

Energy Technology Data Exchange (ETDEWEB)

Kock, Nils; Kaltschmitt, Martin [Technische Univ. Hamburg-Harburg, Hamburg (Germany). Inst. fuer Umwelttechnik und Energiewirtschaft

2011-12-15

The geological conditions in Germany allow maximum temperatures between 160 to 170 C free well head taking techno-economic constraint into consideration. This makes an electricity production for purely technical reasons possible, but only with low efficiencies due to physical constraints. That's why it assault big amounts of waste heat. For example, the existing geothermal power plants in Germany provide in average 18% of electricity and 82% of heat. This heat is use so far only to a very small degree. Even is a district heating system is operated to supply private households, this heat is used with less than 2.500 h per year. That's why the still hot thermal water is press back into the underground without any further utilization. For these reasons to achieve a technical and economic optimization it should be the aim to find different reasonable options to use this waste heat. One possibility is the coupling with a drying process at the location of the geothermal plant. Such options will be analyzed from a technical and economic point of view and some conclusions will be drawn. (orig.)

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

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

Neural network recognition of nuclear power plant transients. Final report, April 15, 1992--April 15, 1995

Energy Technology Data Exchange (ETDEWEB)

Bartlett, E.B.

1995-05-15

The objective of this report is to describe results obtained during the second year of funding that will lead to the development of an artificial neural network (A.N.N) fault diagnostic system for the real-time classification of operational transients at nuclear power plants. The ultimate goal of this three-year project is to design, build, and test a prototype diagnostic adviser for use in the control room or technical support center at Duane Arnold Energy Center (DAEC); such a prototype could be integrated into the plant process computer or safety-parameter display system. The adviser could then warn and inform plant operators and engineers of plant component failures in a timely manner. This report describes the work accomplished in the second of three scheduled years for the project. Included herein is a summary of the second year`s results as well as descriptions of each of the major topics undertaken by the researchers. Also included are reprints of the articles written under this funding as well as those that were published during the funded period.

Neural network recognition of nuclear power plant transients. Final report, April 15, 1992--April 15, 1995

International Nuclear Information System (INIS)

Bartlett, E.B.

1995-01-01

The objective of this report is to describe results obtained during the second year of funding that will lead to the development of an artificial neural network (A.N.N) fault diagnostic system for the real-time classification of operational transients at nuclear power plants. The ultimate goal of this three-year project is to design, build, and test a prototype diagnostic adviser for use in the control room or technical support center at Duane Arnold Energy Center (DAEC); such a prototype could be integrated into the plant process computer or safety-parameter display system. The adviser could then warn and inform plant operators and engineers of plant component failures in a timely manner. This report describes the work accomplished in the second of three scheduled years for the project. Included herein is a summary of the second year's results as well as descriptions of each of the major topics undertaken by the researchers. Also included are reprints of the articles written under this funding as well as those that were published during the funded period

Studies of potential severe accidents in Finnish nuclear power plants. Quarterly report 3. quarter 1987

International Nuclear Information System (INIS)

Aro, Ilari.

1989-07-01

This thesis is based on six publications dealing with severe accident studies in Finnish nuclear power plants. Main emphasis has been put on general technical bases and methodologies applied in severe accident evaluation in Finland. As an example of the use of the analysis and evaluation methods, the analysis of one representative accident sequence, t otal loss of AC power , has been presented for both Finnish power plant types. This accident sequence is required to be analyzed in the Finnish safety guide YVL 2.2 which deals with transient and accident analyses as a basis of technical solutions at nuclear powr plants. Two different analysis methods, MAAP 3.0 and MARCH 3/STCP have been used for receiving as complete a picture as possible of the flow of events and for verifying the models to some extent. Besides the use of the two different models, the method of sensitivity analysis has been used for evaluating the effects of some important technical parameters on the accident flow. Finally, conclusions of the applicability of the two methods for analyzing severe accident sequences in Finnish plants have been discussed

Microscopic heavy-ion theory. Final technical report, June 1, 1993 - May 31, 1996

International Nuclear Information System (INIS)

Ernst, D.J.; Oberacker, V.E.; Umar, A.S.

