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Sample records for plants final technical

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Saurwein, John

    2011-07-15

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

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

    International Nuclear Information System (INIS)

    Saurwein, J.

    2011-01-01

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

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

    International Nuclear Information System (INIS)

    1978-05-01

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

  5. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Glasser, Alan H. [Fusion Theory and Computation Inc., Kingston, WA (United States)

    2018-02-02

    Final technical report on DE-SC0016106. This is the final technical report for a portion of the multi-institutional CEMM project. This report is centered around 3 publications and a seminar presentation, which have been submitted to E-Link.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-03-31

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

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  8. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    John Ross

    2003-04-30

    The Final Technical Report summarizes research accomplishments and Publications in the period of 5/1/99 to 4/30/03 done on the grant. Extensive progress was made in the period covered by this report in the areas of chemical kinetics of non-linear systems; spatial structures, reaction - diffusion systems, and thermodynamic and stochastic theory of electrochemical and general systems.

  9. 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.

  10. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Grogan, Dylan C. P.

    2013-08-15

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

  12. 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...

  13. 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.

  14. 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.

  15. 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

  16. 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.

  17. 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

  18. 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.

  19. CEEM Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Bowers, John [Univ. of California, Santa Barbara, CA (United States)

    2014-11-26

    whom was a member of CEEM), LEDs already have a large societal impact in both developed (leading to large energy savings) and developing countries (bringing light where there is no electrical grid). The improvements in efficiency sought after in the CEEM project are key to a further impact of solid state lighting by LEDs with a projected doubling in efficiency by year 2020. Direct generation of electricity from heat has enormous promise for beneficial use of waste heat. But practical power generation directly from heat requires understanding and development of new and improved materials that will be more efficient and rugged than today’s thermoelectric materials. To accomplish this goal CEEM has synthesized five distinct and promising new classes of thermoelectric materials: (a) nanoparticle arrays that are effective in maximizing electric power generation and reducing detrimental loss of heat; (b) nitride and (c) oxide thermal electric materials that are effective at high temperatures where much beneficial heat is available; (d) arrays of silicon nano-wires that integrate thermal electricity generation into silicon-based electronics and materials; and (e) chemically synthesized nanostructured compounds that are cost effective, earth abundant, and environmentally friendly. The further development of these thermoelectric sources of electricity could have revolutionary impact for society in the recovery of waste heat from sources such as power plants and automobile exhaust, where there could be significant associated energy saving. It could even, in the future, provide disruptive alternatives and replacements for today’s internal combustion engines and could enable improved all-electric propulsion by the heat from shipboard nuclear reactors. The High Efficiency Multi-junction Photovoltaics task was a UCSB/NREL collaboration which bonded sub-cells from two different compound semiconductors material systems to make high efficiency multijunction solar cells for

  20. 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

  1. 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

  2. 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.

  3. 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.

  4. Final Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    J.Y. Hwang; R.C. Greenlund

    2002-12-31

    Michigan Technological University has demonstrated major inroads in establishing the viability of utilizing aluminum smelting by-product waste materials in lightweight concrete product applications. The research identified key elements of producing various forms of lightweight concrete products through utilizing various procedures and mixture components with the by-product materials. A process was developed through pilot plant testing that results in additional aluminum recovery at finer sizes, a clean returnable salt product through spray drying technology, and a low-salt-content oxide product with enough aluminum metal content that it can be used to form lightweight cementitious mixtures. Having three distinct products aids in generating favorable process economics. Revenue projections from aluminum recovery and salt recovery are enough to cover processing costs and create a cost-free oxide product to market for lightweight concrete applications. This supply side commercialization strategy offers aluminum by-product recyclers a potentially no cost product, which has been demonstrated through this project to create desirable and marketable lightweight concrete products of various forms. Environmental benefits to the public are tremendous. At best, all dross and salt cake materials have the potential to be completely recycled and utilized. At worst, disposal sites would see a reduced amount of material: a post processed oxide product with little salt and no hydrogen sulfide or ammonia gas generating capability, which, if isolated from high alkali conditions, would pose no reactivity concerns. The US aluminum industry has historically, along with the steel industry, been a leader in recycling metal. The findings from this project, increased metal recovery, improved salt recycling, and demonstrated end uses for oxide residues, will go a long way in helping the aluminum industry obtain 100% material utilization and zero discharge.

  5. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Sara Bergan, Executive Director; Brendan Jordan, Program Manager; Subcontractors as listed on the report.

    2007-06-06

    can be done in such a way that also maximizes or improves upon conservation and other environmental goals (in some cases even when compared to idled land); Switchgrass and big bluestem work well together in simple mixture plots where big bluestem fills in around the switchgrass which alone grows in bunches and leaves patches of bare soil open and susceptible to erosion; Longer-term studies in the northern plains may also find that every other year harvest schemes produce as much biomass averaged over the years as annual harvests; Grasses can be grown for between $23 and $54/ton in the northern plains at production rates between 3 and 5 tons/acre; Land costs, yields, and harvest frequency are the largest determining factors in the farm scale economics. Without any land rent offset or incentive for production, and with annual harvesting, grass production is likely to be around $35/ton in the northern plains (farm gate); Average transportation costs range from $3 to $10/ton delivered to the plant gate. Average distance from the plant is the biggest factor - $3/ton at 10 miles, $10/ton at 50 miles; There is a substantial penalty paid on a per unit of energy produced basis when one converts grasses to bio-oil, but the bio-oil can then compete in higher priced fuel markets whereas grasses alone compete directly with relatively cheap coal; Bio oil or modified bio-oil (without the HA or other chemical fraction) is a suitable fuel for boiler and combustion turbines that would otherwise use residual fuel oil or number 2 diesel; Ensyn has already commercialized the use of HA in smokey flavorants for the food industry but that market is rather small. HA, however, is also found to be a suitable replacement for the much larger US market for ethanolamines and ethalyne oxides that are used as dispersants; Unless crude oil prices rise, the highest and best use of grass based bio-oil is primarily as a direct fuel. As prices rise, HA, phenol and other chemical fractions may become more

  6. 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

  7. Final Technical Report on Quantifying Dependability Attributes of Software Based Safety Critical Instrumentation and Control Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Smidts, Carol; Huang, Fuqun; Li, Boyuan; Li, Xiang

    2016-01-01

    With the current transition from analog to digital instrumentation and control systems in nuclear power plants, the number and variety of software-based systems have significantly increased. The sophisticated nature and increasing complexity of software raises trust in these systems as a significant challenge. The trust placed in a software system is typically termed software dependability. Software dependability analysis faces uncommon challenges since software systems' characteristics differ from those of hardware systems. The lack of systematic science-based methods for quantifying the dependability attributes in software-based instrumentation as well as control systems in safety critical applications has proved itself to be a significant inhibitor to the expanded use of modern digital technology in the nuclear industry. Dependability refers to the ability of a system to deliver a service that can be trusted. Dependability is commonly considered as a general concept that encompasses different attributes, e.g., reliability, safety, security, availability and maintainability. Dependability research has progressed significantly over the last few decades. For example, various assessment models and/or design approaches have been proposed for software reliability, software availability and software maintainability. Advances have also been made to integrate multiple dependability attributes, e.g., integrating security with other dependability attributes, measuring availability and maintainability, modeling reliability and availability, quantifying reliability and security, exploring the dependencies between security and safety and developing integrated analysis models. However, there is still a lack of understanding of the dependencies between various dependability attributes as a whole and of how such dependencies are formed. To address the need for quantification and give a more objective basis to the review process -- therefore reducing regulatory uncertainty

  8. Final Technical Report on Quantifying Dependability Attributes of Software Based Safety Critical Instrumentation and Control Systems in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Smidts, Carol [The Ohio State Univ., Columbus, OH (United States); Huang, Funqun [The Ohio State Univ., Columbus, OH (United States); Li, Boyuan [The Ohio State Univ., Columbus, OH (United States); Li, Xiang [The Ohio State Univ., Columbus, OH (United States)

    2016-03-25

    With the current transition from analog to digital instrumentation and control systems in nuclear power plants, the number and variety of software-based systems have significantly increased. The sophisticated nature and increasing complexity of software raises trust in these systems as a significant challenge. The trust placed in a software system is typically termed software dependability. Software dependability analysis faces uncommon challenges since software systems’ characteristics differ from those of hardware systems. The lack of systematic science-based methods for quantifying the dependability attributes in software-based instrumentation as well as control systems in safety critical applications has proved itself to be a significant inhibitor to the expanded use of modern digital technology in the nuclear industry. Dependability refers to the ability of a system to deliver a service that can be trusted. Dependability is commonly considered as a general concept that encompasses different attributes, e.g., reliability, safety, security, availability and maintainability. Dependability research has progressed significantly over the last few decades. For example, various assessment models and/or design approaches have been proposed for software reliability, software availability and software maintainability. Advances have also been made to integrate multiple dependability attributes, e.g., integrating security with other dependability attributes, measuring availability and maintainability, modeling reliability and availability, quantifying reliability and security, exploring the dependencies between security and safety and developing integrated analysis models. However, there is still a lack of understanding of the dependencies between various dependability attributes as a whole and of how such dependencies are formed. To address the need for quantification and give a more objective basis to the review process -- therefore reducing regulatory uncertainty

  9. 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.

  10. 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

  11. Final Technical Report: Using Solid Particles as Heat Transfer Fluid for use in Concentrating Solar Power (CSP) Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lattanzi, Aaron [Univ. of Colorado, Boulder, CO (United States); Hrenya, Christine [Univ. of Colorado, Boulder, CO (United States)

    2016-03-31

    In today’s industrial economy, energy consumption has never been higher. Over the last 15 years the US alone has consumed an average of nearly 100 quadrillion BTUs per year [21]. A need for clean and renewable energy sources has become quite apparent. The SunShot Initiative is an ambitious effort taken on by the United States Department of Energy that targets the development of solar energy that is cost-competitive with other methods for generating electricity. Specifically, this work is concerned with the development of concentrating solar power plants (CSPs) with granular media as the heat transfer fluid (HTF) from the solar receiver. Unfortunately, the prediction of heat transfer in multiphase flows is not well understood. For this reason, our aim is to fundamentally advance the understanding of multiphase heat transfer, particularly in gas-solid flows, while providing quantitative input for the design of a near black body receiver (NBB) that uses solid grains (like sand) as the HTF. Over the course of this three-year project, a wide variety of contributions have been made to advance the state-of-the art description for non-radiative heat transfer in dense, gas-solid systems. Comparisons between a state-of-the-art continuum heat transfer model and discrete element method (DEM) simulations have been drawn. The results of these comparisons brought to light the limitations of the continuum model due to inherent assumptions in its derivation. A new continuum model was then developed for heat transfer at a solid boundary by rigorously accounting for the most dominant non-radiative heat transfer mechanism (particle-fluid-wall conduction). The new model is shown to be in excellent agreement with DEM data and captures the dependence of heat transfer on particle size, a dependency that previous continuum models were not capable of. DEM and the new continuum model were then employed to model heat transfer in a variety of receiver geometries. The results provided crucial

  12. 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

  13. 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.

  14. Solarthermische Kraftwerksentwicklung (STKE) - development of solar thermal power plants. Technical aspects. Final report; Solarthermische Kraftwerksentwicklung (STKE). Technischer Teil. Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Pitz-Paal, R.

    2000-01-01

    This project started on 1 January 1996 with DM 3.7 million funds from the BMFT. Originally scheduled for three years, it was extended by a further 11 months for various reasons. Its intention was to reduce the cost of future solar thermal power plants. Particular emphasis was given to the parabolic trough technology asit is closest to commercialisation. Three strategies were involved: 1. Further development and qualification of components for the parabolic trough collector (WG PAREX); 2. Development of instruments for measuring radiation flux distribution in parabolic trough collectors (WG PARMESAN); 3. Development, verification and application of software tools for analysing the complex dynamic response of solar thermal power plants (WG SISTA). [German] Das hier dargestellte Projekt begann am 1.1.1996 und wurde vom Bundesministerium fuer Forschung und Technologie (BMFT) mit etwa 3,7 Mio. DM gefoerdert. Es hatte eine geplante Laufzeit von drei Jahren, wurde aber aufgrund von unterschiedlichen Verzoegerungen (Mitarbeiterwechsel, Defekte an Versuchsanlagen) kostenneutral um 11 Monate verlaengert. Gesamtziel des Projekts war es, zur Kostensenkung bei zukuenftigen solarthermischen Kraftwerken beizutragen. Dabei stand insbesondere die Parabolrinnentechnik im Vordergrund, da sie im Vergleich zu anderen solarthermischen Technologien einer weiteren kommerziellen Vermarktung derzeit am naechsten steht. Es wurden drei Schwerpunkte verfolgt: 1. Die Weiterentwicklung und Qualifizierung von Komponenten fuer den Parabolrinnenkollektor (Arbeitspaket 'Parabolrinnenexperimente', kurz PAREX) 2. Die Entwicklung von Messtechnik zur Bestimmung von Strahlungsflussverteilung bei Parabolrinnenkollektoren (AP 'Parabolrinnen-Messanlage', kurz PARMESAN) 3. Die Erstellung, Verifikation und Anwendung von Softwarewerkzeugen zur Analyse des komplexen dynamischen Verhaltens von solarthermischen Kraftwerken (AP 'Simulation solarthermischer Anlagen', kurz SISTA) (orig.)

  15. 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.