1998-01-01

In this Final Technical Report, the authors summarize the research activities of the three Principal Investigators (Professors Ernst, Oberacker, and Umar) at Vanderbilt University since the last reporting period through the subject award expiration date (Dec. 31, 1996) under contract DE-FG05-87ER40376 with the Department of Energy. The research effort is divided between the following three areas: nuclear structure and astrophysics (microscopic nuclear structure studies and properties of exotic nuclei at HRIBF, supernovae calculations in connection with nuclear astrophysics, and nuclear viscosity studies via muon-induced fission at PSI); pion and kaon interactions with the nucleus at high energies (interaction of pions and kaons with nuclei from low energies to 1 GeV, propagation of excited hadrons in the nuclear medium as probed by pion and electron induced reactions); nuclear physics at high energies (dynamical string-parton model to study multi-particle production at RHIC, electromagnetic lepton pair production at RHIC)

Review of nuclear power plant systems

International Nuclear Information System (INIS)

Doehler

1980-01-01

This presentation starts with a brief description of the Technischer Ueberwachungs-Verein (TUeV) and its main activities in the field of technical assessments. The TUeV-organisation is in general the assessor who performs the review if nuclear power plant systems, structures and equipment. All aspects relating to the safe operation of nuclear power plants are assessed by the TUeV. This paper stresses the review of the design of nuclear power plant systems and structures. It gives an outline on the procedure of an assessment, starting with the regulatory requirements, going into the papers of the applicant and finally ending with the TUeV-appraisal. This procedure is shown using settlement measuring requirements as an example. The review of the design of mechanical structures such as pipes, valves, pump and vessels is shown in detail. (RW)

Head Start Impact Study. Technical Report

Science.gov (United States)

Puma, Michael; Bell, Stephen; Cook, Ronna; Heid, Camilla; Shapiro, Gary; Broene, Pam; Jenkins, Frank; Fletcher, Philip; Quinn, Liz; Friedman, Janet; Ciarico, Janet; Rohacek, Monica; Adams, Gina; Spier, Elizabeth

2010-01-01

This Technical Report is designed to provide technical detail to support the analysis and findings presented in the "Head Start Impact Study Final Report" (U.S. Department of Health and Human Services, January 2010). Chapter 1 provides an overview of the Head Start Impact Study and its findings. Chapter 2 provides technical information on the…

Final environmental impact statement. Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

1980-10-01

This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)

Final Scientific Technical Report Crowder College MARET Center

Energy Technology Data Exchange (ETDEWEB)

Boyt, Art [Crowder College, Neosho, MO (United States); Eberle, Dan [Crowder College, Neosho, MO (United States); Hudson, Pam [Crowder College, Neosho, MO (United States); Hopper, Russ [Crowder College, Neosho, MO (United States)

2013-06-30

, exploring and validating new applications of solar and other renewable technologies, the MARET Facility will house a wide variety of programs which will advance implementation of renewable energy throughout the region. These program goals include; Curriculum in renewable energy for pre-engineering transfer programs; Certification and degree programs for technical degrees for Energy Efficiency, Wind, Photovoltaic and Solar Thermal professionals; Short courses and workshops for building management and design professionals; Public education and demonstration projects in renewable energy through conferences and K-12 educational outreach; Technical degree offering in building construction incorporating “best practices” for energy efficiency and renewables; and Business incubators for new renewable energy businesses and new product development The new MARET facility will support the mission of the US Department of Energy (DOE) Solar Program, “to improve America’s security, environmental quality, and economic prosperity through public-private partnerships that bring reliable and affordable solar energy technologies to the marketplace,” through a variety of educational and business assistance programs. Further, technical innovations planned for the MARET facility and its applied research activities will advance the Solar Program strategic goals to “reduce the cost of solar energy to the point it becomes competitive in relevant energy markets (e.g., buildings, power plants) and for solar technology to enable a sustainable solar industry.” Overarching Goals relative to program needs, future expansion, flexibility, quality of materials, and construction and operational costs:; Experimental: The structure and systems of the building operate as an educational resource. The systems are meant to be a source for data collection and study for building users and instructors; Educational: Part of the evolution of this building and its ongoing goals is to use the building as an