  16. IRIS Final Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    M. D. Carelli

    2003-11-03

    OAK-B135 This NERI project, originally started as the Secure Transportable Autonomous Light Water Reactor (STAR-LW) and currently known as the International Reactor Innovative and Secure (IRIS) project, had the objective of investigating a novel type of water-cooled reactor to satisfy the Generation IV goals: fuel cycle sustainability, enhanced reliability and safety, and improved economics. The research objectives over the three-year (1999-2002) program were as follows: First year: Assess various design alternatives and establish main characteristics of a point design; Second year: Perform feasibility and engineering assessment of the selected design solutions; Third year: Complete reactor design and performance evaluation, including cost assessment These objectives were fully attained and actually they served to launch IRIS as a full fledged project for eventual commercial deployment. The program did not terminate in 2002 at the end of the NERI program, and has just entered in its fifth year. This has been made possible by the IRIS project participants which have grown from the original four member, two-countries team to the current twenty members, nine countries consortium. All the consortium members work under their own funding and it is estimated that the value of their in-kind contributions over the life of the project has been of the order of $30M. Currently, approximately 100 people worldwide are involved in the project. A very important constituency of the IRIS project is the academia: 7 universities from four countries are members of the consortium and five more US universities are associated via parallel NERI programs. To date, 97 students have worked or are working on IRIS; 59 IRIS-related graduate theses have been prepared or are in preparation, and 41 of these students have already graduated with M.S. (33) or Ph.D. (8) degrees. This ''final'' report (final only as far as the NERI program is concerned) summarizes the work performed

  17. Santa Barbara Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Hacker, Angela; Hansen, Sherman; Watkins, Ashley

    2013-11-30

    This report serves as the Final Report for Santa Barbara County’s Energy Efficiency and Conservation Block Grant (EECBG) BetterBuildings Neighborhood Program (BBNP) award from the U.S. Department of Energy (DOE). This report explains how DOE BBNP funding was invested to develop robust program infrastructure designed to help property owners complete energy improvements, thereby generating substantial outcomes for the local environment and economy. It provides an overview of program development and design within the grant period, program accomplishments and challenges to date, and a plan for the future sustainability of emPower, the County’s innovative clean energy and building efficiency program. During the grant period, Santa Barbara County’s emPower program primarily targeted 32,000 owner occupied, single family, detached residential homes over 25 years old within the County. In order to help these homeowners and their contractors overcome market barriers to completing residential energy improvements, the program developed and promoted six voluntary, market-based service areas: 1) low cost residential financing (loan loss reserve with two local credit unions), 2) residential rebates, 3) local customer service, 4) expert energy advising, 5) workforce development and training, and 6) marketing, education and outreach. The main goals of the program were to lower building energy use, create jobs and develop a lasting regional building performance market. These services have generated important early outcomes and lessons after the program’s first two years in service. The DOE BBNP funding was extended through October 2014 to enable Santa Barbara County to generate continued outcomes. In fact, funding related to residential financing remains wholly available for the foreseeable future to continue offering Home Upgrade Loans to approximately 1,300 homeowners. The County’s investment of DOE BBNP funding was used to build a lasting, effective, and innovative

  18. Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Reeder, Richard [Stony Brook Univ., NY (United States); Phillips, Brian [Stony Brook Univ., NY (United States)

    2017-10-18

    A variety of calcifying organisms produce a transient or metastable amorphous calcium carbonate (ACC) precursor phase that is assembled and subsequently transformed into a crystalline biomineral, typically calcite or aragonite. The complex shapes, hierarchical structures, and unique physical properties of the biominerals that result from this calcification pathway have stimulated interest in adapting these concepts for the design and creation of bio-inspired functional materials in the laboratory. ACC also forms as a reactive precursor in diverse inorganic systems and is likely to play a much broader role in calcium carbonate formation. Knowledge of the structure, composition, and behavior of this metastable phase is critical for establishing a structural and mechanistic framework for calcium carbonate formation and its role in biogeochemical processes, including carbon cycling. Minor additives, such as magnesium, phosphorus, and organic macromolecules, are known to play important roles in controlling ACC stability, transformation kinetics, and selection of final crystalline polymorph. Molecular water also occurs in many types of ACC and is thought to play a structural role in its stability and transformation behavior. One of the major challenges that remain unresolved is identification of the structural basis for the role of these minor additives and molecular water. The absence of long-range order in ACC, and other amorphous phases, has posed a challenge for study by techniques commonly used for crystalline solids. Preliminary studies in our group show that the combination of two techniques, synchrotron X-ray-based pair distribution function (PDF) analysis and nuclear magnetic resonance (NMR) spectroscopy can provide entirely new insight to structural properties of synthetic ACC over length scales that are most relevant for understanding its transformation properties. Building on preliminary experiments, we propose a systematic study of synthesis, structure, and

  19. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

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

  20. 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

  1. 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

  2. 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

  3. Technical evaluation report of the Fort St. Vrain final draft upgraded technical specifications

    International Nuclear Information System (INIS)

    Kimura, C.Y.

    1989-01-01

    This report is a technical evaluation of the final draft of the Fort St. Vrain (FSV) Upgraded Technical Specifications (UT/S) as issued by Public Service of Colorado (PSC) on May 27, 1988 with subsequent supplemental updates issued on June 15, 1988 and August 5, 1988. It has been compared for consistency, and safety conservatism with the Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR), the FSV Safety Evaluation Report (SER), the Facility Operating License, DPR-34, and all amendments to the Facility Operating License issued as of June 1, 1988, and Appendix A to the Operating License DPR-34, Technical Specifications. Because of the age of the plant, no supplements to the Fort St. Vrain SER have been issued since the original SER was not issued as a WASH or a NUREG report. This made it necessary to review all amendments to the Facility Operating License since they would contain the safety evaluations done to support changes to the Facility Operating License. The upgraded Fort St. Vrain Technical Specifications were also broadly compared with the latest Westinghouse Standard Technical Specifications (WSTS) to assure that what was proposed for Fort St. Vrain was consistent with the latest NRC staff practices for standard technical specifications

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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

    International Nuclear Information System (INIS)

    Wolff, Holger

    2016-09-01

    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 + 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 + 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.

  10. 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

  11. 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)

  12. 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

  13. 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

  14. Guidelines to implement the license renewal technical requirements of 10CFR54 for integrated plant assessments and time-limited aging analyses. Final report

    International Nuclear Information System (INIS)

    Lehnert, G.; Philpot, L.

    1995-11-01

    This report documents the initial results of the Nuclear Energy Institute License Renewal Implementation Guideline Task Force over the period August 1994 to July 1995 to develop guidance for complying with technical requirements of 10CFR54. The report also provided a starting point for the development of NEI 95-10, ''Industry Guideline for Implementing the Requirements of 10CCR54-The License Renewal Rule''. Information in this document can be used by utilities to prepare the technical material needed in an application for license renewal (LR) of a nuclear power unit. This guideline provides methods for identifying systems, structures, and components (SSCs) and their intended functions within the scope of license renewal. It identifies structures and components (SCs) requiring aging management review and methods for performing the aging management review. The guideline provides a process for identifying and evaluating time-limited aging analyses

  15. Manpower development for safe operation of nuclear power plant. China. Revision of final safety analysis report. Activity: 5.1.3-Task-08. Technical report

    International Nuclear Information System (INIS)

    Almeida, C.; Elias, D.

    1994-01-01

    The objectives of this mission included providing assistance for the revision of the FSAR including: national practices, administrative procedures, required staffing level, other resources, planning, scheduling, content, and organization of the revision. Activities included several days of lectures regarding worldwide practices including the United States and Commonwealth Edison Company (ComEd), interaction with Chinese counterparts re. their FSAR and Technical Specification revision and two visits to the Qin Shan NPP

  16. Audit of Wolf Creek Generating Station, Unit 1 technical specifications. Final technical evaluation report

    International Nuclear Information System (INIS)

    Stromberg, H.M.

    1985-07-01

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

  17. 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)

  18. Movement of metal cations through the soil to the plant root membrane. Final technical report, June 1, 1966--November 30, 1978

    International Nuclear Information System (INIS)

    Barber, S.A.

    1978-11-01

    This project concerns metal cation flux through the soil and into the plant. Some highlights resulting from this research are as follows. Effect of soil properties on relative adsorption of Ca, Sr, K, Rb, and Cs by soil was measured. A theoretically developed concept explained differences between Ca and Sr adsorption on inorganic and organic exchange sites. A convenient method was developed to characterize cation absorption kinetics of intact plant roots. Use of this method showed genotypic variation in effect of ion concentration on influx. Corn absorbed Ca and Sr and K and Rb indiscriminantly. A method, using Ca/Sr and K/Rb ratio of ion influx into the plant, was developed to determine the source of these ions absorbed from the soil. Uptake of these ions from soil by corn was in the ratio on exchange sites rather than that in solution. The method was also used to compare uptake of chelated with ionized cations. A simulation model was developed that described ion flux from the soil into the plant. Ten independently measured soil and plant parameters were used. A computer program was prepared to calculate uptake with time. The model was verified in both growth chamber and field experiments

  19. 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

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

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.

    1985-06-01

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

  1. Virginia Solar Pathways Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Katharine; Cosby, Sarah

    2018-03-28

    This Report provides a technical review of the final results of a funding award to Virginia Electric and Power Company (Dominion Energy Virginia (DEV) or the Company) for a project under the U.S. Department of Energy’s Solar Energy Technologies Office. The three-year project was formally known as the Virginia Solar Pathways Project (VSPP or the Project). The purpose of the VSPP was to develop a collaborative utility-administered solar strategy (Solar Strategy) for DEV’s service territory in the Commonwealth that could serve as a replicable model for other states with similar policy environments. The U.S. Department of Energy (DOE) funding award enabled DEV to take a focused approach to developing the Solar Strategy for its Virginia service territory. The structure and funding from the DOE award also facilitated valuable input from a formal stakeholder team convened to serve as advisors (Advisory Team) to the VSPP and contribute their perspectives and expertise to both the analysis and strategy development aspects of the Project. The development of the Solar Strategy involved three main goals: • Establish a policy and program framework that would integrate existing solar programs with new options appropriate for the Commonwealth’s policy environment and broader economic development objectives; • Promote wider deployment of solar within a low retail electric rate environment; and • Serve as a sustainable, utility-administered solar model that could be replicated in other states with similar policy environments, including, but not limited to, the entire Southeast region. In support of the VSPP goals, the Project Team commissioned four studies to support the Solar Strategy development. Two studies, completed by Navigant Consulting, focused on the integration of solar into the electric grid. The first solar integration study focused on integration of solar into the distribution grid where the utility system directly connects to and serves end-use customers

  2. 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.

  3. 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

  4. Technical concept of accelerator plants

    International Nuclear Information System (INIS)

    Arx, A. von

    1973-01-01

    A description is given of the 45-MeV betatron of the so-called asklepitron 45 developed by BBC. The constructional details are particularly gone into which meet the requirements for optimum apparative radiation protection. These specifications consist in a least possible radiation outside the signal field, smallest contamination of the applied useful radiation, a reliable monitoring system and time stability of the beam bundle. The realization of these requirements is explained by means of the way of the magnet construction of the stabilization of the excitation current and of the emission current and control equipment for optimum injection time and radiation energy. Beam aperture and radiation compensation as well as the monitor system for X-rays and electron radiation are described. Finally, the operational safety and available automation are gone into. (ORU/LH) [de

  5. 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

  6. 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

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

    International Nuclear Information System (INIS)

    1995-04-01

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

  8. Final Technical Report: Increasing Prediction Accuracy.

    Energy Technology Data Exchange (ETDEWEB)

    King, Bruce Hardison [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hansen, Clifford [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    PV performance models are used to quantify the value of PV plants in a given location. They combine the performance characteristics of the system, the measured or predicted irradiance and weather at a site, and the system configuration and design into a prediction of the amount of energy that will be produced by a PV system. These predictions must be as accurate as possible in order for finance charges to be minimized. Higher accuracy equals lower project risk. The Increasing Prediction Accuracy project at Sandia focuses on quantifying and reducing uncertainties in PV system performance models.

  9. 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.

  10. DOE Utility Matching Program Final Technical Report

    International Nuclear Information System (INIS)

    Haghighat, Alireza

    2002-01-01

    This is the Final report for the DOE Match Grant (DE-FG02-99NE38163) awarded to the Nuclear and Radiological Engineering (NRE) Department, University of Florida, for the period of September 1999 to January 2002. This grant has been instrumental for maintaining high-quality graduate and undergraduate education at the NRE department. The grant has been used for supporting student entry and retention and for upgrading nuclear educational facilities, nuclear instrumentation, computer facilities, and computer codes to better enable the incorporation of experimental experiences and computer simulations related to advanced light water fission reactor engineering and other advanced reactor concepts into the nuclear engineering course curricula

  11. High tracking resolution detectors. Final Technical Report

    International Nuclear Information System (INIS)

    Vasile, Stefan; Li, Zheng

    2010-01-01

    High-resolution tracking detectors based on Active Pixel Sensor (APS) have been valuable tools in Nuclear Physics and High-Energy Physics research, and have contributed to major discoveries. Their integration time, radiation length and readout rate is a limiting factor for the planed luminosity upgrades in nuclear and high-energy physics collider-based experiments. The goal of this program was to demonstrate and develop high-gain, high-resolution tracking detector arrays with faster readout, and shorter radiation length than APS arrays. These arrays may operate as direct charged particle detectors or as readouts of high resolution scintillating fiber arrays. During this program, we developed in CMOS large, high-resolution pixel sensor arrays with integrated readout, and reset at pixel level. Their intrinsic gain, high immunity to surface and moisture damage, will allow operating these detectors with minimal packaging/passivation requirements and will result in radiation length superior to APS. In Phase I, we designed and fabricated arrays with calorimetric output capable of sub-pixel resolution and sub-microsecond readout rate. The technical effort was dedicated to detector and readout structure development, performance verification, as well as to radiation damage and damage annealing.

  12. 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

  13. 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

  14. 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

  15. 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.

  16. 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

  17. 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.