Final Technical Report: Results of Phase 1

Energy Technology Data Exchange (ETDEWEB)

Narang, David, J.; Hambrick, Joshua; Srinivasan, Devarajan; Ayyannar, Raja; O' Brien, Kathleen

2011-09-28

Arizona Public Service Company (APS) expects that by 2027, renewable energy will account for 6,590 GWh in energy consumption by its customers. While much of this future energy will come from large centrally-located power plants, distributed renewable energy, sited at the point of end-use will also play an important role in meeting the needs of APS customers and is expected to provide 1,734 GWh. With increasing penetration of residential and commercial photovoltaic (PV) systems at the point of end-use, PV power generation not only offsets the load, but could also cause significant shifts in power flow patterns through the distribution system, and could possibly cause reversal of flow through some branches of a distribution circuit. Significant changes to power flow introduced into existing distribution systems due to the increased amount of PV systems may cause operational issues, including over-voltage on the distribution feeder (loss of voltage regulation) and incorrect operation of control equipment, which may lead to an increase in the number of operations and related equipment wear that could affect equipment reliability and customer power quality. Additionally, connecting generation resources to a distribution feeder can introduce additional sources of short-circuit current to the distribution system. This could potentially result in increased short-circuit currents, potentially reaching damaging levels, causing protection desensitization and a potential loss of protection coordination. These effects may be further compounded by variability of PV production due to shading by clouds. The effects of these phenomena in distributed PV applications are not well understood, and there is a great need to characterize this variability. This project will contribute to understanding the effects of high-penetration solar electricity on the design and operation of distribution systems by demonstrating how a high penetration of PV systems affects grid operations of a

The System 80+ Standard Plant design control document. Volume 18

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains the following technical specifications of section 16 (Technical Specifications) of the ADM Design and Analysis: TS 3.3 Instrumentation; TS 3.4 Reactor Coolant System; TS 3.5 Emergency Core Cooling System; TS 3.6 Containment Systems; TS 3.7 Plant Systems; TS 3.8 Electrical Power Systems; TS 3.9 Refueling Operations; TS 4.0 Design Features; TS 5.0 Administrative Controls. Appendix 16 A Tech Spec Bases is also included. It contains the following: TS B2.0 Safety Limits Bases; TS B3.0 LCO Applicability Bases; TS B3.1 Reactivity Control Bases; TS B3.2 Power Distribution Bases

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

Procedures followed in the evaluation of a LWR plant in Spain and problems encountered

International Nuclear Information System (INIS)

Brincones, M.; Gea, A.; Perez del Moral, C.

1979-01-01

The main problems arising in the safety assessment of nuclear power plants based on the experience of the authors (project managers) and to recomend possible improvements both for Spain and other developing countries are described. The first part will be devoted to the organizative aspects of the assessment and the second part will deal with different possible methods of technical assessment and its associated necesities. Finally, as a result of the previous considerations some recomendations in order to improve the technical assessment practice are proposed. (author)

Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

The Technical Committee Meeting on Procedures for Use of PSA for Optimizing Operational Limits and Conditions for Nuclear Power Plants was held in Barcelona from 20 to 23 September 1993 to serve as a forum for discussion of the development of methods and approaches for PSA applications. The meeting was co-sponsored by the IAEA and the Asco and Vandellos nuclear power plants in Spain and was attended by more than 85 participants from 23 countries. The 35 papers and presentations reflected the extent of activities in this area worldwide. Most of the papers discuss PSA application programmes and/or specific methods and approaches used. This TECDOC, which was prepared by the participants of the Technical Committee meeting, summarizes the insights gained from the papers and plenary discussions. It also presents the conclusions of the work of three working groups which discussed the advantages and limitations of specific aspects of PSA. It provides an up-to-date description of computerized tools for risk monitoring in used or under development in Member States. It is hoped that this report will be a useful source of information on PSA applications. Refs, figs, tabs.

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.

Technical advisory panel for the large acceptance spectrometer: Final report

International Nuclear Information System (INIS)

1989-01-01

The Technical Advisory Panel for the Large Acceptance Spectrometer met on November 17--19, 1988, at CEBAF to perform a second review of the status of this project. The charge to the Panel was ''to provide technical advice to the CEBAF directorate on the design, construction, cost, schedule, and implementation of the Large Acceptance Spectrometer.'' In this written report, an overview of the entire project is given. Specific comments on the major components, data handling and analysis, assembly and installation, and management are presented. The Panel's conclusions are contained in the Executive Summary at the beginning of the report

Structural Health and Prognostics Management for Offshore Wind Plants; Final Report of Sandia R&D Activities.

Energy Technology Data Exchange (ETDEWEB)

Griffith, Daniel Todd [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Wind Energy Technologies Dept.

2015-04-01

This final report is a compilation of resear ch efforts - funded by the US Department of Energy Wind and Water Power Technolog ies Office over a four-year period from FY11 through FY14. The goals of this re search program were to develop and evaluate technical innovati ons with promise for maxi mizing revenues and reducing levelized cost of energy (LCOE) for offs hore wind plants - more specifically the goals of the Structural H ealth and Prognostics Management (SHPM) program were to reduce O&M costs and increase energy capture through use of SHPM-based technologies. A technology roadmap was deve loped at the start of the project to guide the research efforts. This roadmap identified and outlined six major research thrust areas each having five stages of ma turity. Research was conducted in each of these thrust areas, as documented throughout this report, although a major focus was on development of damage detection strategi es for the most frequent blade damage conditions and damage mitigation and life-exte nsion strategies via changes in turbine operations (smart loads management). Th e work summarized in this compilation report is the product of the work of many researchers. A summary of the major findings, status of the SHPM Technology Ro admap and recommendations for future work are also provided.

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)

Green-House-Gas-Reduced Coal-and-Biomass-to-Liquid-Based Jet Fuel (GHGR-CBTL) Process - Final Technical report

Energy Technology Data Exchange (ETDEWEB)

Lux, Kenneth [Altex Technologies Corporation, Sunnyvale, CA (United States); Imam, Thamina [Altex Technologies Corporation, Sunnyvale, CA (United States); Chevanan, Nehru [Altex Technologies Corporation, Sunnyvale, CA (United States); Namazian, Mehdi [Altex Technologies Corporation, Sunnyvale, CA (United States); Wang, Xiaoxing [Pennsylvania State Univ., University Park, PA (United States); Song, Chunshan [Pennsylvania State Univ., University Park, PA (United States)

2017-11-03

This Final Technical Report describes the work and accomplishments of the project entitled, “Green-House-Gas-Reduced Coal-and-Biomass-to-Liquid-Based Jet Fuel (GHGR-CBTL) Process”. The main objective of the project was to raise the Technology Readiness Level (TRL) of the GHGR-CBTL fuel-production technology from TRL 4 to TRL 5 by producing a drop-in synthetic Jet Propellant 8 (JP-8) with a greenhouse-gas footprint less than or equal to petroleum-based JP-8 by utilizing mixtures of coal and biomass as the feedstock. The system utilizes the patented Altex fuel-production technology, which incorporates advanced catalysts developed by Pennsylvania State University. While the system was not fabricated and tested, major efforts were expended to design the 1-TPD and a full-scale plant. The system was designed, a Block-Flow Diagram (BFD), a Process-Flow Diagram (PFD), and Piping-and-Instrumentation Diagrams (P&IDs) were produced, a Bill of Materials (BOM) and associated spec sheets were produced, commercially available components were selected and procured, custom components were designed and fabricated, catalysts were developed and screened for performance, and permitting activities were conducted. Optimization tests for JP-8 production using C2 olefin as the feed were performed over a range of temperatures, pressures and WHSVs. Liquid yields of between 63 to 65% with 65% JP-8 fraction (41-42% JP-8 yield) at 50 psig were achieved. Life-Cycle Analysis (LCA) was performed by Argonne National Laboratory (ANL), and a GHGR-CBTL module was added to the Greenhouse gases, Regulated Emissions, and Energy use in Transportation (GREET®) model. Based upon the experimental results, the plant design was reconfigured for zero natural-gas imports and minimal electricity imports. The LCA analysis of the reconfigured process utilizing the GREET model showed that if the char from the process was utilized to produce combined heat and power (CHP) then a feed containing 23 wt% biomass and