  18. 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

  19. Plus energy house. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Yde, L.

    1996-05-01

    A description of a demonstration project, located near Viborg in Denmark, involving a 400 m{sup 2} house with low energy consumption which has a 200 m{sup 2} living/working area, a 240 m{sup 2} mobile insulated glass facade and a solar greenhouse of 200 m{sup 2} which in addition to plant production can be used for recreational purposes. Humidity in the greenhouse is regulated by heat pumps condensing the water-laden air and thus producing hot water for space heating. The heat pumps maintain a 70% relative humidity in the greenhouse and surplus heat to the amount of 300 kWh/m{sup 2} of glass facade area is produced annually. Excess heat to the amount of 75.000 kWh is available for space heating in adjoining houses. The glazed roof of the house and greenhouse is constructed of two layers of tempered glass. The 20 cm space between the layers, when filled with polystyrene beads, provides thermal insulation equal to that of traditionally insulated outer house-walls. The beads can be sucked in and out of the roof space and can also be used for shading during the summer. It is concluded that the house (400 m{sup 2}) consumes the same quantity of energy as houses of a similar size and at the same time produces 300 kWh/m{sup 2} p.a. with the glass south facade, corresponding to what a solar collector produces per m{sup 2}. (AB)

  20. Final Technical Report - DE-EE0003542

    Energy Technology Data Exchange (ETDEWEB)

    Haley, James D

    2013-03-31

    Wind has provided energy for thousands of years: some of the earliest windmill engineering designs date back to ancient Babylonia and India where wind would be used as a source of irrigation. Today, wind is the quickest growing resource in Americas expanding energy infrastructure. However, to continue to positively diversify Americas energy portfolio and further reduce the countrys reliance of foreign oil, the industry must grow substantially over the next two decades in both turbine installations and skilled industrial manpower to support. The wind sector is still an emergent industry requiring maturation and development of its labor force: dedicated training is needed to provide the hard and soft skills to support the increasingly complex wind turbine generators as the technology evolves. Furthermore, the American workforce is facing a steep decline in available labor resources as the baby boomer generation enters retirement age. It is therefore vital that a process is quickly created for supporting the next generation of wind technicians. However, the manpower growth must incorporate three key components. First, the safety and technical training curriculum must be standardized across the industry - current wind educational programs are disparate and dedicated standardization programs must be further refined and implemented. Second, it is essential that the wind sector avoid disrupting other energy production industries by cannibalizing workers, which would indirectly affect the rest of Americas energy portfolio. The future wind workforce must be created organically utilizing either young people entering the workforce or train personnel emerging from careers outside of energy production. Third, the training must be quick and efficient as large amounts of wind turbines are being erected each year and this growth is expected to continue until at least 2035. One source that matches these three requirements is personnel transitioning from military service to the

  1. VGB-requirements regarding technical data for power plants

    International Nuclear Information System (INIS)

    Richnow, Joerg

    2009-01-01

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

  2. 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

  3. Solar Living House Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Walters, Bradley [Univ. of Florida, Gainesville, FL (United States)

    2017-03-09

    permanent site constructions. This project suggest that high-performance buildings can be realized for more modest budgets. Public Benefits: Work on the Solar Living House and Solar Decathlon 2015 offered our student team unparalleled learning opportunities. Because of the duration of the project, a number of students participated at different points in their education, from first year undergraduates all the way through to advanced graduate students. The opportunity for collaboration with students and faculty from the National University of Singapore was also extraordinary, allowing for a sharing of technical knowledge and cultural exchange. The wider public has benefited from this work as its findings have been shared through public presentations and publications. It serves as a useful stepping stone along the path towards affordable, high-performance buildings.

  4. 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.

  5. 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

  6. Final Technical Report 09 LW 112

    Energy Technology Data Exchange (ETDEWEB)

    Lenhoff, R J

    2010-11-28

    Since the development of new antibiotics is out-paced by the emergence of bacterial resistance to existing antibiotics, it is crucial to understand the genetic mechanisms underlying resistance existing antibiotics. At the center of this mystery is a poorly understood phenomenon, heteroresistance: the coexistence of multiple subpopulations with varying degrees of antibiotic resistance. A better understanding of the fundamental basis of heteroresistance could result in sorely needed breakthroughs in treatment options. This project proposed to leverage a novel microfluidic (microchemostat) technology to probe the heteroresistance phenomenon in bacteria, with the aim of restoring the efficacy of existing {beta}-lactam antibiotics. The clinically important bacteria Methicillin Resistant S. aureus (MRSA) was used as the test case of bacteria that exhibits antibiotic heteroresistance. MRSA is difficult to treat because it is resistant to all {beta}-lactam antibiotics, as well as other classes of antimicrobials. Whereas {beta}-lactams such as methicillin and oxacillin are the preferred antibiotics to treat S. aureus infections due to their efficacy and low side effects, accurate determination and use of oxacillin/methicillin dosage is hampered by heteroresistance. In fact, invasive MRSA infections now account for about 95,000 deaths per year, a number that exceeds the deaths due to either influenza or HIV (12). In some MRSA strains, two subpopulations of cells may coexist: both populations carry the mecA gene that confers resistance, but mecA is differentially expressed so that only a small number of cells are observed during in vitro testing. Why this occurs is not understood. Prior experiments have sought to explain this phenomenon with conflicting results, with technology being the primary barrier to test the system sufficiently. This is the final report on work accomplished under the Lab-wide LDRD project 09-LW-112. This project was awarded to Frederick Balagadde who

  7. 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.

  8. 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.

  9. 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

  10. Automation of technical specification monitoring for nuclear power plants

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  11. 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

  12. 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

  13. 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.

  14. 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

  15. 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.

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

    International Nuclear Information System (INIS)

    See, Kok Fong; Coelli, Tim

    2012-01-01

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

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. Final Technical Report for the Period September 2002 through September 2005; H2-MHR Pre-Conceptual Design Report: SI-Based Plant; H2-MHR Pre-Conceptual Design Report: HTE-Based Plant

    Energy Technology Data Exchange (ETDEWEB)

    M. Richards; A. Shenoy; L. Brown; R. Buckingham; E. Harvego; K. Peddicord; M. Reza; J. Coupey

    2006-04-19

    For electricity and hydrogen production, an advanced reactor technology receiving considerable international interest is a modular, passively-safe version of the high-temperature, gas-cooled reactor, known in the U.S. as the Modular Helium Reactor (MHR), which operates at a power level of 600 MW(t). For electricity production, the MHR operates with an outlet helium temperature of 850 C to drive a direct, Brayton-cycle power-conversion system with a thermal-to-electrical conversion efficiency of 48 percent. This concept is referred to as the Gas Turbine MHR (GT-MHR). For hydrogen production, both electricity and process heat from the MHR are used to produce hydrogen. This concept is referred to as the H2-MHR. This report provides pre-conceptual design descriptions of full-scale, nth-of-a-kind H2 MHR plants based on thermochemical water splitting using the Sulfur-Iodine process and High-Temperature Electrolysis.

  2. 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

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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)

  10. 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.

  11. 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)

  12. 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.

  13. 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

  14. 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.

  15. 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

  16. 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...

  17. 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...

  18. 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.)

  19. 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...

  20. 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...

  1. 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...

  2. 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

  3. 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

  4. NTRCI Legacy Engine Research and Development Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Smith-Holbert, Connie [National Transportation Research Center, Inc., Knoxville, TN (United States); Petrolino, Joseph [National Transportation Research Center, Inc., Knoxville, TN (United States); Watkins, Bart [Power Source Technologies Inc., Corvallis, OR (United States); Irick, David [Power Source Technologies Inc., Corvallis, OR (United States)

    2011-12-31

    The Legacy engine is a completely new design, transitional diesel engine, replacing the reciprocating engine with a rotary engine. The Legacy engine offers significant advances over conventional internal combustion engines in 1) power to weight ratio; 2) multiple fuel acceptance; 3) fuel economy; and 4) environmental compliance. These advances are achieved through a combination of innovative design geometry, rotary motion, aspiration simplicity, and manufacturing/part simplicity. The key technical challenge to the Legacy engine's commercialization, and the focus of this project, was the development of a viable roton tip seal. The PST concept for the roton tip seal was developed into a manufacturable design. The design was evaluated using a custom designed and fabricated seal test fixture and further refined. This design was incorporated into the GEN2.5A prototype and tested for achievable compression pressure. The Decision Point at the end of Phase 1 of the project (described below) was to further optimize the existing tip seal design. Enhancements to the tip seal design were incorporated into the GEN2.5B prototype and tested and evaluated using the iterative research strategy described below. Compression pressures adequate for compression ignition of diesel fuel were achieved, although not consistently in all combustion volumes. The variation in compression pressures was characterized versus design features. As the roton tip seal performance was improved, results pointed toward inadequate performance of the housing side seals. Enhancement of the housing side seal system was accomplished using a custom designed side seal test fixture. The design enhancements developed with the test fixture were also incorporated into the GEN2.5B prototype and tested and evaluated using the iterative research strategy described below. Finally, to simplify the requirements for the roton tip seals and to enhance the introduction and combustion of fuel, a flush-mount fuel injector

  5. 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

  6. 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

  7. 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.

  8. 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)

  9. 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...

  10. Technical Integration of SMART Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-12-15

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

  11. 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

  12. 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

  13. A Detector for Combined SPECT/CT. Final Technical Report

    International Nuclear Information System (INIS)

    Vivek Nagarkar

    2006-01-01

    The goal of the Phase I research was to demonstrate the feasibility of developing a high performance SPECT/CT detector module based on a combination of microcolumnar CsI(Tl) scintillator coupled to an EMCCD readout. We are very pleased to report that our Phase I research has demonstrated the technical feasibility of our approach with a very high degree of success. Specifically, we were able to implement a back-thinned EMCCD with a fiberoptic window which was successfully used to demonstrate the feasibility of near simultaneous radionuclide/CT using the proposed concept. Although significantly limited in imaging area (24 x 24 mm 2 ) and pixel resolution (512 x 512), this prototype has shown exceptional capabilities such as a single optical photon sensitivity, very low noise, an intrinsic resolution of 64 (micro)m for radionuclide imaging, and a resolution in excess of 10 lp/mm for x-ray imaging. Furthermore, the combination of newly developed, thick, microcolumnar CsI and an EMCCD has shown to be capable of operating in a photon counting mode, and that the position and energy information obtained from these data can be used to improve resolution in radionuclide imaging. Finally, the prototype system has successfully been employed for near simultaneous SPECT/CT imaging using both, 125 I and 99m Tc radioisotopes. The tomographic reconstruction data obtained using a mouse heart phantom and other phantoms clearly demonstrate the feasibility and efficacy of the detector in small animal research. The following were the objectives specified in the Phase I proposal: (1) In consultation with Professor Hasegawa, develop specifications for the Phase I/Phase II prototype detector; (2) Modify current vapor deposition protocols to fabricate ∼2 mm thick microcolumnar CsI(Tl) scintillators with excellent columnar structure, high light yield, and high spatial resolution; (3) Perform detailed characterization of the film morphology, light output, and spatial resolution, and use

  14. 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.

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

    International Nuclear Information System (INIS)

    1995-04-01

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

  16. 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

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

    International Nuclear Information System (INIS)

    1995-04-01

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

  18. 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).

  19. 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.

  20. 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

  1. 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

  2. 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

  3. Modular Radioisotope Thermoelectric Generator (RTG) Program. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    Section 2.0 of this report summarizes the MOD-RTG reference flight design, and Section 3.0 discusses the Ground Demonstration System design. Multicouple technology development is discussed in Section 4.0, and Section 5.0 lists all published technical papers prepared during the course of the contract.

  4. 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

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

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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...

  11. Final Scientific and Technical Report State and Regional Biomass Partnerships

    Energy Technology Data Exchange (ETDEWEB)

    Handley, Rick; Stubbs, Anne D.

    2008-12-29

    The Northeast Regional Biomass Program successfully employed a three pronged approach to build the regional capacity, networks, and reliable information needed to advance biomass and bioenergy technologies and markets. The approach included support for state-based, multi-agency biomass working groups; direct technical assistance to states and private developers; and extensive networking and partnership-building activities to share objective information and best practices.

  12. Technical oversight for installation of TNX piezometers, Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Pidcoe, W.W. Jr. [Westinghouse Savannah River Company, Aiken, SC (United States)

    1997-06-05

    Science Applications International Corporation was tasked under subcontract C002025P to provide technical oversight for the drilling of one pilot borehole, and the drilling and installation of five piezometers in the TNX Area Swamp. The work was performed in accordance with the Statement of Work in Task Order Proposal No. ER39-129 dated August 6, 1996. This report describes the activities associated with the performance of the task.

  13. 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

  14. 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

  15. 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

  16. Final Technical Report_Clean Energy Program_SLC-SELF

    Energy Technology Data Exchange (ETDEWEB)

    Henderson, Glenn; Coward, Doug

    2014-01-22

    This is the Final Technical Report for DOE's Energy Efficiency and Conservation Block Grant, Award No. DE-EE0003813, submitted by St. Lucie County, FL (prime recipient) and the Solar and Energy Loan Fund (SELF), the program's third-party administrator. SELF is a 501(c)(3) and a certified Community Development Financial Institution (CDFI). SELF is a community-based lending organization that operates the Clean Energy Loan Program, which focuses on improving the overall quality of life of underserved populations in Florida with an emphasis on home energy improvements and cost-effective renewable energy alternatives. SELF was launched in 2010 through the creation of the non-profit organization and with a $2.9 million Energy Efficiency and Conservation Block (EECBG) grant from the U.S. Department of Energy (DOE). SELF has its main office and headquarters in St. Lucie County, in the region known as the Treasure Coast in East-Central Florida. St. Lucie County received funding to create SELF as an independent non-profit institution, outside the control of local government. This was important for SELF to create its identity as an integral part of the business community and to help in its quest to become a Community Development Financial Institution (CDFI). This goal was accomplished in 2013, allowing SELF to focus on its mission to increase energy savings while serving markets that have struggled to find affordable financial assistance. These homeowners are most impacted by high energy costs. Energy costs are a disproportionate percentage of household expenses for low to moderate income (LMI) households. Electricity costs have been steadily rising in Florida by nearly 5% per year. Housing in LMI neighborhoods often includes older inefficient structures that further exacerbate the problem. Despite the many available clean energy solutions, most LMI property owners do not have the disposable income or equity in their homes necessary to afford the high upfront cost

  17. Thermoeconomic analysis of power plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Tsatsaronis, G.; Winhold, M.

    1984-08-01

    In this report, the concept of exergy and the general methodology of the exergetic analysis and the thermoeconomic (combined exergetic and economic) analysis of energy conversion systems are presented. The THESIS (THermodynamic and Economc SImulation System) computer program used for these analyses is briefly described. Detailed mass, energy, exergy and money balances for a reference steam power plant (Harry Allen Station) are shown. The effect of the most important process parameters on the overall efficiency is investigated. A year-by-year and a levelized revenue requirement analysis are presented. The costs of exergy losses are compared with the capital costs and other expenses due to owning and operating each particular plant component. The question whether it is profitable to reduce the exergy losses by increasing these costs and vice versa is investigated. A cost sensitivity analysis including the effect of coal price and average annual capacity factor is performed. The methodology applied in this report appears to be useful in analyzing and evaluating energy conversion systems. The analyses presented here allow identification and evaluation of the inefficiencies and the opportunities for improvement of an energy conversion process. Results indicate that modifications in certain process parameters can lead to a decrease in the cost of electricity produced by the reference plant.