System-Cost-Optimized Smart EVSE for Residential Application: Final Technical Report including Manufacturing Plan

Energy Technology Data Exchange (ETDEWEB)

Zhu, Charles [Delta Products, Triangle Park, NC (United States)

2015-05-15

In the 2nd quarter of 2012, a program was formally initiated at Delta Products to develop smart-grid-enabled Electric Vehicle Supply Equipment (EVSE) product for residential use. The project was funded in part by the U.S. Department of Energy (DOE), under award DE-OE0000590. Delta products was the prime contractor to DOE during the three year duration of the project. In addition to Delta Products, several additional supplier-partners were engaged in this research and development (R&D) program, including Detroit Edison DTE, Mercedes Benz Research and Development North America, and kVA. This report summarizes the program and describes the key research outcomes of the program. A technical history of the project activities is provided, which describes the key steps taken in the research and the findings made at successive stages in the multi-stage work. The evolution of an EVSE prototype system is described in detail, culminating in prototypes shipped to Department of Energy Laboratories for final qualification. After the program history is reviewed, the key attributes of the resulting EVSE are described in terms of functionality, performance, and cost. The results clearly demonstrate the ability of this EVSE to meet or exceed DOE's targets for this program, including: construction of a working product-intent prototype of a smart-grid-enabled EVSE, with suitable connectivity to grid management and home-energy management systems, revenue-grade metering, and related technical functions; and cost reduction of 50% or more compared to typical market priced EVSEs at the time of DOE's funding opportunity announcement (FOA), which was released in mid 2011. In addition to meeting all the program goals, the program was completed within the original budget and timeline established at the time of the award. The summary program budget and timeline, comparing plan versus actual values, is provided for reference, along with several supporting explanatory notes. Technical

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.

Solutions for cost effective assessment of software based instrumentation and control systems in nuclear power plants. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Implementation

International Nuclear Information System (INIS)

2002-12-01

The introduction of software based instrumentation and control (I and C) systems for use in nuclear power plants, mainly due to I and C modernization activities, has raised many issues of safety and economics. Many of these issues have been raised in the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) meetings and by other organizations, such as the OECD and the European Commission. One increasingly important issue is the need for engineering solutions to justify them for the cost effective assessment and deployment of software based I and C systems. To address this important issue, the IAEA put together the Co-ordinated Research Project (CRP) on Solutions for Cost Effective Assessments of Software based I and C Systems. The overall objective of the project is to facilitate the cost effective assessment of software based I and C systems in nuclear power plants. This is necessary to address obsolescence issues, to introduce new beneficial functionality, and to improve overall performance. The engineering solutions developed in this CRP will contribute to this overall objective. The objective of the CRP was reached through co-ordinated research and collected experience in the areas of project management; requirements specifications; use of software explicitly designed for nuclear applications, use of commercial off the shelf (COTS) products, generic pre-qualification of systems and components; safety and reliability enhancements; verification and validation; and licensing impact. This TECDOC is the result of the research and collected experience put together under this CRP. The CRP participants gave presentations on their work performed as part of this CRP at the various meetings of the group. The first meeting of the CRP was held in Vienna on 8-12 November 1999 in which the participants developed the objectives, scope, and outline of this report. The second meeting was held in Halden, Norway on 4-8 December 2000 and the