  18. SENTINEL trademark technical basis report for Peach Bottom. Final report

    International Nuclear Information System (INIS)

    1998-04-01

    PECO Energy in cooperation with the Electric Power Research Institute (EPRI) installed the SENTINEL trademark software at its Peach Bottom Atomic Power Station (PBAPS). 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 nine months, 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 PBAPS 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

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

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/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

  20. FINAL TECHNICAL REPORT: 20% Wind by 2030: Overcoming the Challenges

    Energy Technology Data Exchange (ETDEWEB)

    Tom Kaiserski; Dan Lloyd

    2012-02-28

    The funds allocated through the Wind Powering America (WPA) grant were utilized by the State of Montana to support broad outreach activities communicating the benefits and opportunities of increased wind energy and transmission development. The challenges to increased wind development were also clearly communicated with the understanding that a clearer comprehension of the challenges would be beneficial in overcoming the obstacles to further development. The ultimate purpose of these activities was to foster the increased development of Montana's rich wind resources through increased public acceptance and wider dissemination of technical resources.

  1. Establishment of the International Power Institute. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Julius E. Coles

    2000-08-04

    The International Power Institute, in collaboration with American industries, seeks to address technical, political, economic and cultural issues of developing countries in the interest of facilitating profitable transactions in power related infrastructure projects. IPI works with universities, governments and commercial organizations to render project-specific recommendations for private-sector investment considerations. IPI also established the following goals: Facilitate electric power infrastructure transactions between developing countries and the US power industry; Collaborate with developing countries to identify development strategies to achieve energy stability; and Encourage market driven solutions and work collaboratively with other international trade energy, technology and banking organizations.

  2. Technical and economic assessment of solar hybrid repowering. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-09-01

    Drawings are presented for the repowering project described in SAN--1608-4-1. Reeves Sation No. 2 was selected for study for repowering at 50 percent (25 MWe) using the 10-MW solar central receiver pilot plant preliminary design for Barstow, California. (WHK)

  3. 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.

  4. 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

  5. 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)

  6. SIAM Conference on Geometric Design and Computing. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2002-03-11

    The SIAM Conference on Geometric Design and Computing attracted 164 domestic and international researchers, from academia, industry, and government. It provided a stimulating forum in which to learn about the latest developments, to discuss exciting new research directions, and to forge stronger ties between theory and applications. Final Report

  7. 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.

  8. 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...

  9. Precision control of biogas plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Moeller, H.B.; Nielsen, Anders M.; Ward, A.J.

    2009-10-15

    The objective of the project has been to improve design and process stability in biogas plants. The results can be divided within the following main categories: 1) Pre-treatment, serial coupling of digesters and post digestion 2) Process inhibition 3) Process control Ad 1) This work has shown that extreme thermophilic pre-treatment of cattle manure and pig manure mixed with silage has a considerable effect on methane yield in a subsequent methanogenic reactor. Ad 2) The effect of ammonia inhibition was studied in a series of continuously stirred tank reactors co-digesting pig manure (40%) with the addition of solid fractions (60%) and increasing concentrations of ammonia caused by addition of NH{sub 4}Cl pulses. Ad 3) Near infrared spectroscopy (NIRS) was used to predict liquid phase volatile fatty acid (VFA) concentrations in three experiments treating three different materials: pig slurry with maize silage, chicken manure and cattle slurry.

  10. Systems study 'Alternative Entsorgung'. Final report. Technical annex 4

    International Nuclear Information System (INIS)

    1984-08-01

    The investigations extend over the personnel, organisational, spatial and equipment conditions, which guarantee the protection of the people employed in the plant, the protection of the plant and the protection of the environment in correct operation and during accidents to the required extent and sufficiently accurately and reliably. The results show that safe enclosure is guaranteed and it is ensured that all exposure to radiation or contamination of persons, goods or the environment is kept as low as possible below the limits laid down in the Radiation Protection Ordinance, taking into account the state of science and technology and all the individual circumstances. The equipment is available and the measures are taken which are necessary to comply with the protection regulations. (orig./HP) [de

  11. 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.

  12. 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

  13. Final Technical Report for subcontract number B612144

    Energy Technology Data Exchange (ETDEWEB)

    Mayali, X. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marcu, O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-11

    The original statement of work stipulated that the Subcontractor shall perform bacterial and algal cultivation and manipulation, microbe isolation, preparation of samples for sequencing and isotopic analysis, data analysis, and manuscript preparation. The Subcontractor shall work closely with Dr. Mayali and other LLNL scientists, and shall participate in monthly SFA meetings (either in person or by telephone). The Subcontractor shall deliver a final report at the conclusion of the work.

  14. Chloroplast Dynamics and Photosynthetic Efficiency: Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Hanson, Maureen [Cornell Univ., Ithaca, NY (United States)

    2016-11-03

    This project investigated the mechanism by which chloroplasts position themselves to maximize solar energy utilization, to enhance gas exchange, to minimize environmental stress, and to promote efficient exchange of metabolites with other compartments within the plant cell. Chloroplasts move within leaf cells to optimize light levels, moving toward levels of light useful for photosynthesis while moving away from excess light. Plastids sometimes extend their reach by sending out projections (stromules) that can connect anchor chloroplasts in position within the cell or provide close contacts with plasma membrane, mitochondria, peroxisomes, endoplasmic reticulum, and the nucleus. The intracellular location of chloroplasts in relation to other organelles with which they share biosynthetic pathways, such as peroxisomes and mitochondria in photorespiration, affects metabolite flow. This work contributed to the knowledge of the mechanisms of organelle movement and anchoring in specific locations in plant cells and how proteins traffic within the cell. We identified two domains on 12 of the 13 Arabidopsis myosins that were similar to the vacuole-binding (V) domain characterized in yeast and to the DIL domain characterized in yeast and mouse as required for secretory vesicle or melanosome movement, respectively. Because all of the Arabidopsis regions with homology to the V domain contain the amino acid sequence PAL, we refer to this region as the Arabidopsis PAL domain. We have used the yeast Myo2p tail structural information to model the 12 myosin XI tail domains containing the homologous PAL and DIL domains. Eight YFP::DIL domain fusions labeled peroxisomes; none labeled mitochondria or chloroplasts. Six myosin XI Vacuole domains labeled mitochondria and seven labeled Golgi bodies. The Arabidopsis myosin XI-F PAL domain and the homologous myosin XI-F PAL domain from N. benthamiana labels chloroplasts and stromules in N. benthamiana leaves. Using an Arabidopsis line

  15. Final Technical Report - Modernization of the Boulder Canyon Hydroelectric Project

    Energy Technology Data Exchange (ETDEWEB)

    Taddeucci, Joe [Dept. of Public Works, Boulder, CO (United States). Utilities Division

    2013-03-29

    The Boulder Canyon Hydroelectric Project (BCH) was purchased by the City of Boulder, CO (the city) in 2001. Project facilities were originally constructed in 1910 and upgraded in the 1930s and 1940s. By 2009, the two 10 MW turbine/generators had reached or were nearing the end of their useful lives. One generator had grounded out and was beyond repair, reducing plant capacity to 10 MW. The remaining 10 MW unit was expected to fail at any time. When the BCH power plant was originally constructed, a sizeable water supply was available for the sole purpose of hydroelectric power generation. Between 1950 and 2001, that water supply had gradually been converted to municipal water supply by the city. By 2001, the water available for hydroelectric power generation at BCH could not support even one 10 MW unit. Boulder lacked the financial resources to modernize the facilities, and Boulder anticipated that when the single, operational historical unit failed, the project would cease operation. In 2009, the City of Boulder applied for and received a U.S. Department of Energy (DOE) grant for $1.18 million toward a total estimated project cost of $5.155 million to modernize BCH. The federal funding allowed Boulder to move forward with plant modifications that would ensure BCH would continue operation. Federal funding was made available through the American Recovery and Reinvestment Act (ARRA) of 2009. Boulder determined that a single 5 MW turbine/generator would be the most appropriate capacity, given the reduced water supply to the plant. Average annual BCH generation with the old 10 MW unit had been about 8,500 MW-hr, whereas annual generation with a new, efficient turbine could average 11,000 to 12,000 MW-hr. The incremental change in annual generation represents a 30% increase in generation over pre-project conditions. The old turbine/generator was a single nozzle Pelton turbine with a 5-to-1 flow turndown and a maximum turbine/generator efficiency of 82%. The new unit is a

  16. FINAL TECHNICAL REPORT Chagas Prevention in Central America

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

    Carlota Monroy

    INFORME FINAL: PROYECTO ID 106531 - 001. CORRESPONDIENTE AL PERIODO DEL 1 DE MARZO 2011 AL 31 DE MARZO 2014. CONTENIDO. 1. Información general ……………………………………………………………1. 2. Resumen del proyecto ………………………………………………………….2. 3. Metas objetivos ...

  17. Technical and economic feasibility of thermal storage. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Shelpuk, B.; Joy, P.; Crouthamel, M.

    1977-06-01

    The technical and economic feasibility of various thermal energy storage alternatives is determined by comparing the system performance and annualized cost which result from each storage alternative operating with the same solar collector model, the same building load model, and the same heating system and controls model. Performance and cost calculations are made on the basis of an hour-by-hour time step using actual weather bureau data for Albuquerque, N. M., and New York City for a single six-month heating season. The primary approach to comparing various storage alternatives is to allow the collector area and storage mass to vary until a minimum cost combination is achieved. In the Albuquerque location collector area of 325 ft/sup 2/, water storage mass of 12.5 lb/ft/sup 2/ of collector area, and phase change mass of 6.25 lb/ft/sup 2/ of collector area results in minimum cost systems, each of which delivers about 50% of the total building demand. The primary conclusion is that, using current costs for materials and containers, water is the cheapest storage alternative for heating applications in both Albuquerque and New York City. The cost of containing or encapsulating phase change materials, coupled with their small system performance advantage, is the main reason for this conclusion. The use of desiccant materials for thermal storage is considered to be impractical due to irreversibilities in thermal cycling.

  18. Modular Electric Vehicle Program (MEVP). Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-01

    The Modular Electric Vehicle Program (MEVP) was an EV propulsion system development program in which the technical effort was contracted by DOE to Ford Motor Company. The General Electric Company was a major subcontractor to Ford for the development of the electric subsystem. Sundstrand Power Systems was also a subcontractor to Ford, providing a modified gas turbine engine APU for emissions and performance testing as well as a preliminary design and producibility study for a Gas Turbine-APU for potential use in hybrid/electric vehicles. The four-year research and development effort was cost-shared between Ford, General Electric, Sundstrand Power Systems and DOE. The contract was awarded in response to Ford`s unsolicited proposal. The program objective was to bring electric vehicle propulsion system technology closer to commercialization by developing subsystem components which can be produced from a common design and accommodate a wide range of vehicles; i.e., modularize the components. This concept would enable industry to introduce electric vehicles into the marketplace sooner than would be accomplished via traditional designs in that the economies of mass production could be realized across a spectrum of product offerings. This would eliminate the need to dedicate the design and capital investment to a limited volume product offering which would increase consumer cost and/or lengthen the time required to realize a return on the investment.

  19. 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

  20. Systems study 'Alternative Entsorgung'. Final report. Technical annex 16

    International Nuclear Information System (INIS)

    1984-04-01

    The system is subdivided into three complexes: conventional fission product bookkeeping with quantity checks on incoming and outgoing material at a few key measuring points as well as inventory on the occasion of the annual closedown for operational reasons; determination of inventory and balancing with the plant in operation via the measuring data of in-process instrumentation of vessels and apparatures in fule reprocessing or tracing of fission products in mixed oxide manufacture by charges down to the production of fuel elements, respectively; control checks at crucial monitoring points by measures of spatial limitation (containment) and observation (surveillance) to be determined by means of analyses of relevant diversion pathways carried out systematically. (orig./HP) [de

  1. Final Technical Report Steam Cycle Washer for Unbleached Pulp

    Energy Technology Data Exchange (ETDEWEB)

    Starkey, Yvonne; Salminen, Reijo; Karlsnes, Andy

    2008-09-22

    Project Abstract for “Steam Cycle Washer for Unbleached Pulp” When completed, the patented SC Washer will provide an innovative, energy efficient demonstration project to wash unbleached pulp using a pressure vessel charged with steam. The Port Townsend Paper Corporation’s pulp mill in Port Townsend, WA was initially selected as the host site for conducting the demonstration of the SCW. Due to 2006 and 2007 delays in the project caused by issues with 21st Century Pulp & Paper, the developer of the SCW, and the 2007 bankruptcy proceedings and subsequent restructuring at Port Townsend Paper, the mill can no longer serve as a host site. An alternate host site is now being sought to complete the commercial demonstration of the Steam Cycle Washer for Unbleached Pulp. Additionally, estimated costs to complete the project have more than doubled since the initial estimates for the project were completed in 2002. Additional grant funding from DOE was sought and in July, 2008 the additional DOE funds were procured under a new DOE award, DE-PS36-08GO98014 issued to INL. Once the new host site is secured the completion of the project will begin under the management of INL. Future progress reports and milestone tracking will be completed under requirements of new DOE Award Number DE-PS36-08GO98014. The following are excerpts from the project Peer Review completed in 2006. They describe the project in some detail. Additional information can be found by reviewing DOE Award Number: DE-PS36-08GO98014. 5. Statement of Problem and Technical Barriers: The chemical pulping industry is one of the major users of fresh water in the United States. On average the industry uses over 80 tons of water to produce one ton of pulp, some states use up to 50% more (Washington 120 and Wisconsin 140). In order to process one ton of pulp using 80 tons of process water, a large amount of: • energy is used in process heat and • power is required for pumping the large volume of pulp slurries

  2. Team Massachusetts & Central America Solar Decathlon 2015 Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kenneth [Western New England Univ., Springfield, MA (United States)

    2016-04-29

    Our team was Team MASSCA (Massachusetts and Central America), which was a partnership of Western New England University (WNE) located in Massachusetts USA, The Technological University of Panama (UTP), and Central American Technological University (UNITEC) of Honduras. Together we had a group of 6 faculty members and approximately 30 undergraduate students. Our house is ‘The EASI’ House, which stands for Efficient, Affordable, Solar Innovation. The EASI house is rectangular with two bedrooms and one bath, and offers a total square footage of 680. Based on competition estimates, The EASI house costs roughly $121,000. The EASI house has a 5kW solar system. Faculty and students from all three institutions were represented at the competition in Irvine California. Team MASSCA did well considering this was our first entry in the Solar Decathlon competition. Team MASSCA won the following awards: First Place – Affordability Contest Second Place – Energy Balance Contest. The competition provided a great experience for our students (and faculty as well). This competition provided leadership, endurance, and technical knowledge/skills for our students, and was the single most important hands-on experience during their undergraduate years. We are extremely pleased with the awards we received. At the same time we have learned from our efforts and would do better if we were to compete in the future. Furthermore, as a result of our team’s Inter-Americas collaborative effort, UTP and WNE have partnered to form Team PANAMASS (PANAma and MASSachusetts) and have developed The 3 SMART House for the inaugural Solar Decathlon Latin America & Caribbean competition held in Colombia.