Final technical evaluation report for the proposed revised reclamation plan for the Atlas Corporation Moab Mill

International Nuclear Information System (INIS)

1997-03-01

This final Technical Evaluation Report (TER) summarizes the US Nuclear Regulatory Commission staff's review of Atlas Corporation's proposed reclamation plan for its uranium mill tailings pile near Moab, Utah. The proposed reclamation would allow Atlas to (1) reclaim the tailings pile for permanent disposal and long-term custodial care by a government agency in its current location on the Moab site, (2) prepare the site for closure, and (3) relinquish responsibility of the site after having its NRC license terminated. The NRC staff concludes that, subject to license conditions identified in the TER, the proposed reclamation plan meets the requirements identified in NRC regulations, which appear primarily in 10 CFR Part 40. 112 refs., 6 figs., 16 tabs

Flexible 75 kWel Stirling CHP-plant for bio-fuels with low emissions and a high fuel utilization. Final technical report

Energy Technology Data Exchange (ETDEWEB)

2011-07-01

The objective of the project ''Flexible 75 kWel Stirling CHP-plant for bio-fuels with low emissions and a high fuel utilization'' was to combine the Danish experiences with the Stirling engine and updraft gasification with the application of the FLOX gas burner technology for developing and demonstrating a flexible biomass-based small scale CHP plant with 75 kW electrical output, high power efficiency and low emissions. Further, the project has aimed at increasing the technology's reliability and decreasing the need for service. Also, the project has included the development of a control and communication system for unmanned start-up and operation of the plant. During the project the objective was altered and so the development of a new Stirling engine design was done on the 4-cylindred 35 kWe Stirling engine instead of the 8-cylindred 75 kWe Stirling engine. Focus has been on designing a more durable engine designed for easy and fast service. Cold test of the engine has been successful and now full-scale hot tests are to be performed. In the project Stirling DK has also in cooperation with project partner Danish gas Technology Centre developed the Stirling Engine with Diluted Oxidation (SEDIOX) concept which is a combustion technology based on the diluted oxidation principle. A trademark is obtained and also a patent application is filed and pending regarding the SEDIOX combustion chamber concept. All components for the Stirling gasification plant were produced and installed at Svanholm Estate. The plant consisted of one conventional combustion chamber and one SD3E-type Stirling engine. The plant was commissioned in June 2009 and 1,472 hours of operation and 43 MWh of electricity production was achieved before the plant was de-commissioned in February 2010 due to divergences between Svanholm Estate and Stirling DK. During operation the control system including remote access was tested thoroughly and with great success. The new overall

Final Technical Report - SciDAC Cooperative Agreement: Center for Extended Magnetohydrodynamic Modeling/ Transport and Dynamics in Torodial Fusion System

International Nuclear Information System (INIS)

Schanck, Dalton D.

2010-01-01

Final technical report for research performed by Professor Dalton D. Schnack on SciDAC Cooperative Agreement: Center for Extended MHD Modeling, DE-FC02-06ER54870, for the period 7/1/06 to 2/15/08. Principal results for this period are: 1. Development of a model for computational modeling for the primitive form of the extended MMD equations. This was reported as Phys. Plasmas 13, 058103 (2006). 2. Comparison between the NIMROD and M3D codes for simulation of the nonlinear sawtooth crash in the CDXU tokamak. This was reported in Phys. Plasmas 14, 056105 (2006). 3. Demonstration of 2-fluid and gyroviscous stabilization of interchange modes using computational extended MHD models. This was reported in Phys. Rev. Letters 101, 085005 (2008). Each of these publications is attached as an Appendix of this report. They should be consulted for technical details.

Direct fuel cell power plants: the final steps to commercialization

Science.gov (United States)

Glenn, Donald R.