  3. 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.

  4. 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).

  5. 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...

  6. Texas Hydrogen Education Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Hitchcock, David; Bullock, Dan

    2011-06-30

    , and hydrogen fueling) are effective for engaging target audiences, and (3) a clear path forward is needed for state and local agencies interested in project implementation (funding, financing, preliminary design, technical assistance, etc.).

  7. Transportation and Greenhouse Gas Emissions Trading. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Steve Winkelman; Tim Hargrave; Christine Vanderlan

    1999-10-01

    The authors conclude in this report that an upstream system would ensure complete regulatory coverage of transportation sector emissions in an efficient and feasible manner, and as such represents a key component of a national least-cost GHG emissions abatement strategy. The broad coverage provided by an upstream system recommends this approach over vehicle-maker based approaches, which would not cover emissions from heavy-duty vehicles and the aviation, marine and off-road sub-sectors. The on-road fleet approach unfairly and inefficiently burdens vehicle manufacturers with responsibility for emissions that they cannot control. A new vehicles approach would exclude emissions from vehicles on the road prior to program inception. The hybrid approach faces significant technical and political complications, and it is not clear that the approach would actually change behavior among vehicle makers and users, which is its main purpose. They also note that a trading system would fail to encourage many land use and infrastructure measures that affect VMT growth and GHG emissions. They recommend that this market failure be addressed by complementing the trading system with a program specifically targeting land use- and infrastructure-related activities. A key issue that must be addressed in designing a national GHG control strategy is whether or not it is necessary to guarantee GHG reductions from the transport sector. Neither an upstream system nor a downstream approach would do so, since both would direct capital to the least-cost abatement opportunities wherever they were found. They review two reasons why it may be desirable to force transportation sector reductions: first, that the long-term response to climate change will require reductions in all sectors; and second, the many ancillary benefits associated with transportation-related, and especially VMT-related, emissions reduction activities. If policy makers find it desirable to establish transportation

  8. 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

  9. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility; FINAL

    International Nuclear Information System (INIS)

    Thomas B. Kirchner

    2002-01-01

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-31

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

  11. 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

  12. 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

  13. Marin Solar Village: feasibility study and technical analysis. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-08-31

    The energy needs of Hamilton Air Force Base's Solar Village for electricity and heating and cooling of buildings are considered and alternative ways of meeting the Village's requirements for these forms of energy are evaluated. First, Solar Village's energy demand is calculated and compared to a base case representing calculations for typical energy usage for a development of similar size and density that is in conformance with current state and local ordinances. The potential of selected alternative technologies to meet the Solar Village projected demand for electrical power and natural gas is evaluated. Scenarios were developed to reduce demand, particularly in the building sector. Four alternative on-site energy technologies have been evaluated: wind, solar thermal electric, biomass conversion, photovoltaics. Each alternative is analyzed in detail. Of the four alternatives considered, the one with the greatest present potential is biomass conversion. Two technologies have been incorporated into the design. A 3-acre land fill is covered with a mantle of soil. A network of pipes carries off the methane gas which is a natural product of anaerobic decomposition of the materials in the land fill. The second technology involves the planting of rapidly-growing trees on denuded and unused portions of the site; 50 acres devoted to tree production could yield 12% of the back-up energy required for home heating on a sustainable basis.

  14. IRIS International Reactor Innovative and Secure Final Technical Progress Report

    International Nuclear Information System (INIS)

    Carelli, M.D.

    2003-01-01

    OAK-B135 This NERI project, originally started as the Secure Transportable Autonomous Light Water Reactor (STAR-LW) and currently known as the International Reactor Innovative and Secure (IRIS) project, had the objective of investigating a novel type of water-cooled reactor to satisfy the Generation IV goals: fuel cycle sustainability, enhanced reliability and safety, and improved economics. The research objectives over the three-year (1999-2002) program were as follows: First year: Assess various design alternatives and establish main characteristics of a point design; Second year: Perform feasibility and engineering assessment of the selected design solutions; Third year: Complete reactor design and performance evaluation, including cost assessment These objectives were fully attained and actually they served to launch IRIS as a full fledged project for eventual commercial deployment. The program did not terminate in 2002 at the end of the NERI program, and has just entered in its fifth year. This has been made possible by the IRIS project participants which have grown from the original four member, two-countries team to the current twenty members, nine countries consortium. All the consortium members work under their own funding and it is estimated that the value of their in-kind contributions over the life of the project has been of the order of $30M. Currently, approximately 100 people worldwide are involved in the project. A very important constituency of the IRIS project is the academia: 7 universities from four countries are members of the consortium and five more US universities are associated via parallel NERI programs. To date, 97 students have worked or are working on IRIS; 59 IRIS-related graduate theses have been prepared or are in preparation, and 41 of these students have already graduated with M.S. (33) or Ph.D. (8) degrees. This ''final'' report (final only as far as the NERI program is concerned) summarizes the work performed in the first four

  15. Final Technical Report for DE-SC0012297

    Energy Technology Data Exchange (ETDEWEB)

    Dell' Antonio, Ian [Brown Univ., Providence, RI (United States)

    2017-08-01

    This is the final report on the work performed in award DE-SC0012297, Cosmic Frontier work in support of the LSST Dark Energy Science Collaboration's work to develop algorithms, simulations, and statistical tests to ensure optimal extraction of the dark energy properties from galaxy clusters observed with LSST. This work focused on effects that could produce a systematic error on the measurement of cluster masses (that will be used to probe the effects of dark energy on the growth of structure). These effects stem from the deviations from pure ellipticity of the gravitational lensing signal and from the blending of light of neighboring galaxies. Both these effects are expected to be more significant for LSST than for the stage III experiments such as the Dark Energy Survey. We calculate the magnitude of the mass error (or bias) for the first time and demonstrate that it can be treated as a multiplicative correction and calibrated out, allowing mass measurements of clusters from gravitational lensing to meet the requirements of LSST's dark energy investigation.

  16. Final technical report on studies of plasma transport

    International Nuclear Information System (INIS)

    O'Neil, T.M.; Driscoll, C.F.; Malmberg, J.H.

    1997-01-01

    This document gives an overview of the scientific results obtained under the DOE grant, and references the journal articles which give more complete descriptions of the various topics. Recently, the research has been focused on 2-dimensional vortices and turbulence: experiments using a new camera-diagnosed electron plasma apparatus have given surprising results which both clarify and challenge theories. Here, the crossfield E x B flow of the electron plasma is directly analogous to the 2-d flow of an ideal fluid such as water, and may also give insight into more complicated poloidal flows exhibited in toroidal plasmas. The shear-flow instabilities, turbulence, and vortices can be accurately observed, and the free relaxation of this turbulence has been characterized. The physical processes underlying the complicated turbulent evolution can also be studied in more controlled near-linear regimes. The original experimental focus of this program was on radial particle transport from applied external field asymmetries. Here, this research program clearly identified the importance of the collective response of the plasma, giving smaller fields from shielding, or enhanced fields from resonant modes. Experiments and theory work have also elucidated the flow of a plasma along the magnetic field. Finally, some theory was pursued for direct application to fusion plasmas, and to gravitating gas clouds in astrophysics. This program was highly successful in clarifying basic plasma transport processes

  17. Advanced Beta Dosimetry Techniques.Final Scientific/Technical Report

    International Nuclear Information System (INIS)

    David M. Hamby, PhD

    2006-01-01

    Final report describing NEER research on Advanced Beta Dosimetry Techniques. The research funded by this NEER grant establishes the framework for a detailed understanding of the challenges in beta dosimetry, especially in the presence of a mixed radiation field. The work also stimulated the thinking of the research group which will lead to new concepts in digital signal processing to allow collection of detection signals and real-time analysis such that simultaneous beta and gamma spectroscopy can take place. The work described herein (with detail in the many publications that came out of this research) was conducted in a manner that provided dissertation and thesis topics for three students, one of which was completely funded by this grant. The overall benefit of the work came in the form of a dramatic shift in signal processing that is normally conducted in pulse shape analysis. Analog signal processing was shown not to be feasible for this type of work and that digital signal processing was a must. This, in turn, led the research team to a new understanding of pulse analysis, one in which expands the state-of-the-art in simultaneous beta and gamma spectroscopy with a single detector

  18. Systems study 'Alternative Entsorgung'. Final report. Technical annex 7

    International Nuclear Information System (INIS)

    Engelmann, H.J.

    1984-10-01

    A radiation protection concept was worked out for final storage of spent fuel elements. It contains the areas of instrumentation and equipment with the necessary devices and measuring equipment for monitoring emission and the room air, personnel dosimetry, measuring contamination, local dose rate measurements and division into radiation protection areas. The barrel incoming inspection is described. The work for determining the radiological load of the operating staff and the environment for correct and incorrect operation is also described. The radiological load of the operating staff for correct operation was determined in the form of the collective dose with dose factors in accordance with ICRP and individual doses according to Radiation Protection Ordinance. The collective dose is 0.28 pers. Sv/a and the maximum individual dose remains below 1.0 E-2 Sv/a. The individual doses determined remain below the permitted limits of Radiation Protection Ordinance. In the context of accident analysis, it was found that no accidents occur, which load the operating staff radiologically above the permitted limits of the Radiation Protection Ordinance. A probability consideration of accidents shows that the accident risk of the operating staff is several orders of magnitude below that of the normal operating risk. (orig./HP) [de

  19. ASME code and ratcheting in piping components. Final technical report

    International Nuclear Information System (INIS)

    Hassan, T.; Matzen, V.C.

    1999-01-01

    The main objective of this research is to develop an analysis program which can accurately simulate ratcheting in piping components subjected to seismic or other cyclic loads. Ratcheting is defined as the accumulation of deformation in structures and materials with cycles. This phenomenon has been demonstrated to cause failure to piping components (known as ratcheting-fatigue failure) and is yet to be understood clearly. The design and analysis methods in the ASME Boiler and Pressure Vessel Code for ratcheting of piping components are not well accepted by the practicing engineering community. This research project attempts to understand the ratcheting-fatigue failure mechanisms and improve analysis methods for ratcheting predictions. In the first step a state-of-the-art testing facility is developed for quasi-static cyclic and seismic testing of straight and elbow piping components. A systematic testing program to study ratcheting is developed. Some tests have already been performed and the rest will be completed by summer'99. Significant progress has been made in the area of constitutive modeling. A number of sophisticated constitutive models have been evaluated in terms of their simulations for a broad class of ratcheting responses. From the knowledge gained from this evaluation study two improved models are developed. These models are demonstrated to have promise in simulating ratcheting responses in piping components. Hence, implementation of these improved models in widely used finite element programs, ANSYS and/or ABAQUS, is in progress. Upon achieving improved finite element programs for simulation of ratcheting, the ASME Code provisions for ratcheting of piping components will be reviewed and more rational methods will be suggested. Also, simplified analysis methods will be developed for operability studies of piping components and systems. Some of the future works will be performed under the auspices of the Center for Nuclear Power Plant Structures

  20. Final Technical Report: Development of Post-Installation Monitoring Capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Polagye, Brian [University of Washington

    2014-03-31

    The development of approaches to harness marine and hydrokinetic energy at large-scale is predicated on the compatibility of these generation technologies with the marine environment. At present, aspects of this compatibility are uncertain. Demonstration projects provide an opportunity to address these uncertainties in a way that moves the entire industry forward. However, the monitoring capabilities to realize these advances are often under-developed in comparison to the marine and hydrokinetic energy technologies being studied. Public Utility District No. 1 of Snohomish County has proposed to deploy two 6-meter diameter tidal turbines manufactured by OpenHydro in northern Admiralty Inlet, Puget Sound, Washington. The goal of this deployment is to provide information about the environmental, technical, and economic performance of such turbines that can advance the development of larger-scale tidal energy projects, both in the United States and internationally. The objective of this particular project was to develop environmental monitoring plans in collaboration with resource agencies, while simultaneously advancing the capabilities of monitoring technologies to the point that they could be realistically implemented as part of these plans. In this, the District was joined by researchers at the Northwest National Marine Renewable Energy Center at the University of Washington, Sea Mammal Research Unit, LLC, H.T. Harvey & Associates, and Pacific Northwest National Laboratory. Over a two year period, the project team successfully developed four environmental monitoring and mitigation plans that were adopted as a condition of the operating license for the demonstration project that issued by the Federal Energy Regulatory Commission in March 2014. These plans address nearturbine interactions with marine animals, the sound produced by the turbines, marine mammal behavioral changes associated with the turbines, and changes to benthic habitat associated with colonization

  1. Final Technical Report - Photovoltaics for You (PV4You) Program

    Energy Technology Data Exchange (ETDEWEB)

    Weissman, J. M. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Sherwood, L. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Pulaski, J. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Cook, C. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Kalland, S. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Haynes, J. [Interstate Renewable Energy Council (IREC), New York, NY (United States)

    2005-08-14

    position in developing quality and competency standards for solar professionals and for training programs critical components to bring the solar industry into step with other recognized craft labor forces. IREC's objective was to provide consumer assurances and assist the states and the solar industry in building a strong and qualified workforce. IREC's Schools Going Solar Clearinghouse provided channels of information to educate students, teachers, parents and the community at large about the benefits of solar energy. Solar school projects enhance science and math education while creating an initial entry market for domestic PV. And, IREC's community and outreach network got the right information out to capture the interest and met the needs of different audiences and reached groups that weren't traditionally part of the solar community. IREC's PV4You project was effective because it resulted in reduced costs through easier interconnection and better net metering agreements and by raising the competency standards for solar practitioners. The project provided ways to eliminate barriers and constraints by providing technical assistance, offering model agreements based on industry consensus that were used by state and local decision makers. And, the project increased public acceptance by providing information, news and guidelines for different audiences.

  2. 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)

  3. Final Technical Report - In-line Uranium Immunosensor

    International Nuclear Information System (INIS)

    Blake, Diane A.

    2006-01-01

    In this project, personnel at Tulane University and Sapidyne Instruments Inc. developed an in-line uranium immunosensor that could be used to determine the efficacy of specific in situ biostimulation approaches. This sensor was designed to operate autonomously over relatively long periods of time (2-10 days) and was able to provide near real-time data about uranium immobilization in the absence of personnel at the site of the biostimulation experiments. An alpha prototype of the in-line immmunosensor was delivered from Sapidyne Instruments to Tulane University in December of 2002 and a beta prototype was delivered in November of 2003. The beta prototype of this instrument (now available commercially from Sapidyne Instruments) was programmed to autonomously dilute standard uranium to final concentrations of 2.5 to 100 nM (0.6 to 24 ppb) in buffer containing a fluorescently labeled anti-uranium antibody and the uranium chelator, 2,9-dicarboxyl-1,10-phenanthroline. The assay limit of detection for hexavalent uranium was 5.8 nM or 1.38 ppb. This limit of detection is well below the drinking water standard of 30 ppb recently promulgated by the EPA. The assay showed excellent precision; the coefficients of variation (CV's) in the linear range of the assay were less than 5% and CV?s never rose above 14%. Analytical recovery in the immunosensors-based assay was assessed by adding variable known quantities of uranium to purified water samples. A quantitative recovery (93.75% - 108.17%) was obtained for sample with concentrations from 7.5 to 20 nM (2-4.75 ppb). In August of 2005 the sensor was transported to Oak Ridge National Laboratory, for testing of water samples at the Criddle test site (see Wu et al., Environ. Sci. Technol. 40:3978-3985 2006 for a description of this site). In this first on-site test, the in-line sensor was able to accurately detect changes in the concentrations of uranium in effluent samples from this site. Although the absolute values for the uranium

  4. 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

  5. Technical assistance for Meharry Medical College Energy Efficiency Project. Final project status and technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-08

    This report presents the results of a program to provide technical assistance to Meharry Medical College. The purpose of the program is to facilitate Meharry`s effort to finance a campus-wide facility retrofit. The US Department of Energy (USDOE) funded the program through a grant to the Tennessee Department of Economic and Community Development (TECD). The University of Memphis-Technology and Energy Services (UM-TES), under contract to TECD, performed program services. The report has three sections: (1) introduction; (2) project definition, financing, and participants; and (3) opportunities for federal participation.

  6. 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

  7. 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.

  8. 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

  9. 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

  10. Dissemination of Continuing Education Materials Via Television Delivery Systems. Final Technical Report and Final Report.

    Science.gov (United States)

    Munushian, Jack

    In 1972, the University of Southern California School of Engineering established a 4-channel interactive instructional television network. It was designed to allow employees of participating industries to take regular university science and engineering courses and special continuing education courses at or near their work locations. Final progress…

  11. 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)

  12. 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

  13. 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

  14. 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

  15. 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

  16. "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.

  17. 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.

  18. [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.

  19. 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

  20. 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

  1. 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)

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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...

  15. 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

  16. 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

  17. 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.

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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.

  6. 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.

  7. 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)

  8. 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.)

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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

  18. 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

  19. 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)

  20. 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

  1. 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.

  2. 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

  3. 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

  4. 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)

  5. 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.

  6. 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

  7. 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.

  8. 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

  9. Assessment of plant-derived hydrocarbons. Final report

    Energy Technology Data Exchange (ETDEWEB)

    McFadden, K.; Nelson, S.H.

    1981-09-30

    A number of hydrocarbon producing plants are evaluated as possible sources of rubber, liquid fuels, and industrial lubricants. The plants considered are Euphorbia lathyris or gopher plant, milkweeds, guayule, rabbit brush, jojoba, and meadow foam. (ACR)

  10. 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.

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

    Science.gov (United States)

    1996-11-01

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

  12. 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

  13. 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

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

    Science.gov (United States)

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

    2015-03-01

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

  15. 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].

  16. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  18. 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

  19. 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)

  20. 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.

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

    International Nuclear Information System (INIS)

    O'Leary, M.H.

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    1977-06-01

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

  3. Final Report: RPP-WTP Semi-Integrated Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Duignan, M. R.; Adamson, D. J.; Calloway, T. B.; Fowley, M. D.; Qureshi, Z. H.; Steimke, J. L.; Williams, M. R.; Zamecnik, J. R.

    2005-06-01

    In August 2004 the last of the SIPP task testing ended--a task that formally began with the issuance of the RPP-WTP Test Specification in June 2003. The planning for the task was a major effort in itself and culminated with the input of all stakeholders, DOE, Bechtel National, Inc., Washington Group International, in October 2003 at Hanford, WA (Appendix A). This report documents the activities carried out as a result of that planning. Campaign IV, the fourth and final step towards the Semi-Integrated Pilot Plant (SIPP) task, conducted by the Savannah River National Laboratory (SRNL) at the Savannah River Site, was to take the several recycle streams produced in Campaign III, the third step of the task, and combine them with other simulated recycle and chosen waste streams. (Campaign III was fed recycles from Campaign II, as Campaign II was fed by Campaign I.) The combined stream was processed in a fashion that mimicked the pretreatment operations of the DOE River Protection Project--Waste Treatment and Immobilization Plant (RPP-WTP) with the exception of the Ion Exchange Process. The SIPP task is considered semi-integrated because it only deals with the pretreatment operations of the RPP-WTP. That is, the pilot plant starts by receiving waste from the tank farm and ends when waste is processed to the point of being sent for vitrification. The resulting pretreated LAW and HLW simulants produced by the SIPP were shipped to VSL (Vitreous State Laboratory) and successfully vitrified in pilot WTP melters. Within the SIPP task these steps are referred to as Campaigns and there were four Campaigns in all. Campaign I, which is completely different than other campaigns, subjected a simulant of Hanford Tank 241-AY-102/C-106 (AY102) waste to cross-flow ultrafiltration only and in that process several important recycle streams were produced as a result of washing the simulant and cleaning the cross-flow filter. These streams were fed to subsequent campaigns and that work was

  4. Final Report: RPP-WTP Semi-Integrated Pilot Plant

    International Nuclear Information System (INIS)

    Duignan, M. R.; Adamson, D. J.; Calloway, T. B.; Fowley, M. D.; Qureshi, Z. H.; Steimke, J. L.; Williams, M. R.; Zamecnik, J. R.

    2005-01-01

    In August 2004 the last of the SIPP task testing ended--a task that formally began with the issuance of the RPP-WTP Test Specification in June 2003. The planning for the task was a major effort in itself and culminated with the input of all stakeholders, DOE, Bechtel National, Inc., Washington Group International, in October 2003 at Hanford, WA (Appendix A). This report documents the activities carried out as a result of that planning. Campaign IV, the fourth and final step towards the Semi-Integrated Pilot Plant (SIPP) task, conducted by the Savannah River National Laboratory (SRNL) at the Savannah River Site, was to take the several recycle streams produced in Campaign III, the third step of the task, and combine them with other simulated recycle and chosen waste streams. (Campaign III was fed recycles from Campaign II, as Campaign II was fed by Campaign I.) The combined stream was processed in a fashion that mimicked the pretreatment operations of the DOE River Protection Project--Waste Treatment and Immobilization Plant (RPP-WTP) with the exception of the Ion Exchange Process. The SIPP task is considered semi-integrated because it only deals with the pretreatment operations of the RPP-WTP. That is, the pilot plant starts by receiving waste from the tank farm and ends when waste is processed to the point of being sent for vitrification. The resulting pretreated LAW and HLW simulants produced by the SIPP were shipped to VSL (Vitreous State Laboratory) and successfully vitrified in pilot WTP melters. Within the SIPP task these steps are referred to as Campaigns and there were four Campaigns in all. Campaign I, which is completely different than other campaigns, subjected a simulant of Hanford Tank 241-AY-102/C-106 (AY102) waste to cross-flow ultrafiltration only and in that process several important recycle streams were produced as a result of washing the simulant and cleaning the cross-flow filter. These streams were fed to subsequent campaigns and that work was

  5. Solar Total Energy System, Large Scale Experiment, Shenandoah, Georgia. Final technical progress report. Volume II, Section 3. Facility concept design. [1. 72 MW thermal and 383. 6 kW electric power for 42,000 ft/sup 2/ knitwear plant

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1977-10-17

    The Stearns-Roger Engineering Company conceptual design of ERDA's Large Scale Experiment No. 2 (LSE No. 2) is presented. The various LSEs are part of ERDA's Solar Total Energy Program (STES) and a separate activity of the National Solar Thermal Power Systems Program. The object of this LSE is to design, construct, test, evaluate and operate a STES for the purpose of obtaining experience with large scale hardware systems and to establish engineering capability for subsequent demonstration projects. This particular LSE is to be located at Shenandoah, Georgia, and will provide power to the Bleyle knitwear factory. The Solar Total Energy system is sized to supply 1.720 MW thermal power and 383.6 KW electrical power. The STES is sized for the extended knitwear plant of 3902 M/sup 2/ (42,000 sq-ft) which will eventually employ 300 people. The details of studies conducted for Phase II of the Solar Total Energy System (STES) for the conceptual design requirements of the facility are presented. Included in this section are the detailed descriptions and analyses of the following subtasks: facility concept design, system concept design, performance analysis, operation plan, component and subsystem development, procurement plan, cost estimating and scheduling, and technical and management plans. (WHK)

  6. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-04-01

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

  7. Nuclear design and technical development required for ISER plant

    International Nuclear Information System (INIS)

    Yokoyama, Takashi; Yamano, Naoki.

    1987-01-01

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

  8. Final priority; technical assistance to improve state data capacity--National Technical Assistance Center to improve state capacity to accurately collect and report IDEA data. Final priority.

    Science.gov (United States)

    2013-05-20

    The Assistant Secretary for Special Education and Rehabilitative Services announces a priority under the Technical Assistance to Improve State Data Capacity program. The Assistant Secretary may use this priority for competitions in fiscal year (FY) 2013 and later years. We take this action to focus attention on an identified national need to provide technical assistance (TA) to States to improve their capacity to meet the data collection and reporting requirements of the Individuals with Disabilities Education Act (IDEA). We intend this priority to establish a TA center to improve State capacity to accurately collect and report IDEA data (Data Center).

  9. 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.

  10. 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

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  12. 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

  13. Final Technical Report: "Representing Endogenous Technological Change in Climate Policy Models: General Equilibrium Approaches"

    Energy Technology Data Exchange (ETDEWEB)

    Ian Sue Wing

    2006-04-18

    The research supported by this award pursued three lines of inquiry: (1) The construction of dynamic general equilibrium models to simulate the accumulation and substitution of knowledge, which has resulted in the preparation and submission of several papers: (a) A submitted pedagogic paper which clarifies the structure and operation of computable general equilibrium (CGE) models (C.2), and a review article in press which develops a taxonomy for understanding the representation of technical change in economic and engineering models for climate policy analysis (B.3). (b) A paper which models knowledge directly as a homogeneous factor, and demonstrates that inter-sectoral reallocation of knowledge is the key margin of adjustment which enables induced technical change to lower the costs of climate policy (C.1). (c) An empirical paper which estimates the contribution of embodied knowledge to aggregate energy intensity in the U.S. (C.3), followed by a companion article which embeds these results within a CGE model to understand the degree to which autonomous energy efficiency improvement (AEEI) is attributable to technical change as opposed to sub-sectoral shifts in industrial composition (C.4) (d) Finally, ongoing theoretical work to characterize the precursors and implications of the response of innovation to emission limits (E.2). (2) Data development and simulation modeling to understand how the characteristics of discrete energy supply technologies determine their succession in response to emission limits when they are embedded within a general equilibrium framework. This work has produced two peer-reviewed articles which are currently in press (B.1 and B.2). (3) Empirical investigation of trade as an avenue for the transmission of technological change to developing countries, and its implications for leakage, which has resulted in an econometric study which is being revised for submission to a journal (E.1). As work commenced on this topic, the U.S. withdrawal

  14. 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.)

  15. 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

  16. 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)

  17. 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)

  18. Water use, productivity and interactions among desert plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Ehleringer, J.R.

    1992-11-17

    Productivity, stability, and competitive interactions among ecosystem components within aridlands are key processes related directly to water in deserts. This project assumes that integrated aspects of plant metabolism provide insight into the structure and function of plant communities and ecosystems. While it is difficult to extrapolate from instantaneous physiological observations to higher scales, such as whole plant performance or to the interactions between plants as components of ecosystems, several key aspects of plant metabolism are scalable. Analyses of stable isotopic composition in plant tissues at natural abundance levels provide a useful tool that can provide insight into the consequences of physiological processes over temporal and spatial scales. Some plant processes continuously fractionate among light and heavy stable isotopic forms of an element; over time this results in integrated measures of plant metabolism. For example, carbon isotope fractionation during photosynthesis results in leaf carbon isotopic composition that is a measure of the set-point for photosynthetic metabolism and of water-use efficiency. Thus it provides information on the temporal scaling of a key physiological process.

  19. Corrosion-related failures in power plant condensers. Final report

    International Nuclear Information System (INIS)

    Beavers, J.A.; Agrawal, A.K.; Berry, W.E.

    1980-08-01

    A survey of the literature has been conducted for the Electric Power Research Institute on corrosion failures in surface condensers. The survey was directed toward condenser failures in pressurized water reactor (PWR) power plants but includes pertinent literature related to fossil and to other nuclear power plants. It includes literature on reported service failures and on experimental studies that impact on these failures

  20. Final Report: 17th international Symposium on Plant Lipids

    Energy Technology Data Exchange (ETDEWEB)

    Christoph Benning

    2007-03-07

    This meeting covered several emerging areas in the plant lipid field such as the biosynthesis of cuticle components, interorganelle lipid trafficking, the regulation of lipid homeostasis, and the utilization of algal models. Stimulating new insights were provided not only based on research reports based on plant models, but also due to several excellent talks by experts from the yeast field.