Since the last paper presented at the Second Grove Fuel Cell Symposium, the Energy Research Corporation (ERC) has established two commercial subsidiaries, become a publically-held firm, expanded its facilities and has moved the direct fuel cell (DFC) technology and systems significantly closer to commercial readiness. The subsidiaries, the Fuel Cell Engineering Corporation (FCE) and Fuel Cell Manufacturing Corporation (FCMC) are perfecting their respective roles in the company's strategy to commercialize its DFC technology. FCE is the prime contractor for the Santa Clara Demonstration and is establishing the needed marketing, sales, engineering, and servicing functions. FCMC in addition to producing the stacks and stack modules for the Santa Clara demonstration plant is now upgrading its production capability and product yields, and retooling for the final stack scale-up for the commercial unit. ERC has built and operated the tallest and largest capacities-to-date carbonate fuel cell stacks as well as numerous short stacks. While most of these units were tested at ERC's Danbury, Connecticut (USA) R&D Center, others have been evaluated at other domestic and overseas facilities using a variety of fuels. ERC has supplied stacks to Elkraft and MTU for tests with natural gas, and RWE in Germany where coal-derived gas were used. Additional stack test activities have been performed by MELCO and Sanyo in Japan. Information from some of these activities is protected by ERC's license arrangements with these firms. However, permission for limited data releases will be requested to provide the Grove Conference with up-to-date results. Arguably the most dramatic demonstration of carbonate fuel cells in the utility-scale, 2 MW power plant demonstration unit, located in the City of Santa Clara, California. Construction of the unit's balance-of-plant (BOP) has been completed and the installed equipment has been operationally checked. Two of the four DFC stack sub-modules, each

Operating experiences with heat-exchanging components of a semi-technical pilot plant for steam gasification of coal using heat from HTR

International Nuclear Information System (INIS)

Kirchhoff, R.; Heek, K.H. van

1984-01-01

within the framework of the PNP- Project, a semi-technical plant for the development of a process of coal gasification by means of nuclear heat was operated. Here gasification is for the first time implemented in a fluidized bed using heat of an electrically heated helium cycle at pressure up to 40 bar and temperatures normal for HTR. The plant serves for testing and developing various components as immersion heater, insulations, dosing devices, and for compiling sound data for further planning

Technical development to remove radionuclides from agricultural soils by plants (Joint research)

International Nuclear Information System (INIS)

Yamada, Satoshi; Sakoda, Akihiro; Ishimori, Yu

2012-07-01

Tottori University and Japan Atomic Energy Agency started a joint study to develop an environmental remediation technique for agricultural soil. Nine plants were water-cultured and examined for screening. A few were selected as candidates for demonstrations in fields. Preselected plants were mainly halophytes that can specifically absorb more Na than K, and others like sunflower demonstrated for domestic large-scale tests. Easily cultivated and harvested plants without harmful effect on new agriculture were also considered. Seedings prepared were first grown for a certain term. Additive-free, 133 Cs and 88 Sr groups, which are both stable isotopes, were then made. Cs (CsCl) and Sr (SrCl 2 ·6H 2 O) contents in cultures were 1.6836 mg/L (0.01 mM) and 266.62 mg/L (1 mM), respectively. Stems, leaves and roots were harvested, in principle, two weeks after the addition, to measure K, Ca, Mg, Sr and Cs concentrations in them. Considering the examination period, a content rate (i.e. element amount per dry sample weight) was regarded as an index. It was concluded that New Zealand spinach and ice plant were most adequate for removing contaminants from surface soil. The two accumulate Cs and Sr mostly in the shoots, are prostrate, and spread the roots shallowly. For valid application, growth-phase dependences of absorption and distribution, growth property and root distribution should be elucidated. Plants that meet the present purpose are ones that specifically absorb object substances, or that show normal absorption but high removal rate per area due to the large bulk size. The latter view also needs to be evaluated when the field test is conducted, since developing stages of the plants used in the present work were not correspondent. Finally, the application study plan was developed based on the screening test results. (author)