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

    International Nuclear Information System (INIS)

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

    1982-10-01

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

  2. 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

  3. 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)

  4. Technical Report (Final): Development of Solid State Reagents for Preparing Radiolabeled Imaging Agents

    Energy Technology Data Exchange (ETDEWEB)

    Kabalka, George W

    2011-05-20

    The goal of this research was on the development of new, rapid, and efficient synthetic methods for incorporating short-lived radionuclides into agents of use in measuring dynamic processes. The initial project period (Year 1) was focused on the preparation of stable, solid state precursors that could be used to efficiently incorporate short-lived radioisotopes into small molecules of use in biological applications (environmental, plant, and animal). The investigation included development and evaluation of new methods for preparing carbon-carbon and carbon-halogen bonds for use in constructing the substrates to be radiolabeled. The second phase (Year 2) was focused on developing isotope incorporation techniques using the stable, boronated polymeric precursors. The final phase (Year 3), was focused on the preparation of specific radiolabeled agents and evaluation of their biodistribution using micro-PET and micro-SPECT. In addition, we began the development of a new series of polymeric borane reagents based on polyethylene glycol backbones.

  5. Remote repair and inspection technics in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

    1986-01-01

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

  6. Vadose zone microbial community structure and activity in metal/radionuclide contaminated sediments. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Balkwill, David L.

    2002-08-17

    This final technical report describes the research carried out during the final two months of the no-cost extension ending 11/14/01. The primary goals of the project were (1) to determine the potential for transformation of Cr(VI) (oxidized, mobile) to Cr(III) (reduced, immobile) under unsaturated conditions as a function of different levels and combinations of (a) chromium, (b) nitrate (co-disposed with Cr), and (c) molasses (inexpensive bioremediation substrate), and (2) to determine population structure and activity in experimental treatments by characterization of the microbial community by signature biomarker analysis and by RT-PCR and terminal restriction fragment length polymorphism (T-RFLP) and 16S ribosomal RNA genes. It was determined early in the one-year no-cost extension period that the T-RFLP approach was problematic in regard to providing information on the identities of microorganisms in the samples examined. As a result, it could not provide the detailed information on microbial community structure that was needed to assess the effects of treatments with chromium, nitrate, and/or molasses. Therefore, we decided to obtain the desired information by amplifying (using TR-PCR, with the same primers used for T-RFLP) and cloning 16S rRNA gene sequences from the same RNA extracts that were used for T-RFLP analysis. We also decided to use a restriction enzyme digest procedure (fingerprinting procedure) to place the clones into types. The primary focus of the research carried out during this report period was twofold: (a) to complete the sequencing of the clones, and (b) to analyze the clone sequences phylogenetically in order to determine the relatedness of the bacteria detected in the samples to each other and to previously described genera and species.

  7. 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

  8. IMPROVING TACONITE PROCESSING PLANT EFFICIENCY BY COMPUTER SIMULATION, Final Report

    Energy Technology Data Exchange (ETDEWEB)

    William M. Bond; Salih Ersayin

    2007-03-30

    This project involved industrial scale testing of a mineral processing simulator to improve the efficiency of a taconite processing plant, namely the Minorca mine. The Concentrator Modeling Center at the Coleraine Minerals Research Laboratory, University of Minnesota Duluth, enhanced the capabilities of available software, Usim Pac, by developing mathematical models needed for accurate simulation of taconite plants. This project provided funding for this technology to prove itself in the industrial environment. As the first step, data representing existing plant conditions were collected by sampling and sample analysis. Data were then balanced and provided a basis for assessing the efficiency of individual devices and the plant, and also for performing simulations aimed at improving plant efficiency. Performance evaluation served as a guide in developing alternative process strategies for more efficient production. A large number of computer simulations were then performed to quantify the benefits and effects of implementing these alternative schemes. Modification of makeup ball size was selected as the most feasible option for the target performance improvement. This was combined with replacement of existing hydrocyclones with more efficient ones. After plant implementation of these modifications, plant sampling surveys were carried out to validate findings of the simulation-based study. Plant data showed very good agreement with the simulated data, confirming results of simulation. After the implementation of modifications in the plant, several upstream bottlenecks became visible. Despite these bottlenecks limiting full capacity, concentrator energy improvement of 7% was obtained. Further improvements in energy efficiency are expected in the near future. The success of this project demonstrated the feasibility of a simulation-based approach. Currently, the Center provides simulation-based service to all the iron ore mining companies operating in northern

  9. 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.)

  10. 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

  11. Final Technical Report - SciDAC Cooperative Agreement: Center for Wave Interactions with Magnetohydrodynamics

    International Nuclear Information System (INIS)

    Schnack, Dalton D.

    2012-01-01

    Final technical report for research performed by Dr. Thomas G. Jenkins in collaboration with Professor Dalton D. Schnack on SciDAC Cooperative Agreement: Center for Wave Interactions with Magnetohydrodyanics, DE-FC02-06ER54899, for the period of 8/15/06 - 8/14/11. This report centers on the Slow MHD physics campaign work performed by Dr. Jenkins while at UW-Madison and then at Tech-X Corporation. To make progress on the problem of RF induced currents affect magnetic island evolution in toroidal plasmas, a set of research approaches are outlined. Three approaches can be addressed in parallel. These are: (1) Analytically prescribed additional term in Ohm's law to model the effect of localized ECCD current drive; (2) Introduce an additional evolution equation for the Ohm's law source term. Establish a RF source 'box' where information from the RF code couples to the fluid evolution; and (3) Carry out a more rigorous analytic calculation treating the additional RF terms in a closure problem. These approaches rely on the necessity of reinvigorating the computation modeling efforts of resistive and neoclassical tearing modes with present day versions of the numerical tools. For the RF community, the relevant action item is - RF ray tracing codes need to be modified so that general three-dimensional spatial information can be obtained. Further, interface efforts between the two codes require work as well as an assessment as to the numerical stability properties of the procedures to be used.

  12. Volatiles combustion in fluidized beds. Final technical report, 4 September 1992--4 June 1995

    Energy Technology Data Exchange (ETDEWEB)

    Pendergrass, R.A. II; Raffensperger, C.; Hesketh, R.P.

    1996-02-29

    The goal of this project is to investigate the conditions in which volatiles will burn within both the dense and freeboard regions of fluidized beds. Experiments using a fluidized bed operated at incipient fluidization are being conducted to characterize the effect of particle surface area, initial fuel concentration, and particle type on the inhibition of volatiles within a fluidized bed. A review of the work conducted under this grant is presented in this Final Technical Report. Both experimental and theoretical work have been conducted to examine the inhibition of the combustion by the fluidized bed material, sand. It has been shown that particulate phase at incipient fluidization inhibits the combustion of propane by free radical destruction at the surface of sand particles within the particulate phase. The implications of these findings is that at bed temperatures lower than the critical temperatures, gas combustion can only occur in the bubble phase or at the top surface of a bubbling fluidized bed. In modeling fluidized bed combustion this inhibition by the particulate phase should be included.

  13. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Field, H C

    1988-03-01

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

  15. Next Generation Nuclear Plant Methods Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-09-01

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

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

    International Nuclear Information System (INIS)

    Field, H.C.

    1988-03-01

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

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

    Science.gov (United States)

    Lyman, Edwin

    2007-04-01

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

  19. Hybrid Cooling for Geothermal Power Plants: Final ARRA Project Report

    Energy Technology Data Exchange (ETDEWEB)

    Bharathan, D.

    2013-06-01

    Many binary-cycle geothermal plants use air as the heat rejection medium. Usually this is accomplished by using an air-cooled condenser (ACC) system to condense the vapor of the working fluid in the cycle. Many air-cooled plants suffer a loss of production capacity of up to 50% during times of high ambient temperatures. Use of limited amounts of water to supplement the performance of ACCs is investigated. Deluge cooling is found to be one of the least-cost options. Limiting the use of water in such an application to less than one thousand operating hours per year can boost plant output during critical high-demand periods while minimizing water use in binary-cycle geothermal power plants.

  20. Preconstruction of the Honey Lake Hybrid Power Plant: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1988-04-30

    The work undertaken under this Contract is the prosecution of the preconstruction activities, including preliminary engineering design, well field development, completion of environmental review and prosecution of permits, and the economic and financial analysis of the facility. The proposed power plant is located in northeastern California in Lassen County, approximately 25 miles east of the town of Susanville. The power plant will use a combination of wood residue and geothermal fluids for power generation. The plant, when fully constructed, will generate a combined net output of approximately 33 megawatts which will be sold to Pacific Gas and Electric Company (PGandE) under existing long-term power sales contracts. Transfer of electricity to the PGandE grid will require construction of a 22-mile transmission line from the power plant to Susanville. 11 refs., 12 figs., 4 tabs.

  1. HVAC systems and nuclear plant safety. Final report, May 1992

    International Nuclear Information System (INIS)

    1992-05-01

    The primary objective of this study was to provide perspective on the overall risk impact of heating, ventilating, and air conditioning (HVAC) system problems. Industry experience with HVAC system problems is documented and analyzed. In addition, the results of 10 plant-specific probabilistic risk assessments (PRA) were reviewed to determine the contribution of HVAC systems to the risk of core damage. The PRAs included in this review cover a broad range of plant types and operating conditions. The review found that the impact of HVAC systems on risk is plant specific. These results exhibit a broad range of frequencies for HVAC contribution to risk, and the percentage of total core damage due to HVAC problems also had a wide variability. Plant-specific differences in design, environment, operation, and maintenance are the primary factors in determining the risk contribution of HVAC systems. (author)

  2. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-09-15

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

  4. 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

  5. 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…

  6. 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.)

  7. 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.

  8. 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…

  9. Waste Isolation Pilot Plant: Final supplement environmental impact statement

    International Nuclear Information System (INIS)

    1990-01-01

    The purpose of this Supplement Environmental Impact Statement (SEIS) is to update the environmental record established in 1980 by evaluating the environmental impacts associated with new information, new circumstances, and proposal modifications. This SEIS evaluates and compares the Proposed Action and two alternatives. This final SEIS for the WIPP project is a revision of the draft SEIS published in April 1989. It includes responses to the public comments received in writing and at the public hearings and revisions of the draft SEIS in response to the public comments. Revisions of importance have been identified in this final SEIS by vertical lines in the margins to highlight changes made in response to comments. Volumes 1 through 3 of the final SEIS contain the text, appendices, and the summary comments and responses, respectively. Volumes 6 through 13 of the final SEIS contain reproductions of all of the comments received on the draft SEIS, and Volumes 4 and 5 contain the indices to Volumes 6 through 13. An Executive Summary and/or Volumes 1 through 5 of the final SEIS have been distributed to those who received the draft SEIS or requested a copy of the final SEIS. Volume 5 contains indices to public comments

  10. 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)

  11. 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)

  12. 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.

  13. 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.

  14. 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)

  15. Human factors review of power plant maintainability. Final report

    International Nuclear Information System (INIS)

    Seminara, J.L.; Parsons, S.O.

    1981-02-01

    Human factors engineering is an interdisciplinary science and technology concerned with shaping the design of machines, facilities, and operational environments to promote safe, efficient, and reliable performance on the part of operators and maintainers of equipment systems. The human factors aspects of five nuclear power plants and four fossil fuel plants were evaluated using such methods as a check list guided observation system, structured interviews with maintenance personnel, direct observation of maintenance tasks, reviews of procedures, and analyses of maintenance errors or accidents by means of the critical incident technique. The study revealed a wide variety of human factors problem areas, most of which are extensively photodocumented. The study recommends that a more systematic and formal approach to ensure that future power plants are human engineered to the needs of maintenance personnel

  16. Feasibility design study. Land-based OTEC plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Brewer, J. H.; Minor, J.; Jacobs, R.

    1979-01-01

    The purpose of this study has been to determine the feasibility of installing 10 MWe (MegaWatt-electric) and 40 MWe land-based OTEC demonstration power plants at two specific sites: Keahole Point on the western shore of the island of Hawaii; and Punta Tuna, on the southeast coast of the main island of Puerto Rico. In addition, the study has included development of design parameters, schedules and budgets for the design, construction and operation of these plants. Seawater systems (intake and discharge pipes) were to be sized so that flow losses were equivalent to those expected with a platform-based OTEC power plant. The power module (components and general arrangement was established based on the TRW design. Results are presented in detail. (WHK)

  17. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

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

  18. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

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

  19. 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.)

  20. Movement of mercury-203 in plants. Final report

    International Nuclear Information System (INIS)

    Gay, D.D.; Butler, G.P.

    1977-10-01

    Seeds of Pisum sativum, varieties Little Marvel and Alaska, were planted in soils contaminated with radioactive ionic mercury, methylmercury or phenylmercury compounds. After saturation, stems, leaves, and pods were harvested and analyzed by gamma spectroscopy. Utilizing a least squares three-way analysis of covariance coupled with a Studentized Range Test, significant differences were noted among the levels of the three mercury compounds in the plants, between mercury levels in the two pea varieties and among mercury levels in the different pea tissues examined. Phenylmercury levels differed consistently from levels of ionic mercury and methylmercury suggesting a separate pathway for it in peas

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-30

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

  2. 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

  3. 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.

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  5. Hydrocarbons and energy from plants: Final report, 1984-1987

    Energy Technology Data Exchange (ETDEWEB)

    Calvin, M.; Otvos, J.; Taylor, S.E.; Nemethy, E.K.; Skrukrud, C.L.; Hawkins, D.R.; Lago, R.

    1988-08-01

    Plant hydrocarbon (isoprenoid) production was investigated as an alternative source to fossil fuels. Because of their high triterpenoid (hydrocarbon) content of 4--8%, Euphorbia lathyris plants were used as a model system for this study. The structure of the E. lathyris triterpenoids was determined, and triterpenoid biosynthesis studied to better understand the metabolic regulation of isoprenoid production. Triterpenoid biosynthesis occurs in two distinct tissue types in E. lathyris plants: in the latex of the laticifer cells; and in the mesophyll cells of the leaf and stem. The latex has been fractionated by centrifugation, and it has been determined that the later steps of isoprenoid biosynthesis, the conversion of mevalonic acid to the triterpenes, are compartmentized within a vacuole. Also identified was the conversion of hydroxymethyl glutaryl-CoA to mevalonic acid, catalyzed by the enzyme Hydroxymethyl glutaryl-CoA Reductase, as a key rate limiting step in isoprenoid biosynthesis. At least two isozymes of this enzyme, one in the latex and another in the leaf plastids, have been identified. Environmental stress has been applied to plants to study changes in carbon allocation. Salinity stress caused a large decrease in growth, smaller decreases in photosynthesis, resulting in a larger allocation of carbon to both hydrocarbon and sugar production. An increase in Hydroxymethyl glutaryl-CoA Reductase activity was also observed when isoprenoid production increased. Other species where also screened for the production of hydrogen rich products such as isoprenoids and glycerides, and their hydrocarbon composition was determined.

  6. Portsmouth Gaseous Diffusion Plant expansion: final environmental statement. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1977-09-01

    Volume 1 is comprised of chapters on: background and description; environmental impacts of add-on gaseous diffusion plant; unavoidable adverse environmental effects; alternatives; relationship between short-term uses and long-term productivity; relationship of program to land-use plans, policies, and controls; irreversible and irretrievable commitments of resources; cost-benefit analysis; and response to comment letters. (LK)

  7. Portsmouth Gaseous Diffusion Plant expansion: final environmental statement. Volume 1

    International Nuclear Information System (INIS)

    1977-09-01

    Volume 1 is comprised of chapters on: background and description; environmental impacts of add-on gaseous diffusion plant; unavoidable adverse environmental effects; alternatives; relationship between short-term uses and long-term productivity; relationship of program to land-use plans, policies, and controls; irreversible and irretrievable commitments of resources; cost-benefit analysis; and response to comment letters

  8. Delays in nuclear power plant construction. Volume I. Final report

    International Nuclear Information System (INIS)

    1977-01-01

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

  9. Scalable data management, analysis and visualization (SDAV) Institute. Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Geveci, Berk [Kitware, Inc., Clifton Park, NY (United States)

    2017-03-28

    The purpose of the SDAV institute is to provide tools and expertise in scientific data management, analysis, and visualization to DOE’s application scientists. Our goal is to actively work with application teams to assist them in achieving breakthrough science, and to provide technical solutions in the data management, analysis, and visualization regimes that are broadly used by the computational science community. Over the last 5 years members of our institute worked directly with application scientists and DOE leadership-class facilities to assist them by applying the best tools and technologies at our disposal. We also enhanced our tools based on input from scientists on their needs. Many of the applications we have been working with are based on connections with scientists established in previous years. However, we contacted additional scientists though our outreach activities, as well as engaging application teams running on leading DOE computing systems. Our approach is to employ an evolutionary development and deployment process: first considering the application of existing tools, followed by the customization necessary for each particular application, and then the deployment in real frameworks and infrastructures. The institute is organized into three areas, each with area leaders, who keep track of progress, engagement of application scientists, and results. The areas are: (1) Data Management, (2) Data Analysis, and (3) Visualization. Kitware has been involved in the Visualization area. This report covers Kitware’s contributions over the last 5 years (February 2012 – February 2017). For details on the work performed by the SDAV institute as a whole, please see the SDAV final report.

  10. Final Technical Report. DeepCwind Consortium Research Program. January 15, 2010 - March 31, 2013

    Energy Technology Data Exchange (ETDEWEB)

    Dagher, Habib [Univ. of Maine, Orono, ME (United States); Viselli, Anthony [Univ. of Maine, Orono, ME (United States); Goupee, Andrew [Univ. of Maine, Orono, ME (United States); Thaler, Jeffrey [Univ. of Maine, Orono, ME (United States); Brady, Damian [Univ. of Maine, Orono, ME (United States); Browne, Peter [HDR, Inc., Omaha, NE (United States); Browning, James [Univ. of Colorado, Boulder, CO (United States); Chung, Jade [Univ. of Maine, Orono, ME (United States); Coulling, Alexander [Univ. of Maine, Orono, ME (United States); Deese, Heather [Island Institute, Rockland, ME (United States); Fowler, Matthew [Univ. of Maine, Orono, ME (United States); Holberton, Rebecca [Univ. of Maine, Orono, ME (United States); Anant, Jain [Intertek, Duluth, GA (United States); Jalbert, Dustin [Univ. of Maine, Orono, ME (United States); Johnson, Theresa [Univ. of Maine, Orono, ME (United States); Jonkman, Jason [National Renewable Energy Laboratory, Golden, CO (United States); Karlson, Benjamin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kimball, Richard [Maine Maritime Academy, Castine, ME (United States); Koo, Bonjun [Technip, Paris (France); Lackner, Matthew [Univ. of Massachusetts, Amherst, MA (United States); Lambrakos, Kostas [Technip, Paris (France); Lankowski, Matthew [Univ. of Maine, Orono, ME (United States); Leopold, Adrienne [Univ. of Maine, Orono, ME (United States); Lim, Ho-Joon [Technip, Paris (France); Mangum, Linda [Univ. of Maine, Orono, ME (United States); Martin, Heather [Univ. of Maine, Orono, ME (United States); Masciola, Marco [National Renewable Energy Laboratory, Golden, CO (United States); Maynard, Melissa [Univ. of Maine, Orono, ME (United States); McCleave, James [Univ. of Maine, Orono, ME (United States); Mizrahi, Robert [New Jersey Audubon Society, Bernardsville, NJ (United States); Molta, Paul [National Renewable Energy Laboratory, Golden, CO (United States); Pershing, Andrew [Gulf of Maine Research Institute, Portland, ME (United States); Pettigrew, Neal [Univ. of Maine, Orono, ME (United States); Prowell, Ian [MMI Engineering, Oakland, CA (United States); Qua, Andrew [Kleinschmidt Associates, Pittsfield, ME (United States); Sherwood, Graham [Gulf of Maine Research Institute, Portland, ME (United States); Snape, Thomas [Univ. of Maine, Orono, ME (United States); Steneck, Robert [Univ. of Maine, Orono, ME (United States); Stewart, Gordon [Univ. of Massachusetts, Amherst, MA (United States); Stockwell, Jason [Gulf of Maine Research Institute, Portland, ME (United States); Swift, Andrew H. P. [Texas Tech Univ., Lubbock, TX (United States); Thomas, Dale [Maine Maritime Academy, Castine, ME (United States); Viselli, Elizabeth [Univ. of Maine, Orono, ME (United States); Zydlewski, Gayle [Univ. of Maine, Orono, ME (United States)

    2013-06-11

    This is the final technical report for the U.S. Department of Energy-funded program, DE-0002981: DeepCwind Consortium Research Program. The project objective was the partial validation of coupled models and optimization of materials for offshore wind structures. The United States has a great opportunity to harness an indigenous abundant renewable energy resource: offshore wind. In 2010, the National Renewable Energy Laboratory (NREL) estimated there to be over 4,000 GW of potential offshore wind energy found within 50 nautical miles of the US coastlines (Musial and Ram, 2010). The US Energy Information Administration reported the total annual US electric energy generation in 2010 was 4,120 billion kilowatt-hours (equivalent to 470 GW) (US EIA, 2011), slightly more than 10% of the potential offshore wind resource. In addition, deep water offshore wind is the dominant US ocean energy resource available comprising 75% of the total assessed ocean energy resource as compared to wave and tidal resources (Musial, 2008). Through these assessments it is clear offshore wind can be a major contributor to US energy supplies. The caveat to capturing offshore wind along many parts of the US coast is deep water. Nearly 60%, or 2,450 GW, of the estimated US offshore wind resource is located in water depths of 60 m or more (Musial and Ram, 2010). At water depths over 60 m building fixed offshore wind turbine foundations, such as those found in Europe, is likely economically infeasible (Musial et al., 2006). Therefore floating wind turbine technology is seen as the best option for extracting a majority of the US offshore wind energy resource. Volume 1 - Test Site; Volume 2 - Coupled Models; and Volume 3 - Composite Materials

  11. Hurricane Resilient Wind Plant Concept Study Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Dibra, Besart [Keystone Engineering Inc., Vonore, TN (United States); Finucane, Zachary [Keystone Engineering Inc., Vonore, TN (United States); Foley, Benjamin [Keystone Engineering Inc., Vonore, TN (United States); Hall, Rudy [Keystone Engineering Inc., Vonore, TN (United States); Damiani, Rick [National Renewable Energy Lab. (NREL), Golden, CO (United States); Maples, Benjamin [National Renewable Energy Lab. (NREL), Golden, CO (United States); Parker, Zachary [National Renewable Energy Lab. (NREL), Golden, CO (United States); Robertson, Amy [National Renewable Energy Lab. (NREL), Golden, CO (United States); Scott, George [National Renewable Energy Lab. (NREL), Golden, CO (United States); Stehly, Tyler [National Renewable Energy Lab. (NREL), Golden, CO (United States); Wendt, Fabian [National Renewable Energy Lab. (NREL), Golden, CO (United States); Andersen, Mads Boel Overgaard [Siemens Wind Power A/S, Brande (Denmark); Standish, Kevin [Siemens Wind Power A/S, Brande (Denmark); Lee, Ken [Wetzel Engineering Inc., Round Rock, TX (United States); Raina, Amool [Wetzel Engineering Inc., Round Rock, TX (United States); Wetzel, Kyle [Wetzel Engineering Inc., Round Rock, TX (United States); Musial, Walter [National Renewable Energy Lab. (NREL), Golden, CO (United States); Schreck, Scott [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2016-10-01

    Hurricanes occur over much of the U.S. Atlantic and Gulf coasts, from Long Island to the U.S.-Mexico border, encompassing much of the nation's primary offshore wind resource. Category 5 hurricanes have made landfall as far north as North Carolina, with Category 3 hurricanes reaching New York with some frequency. Along the US West coast, typhoons strike with similar frequency and severity. At present, offshore wind turbine design practices do not fully consider the severe operating conditions imposed by hurricanes. Although universally applied to most turbine designs, International Electrotechnical Commission (IEC) standards do not sufficiently address the duration, directionality, magnitude, or character of hurricanes. To assess advanced design features that could mitigate hurricane loading in various ways, this Hurricane-Resilient Wind Plant Concept Study considered a concept design study of a 500-megawatt (MW) wind power plant consisting of 10-MW wind turbines deployed in 25-meter (m) water depths in the Western Gulf of Mexico. This location was selected because hurricane frequency and severity provided a unique set of design challenges that would enable assessment of hurricane risk and projection of cost of energy (COE) changes, all in response to specific U.S. Department of Energy (DOE) objectives. Notably, the concept study pursued a holistic approach that incorporated multiple advanced system elements at the wind turbine and wind power plant levels to meet objectives for system performance and reduced COE. Principal turbine system elements included a 10-MW rotor with structurally efficient, low-solidity blades; a lightweight, permanent-magnet, direct-drive generator, and an innovative fixed substructure. At the wind power plant level, turbines were arrayed in a large-scale wind power plant in a manner aimed at balancing energy production against capital, installation, and operation and maintenance (O&M) costs to achieve significant overall reductions in

  12. 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

  13. 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)

  14. High-Efficiency Nitride-Based Solid-State Lighting. Final Technical Progress Report

    International Nuclear Information System (INIS)

    Paul T. Fini; Shuji Nakamura

    2005-01-01

    In this final technical progress report we summarize research accomplished during Department of Energy contract DE-FC26-01NT41203, entitled ''High-Efficiency Nitride-Based Solid-State Lighting''. Two teams, from the University of California at Santa Barbara (Principle Investigator: Dr. Shuji Nakamura) and the Lighting Research Center at Rensselaer Polytechnic Institute (led by Dr. N. Narendran), pursued the goals of this contract from thin film growth, characterization, and packaging/luminaire design standpoints. The UCSB team initially pursued the development of blue gallium nitride (GaN)-based vertical-cavity surface-emitting lasers, as well as ultraviolet GaN-based light emitting diodes (LEDs). In Year 2, the emphasis shifted to resonant-cavity light emitting diodes, also known as micro-cavity LEDs when extremely thin device cavities are fabricated. These devices have very directional emission and higher light extraction efficiency than conventional LEDs. Via the optimization of thin-film growth and refinement of device processing, we decreased the total cavity thickness to less than 1 (micro)m, such that micro-cavity effects were clearly observed and a light extraction efficiency of over 10% was reached. We also began the development of photonic crystals for increased light extraction, in particular for so-called ''guided modes'' which would otherwise propagate laterally in the device and be re-absorbed. Finally, we pursued the growth of smooth, high-quality nonpolar a-plane and m-plane GaN films, as well as blue light emitting diodes on these novel films. Initial nonpolar LEDs showed the expected behavior of negligible peak wavelength shift with increasing drive current. M-plane LEDs in particular show promise, as unpackaged devices had unsaturated optical output power of ∼ 3 mW at 200 mA drive current. The LRC's tasks were aimed at developing the subcomponents necessary for packaging UCSB's light emitting diodes, and packaging them to produce a white light

  15. 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)

  16. 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)

  17. 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

  18. 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)

  19. 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

  20. Methodology and application of surrogate plant PRA analysis to the Rancho Seco Power Plant: Final report

    International Nuclear Information System (INIS)

    Gore, B.F.; Huenefeld, J.C.

    1987-07-01

    This report presents the development and the first application of generic probabilistic risk assessment (PRA) information for identifying systems and components important to public risk at nuclear power plants lacking plant-specific PRAs. A methodology is presented for using the results of PRAs for similar (surrogate) plants, along with plant-specific information about the plant of interest and the surrogate plants, to infer important failure modes for systems of the plant of interest. This methodology, and the rationale on which it is based, is presented in the context of its application to the Rancho Seco plant. The Rancho Seco plant has been analyzed using PRA information from two surrogate plants. This analysis has been used to guide development of considerable plant-specific information about Rancho Seco systems and components important to minimizing public risk, which is also presented herein

  1. 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.

  2. 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.

  3. Recovery Act: Alpena Biorefinery and Alpena Biorefinery Lignin Separation Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Retsina, Theodora [American Process Inc., Atlanta, GA (United States)

    2016-12-19

    The Alpena Biorefinery (AB) was constructed in Alpena, Michigan, at the Decorative Panels International hardboard manufacturing facility. The goal of the AB was to demonstrate a modular, technically successful, and financially viable process of making cellulosic ethanol from woody biomass extract at wood processing facilities. At full capacity, the AB can produce 894,200 gallons per year of cellulosic ethanol and 696,000 gallons per year of aqueous potassium acetate, using extract from northern hardwood and aspen woodchips feedstock. The project objectives and the value proposition of AB promote the national goals of energy independence, greenhouse gas reduction, and green job creation and retention. A successful outcome of the Alpena Biorefinery project has been commercial sales of the first ever cellulosic ethanol RINS generated from woody biomass in the US, under the EPA’s Renewable Fuels Standard Program. We believe that American Process is also likely the first company in the world to produce commercial quantities of cellulosic ethanol from mixed forest residue. Life Cycle Analysis performed by Michigan Institute of Technology found that the entire life cycle greenhouse gas emissions from the plant’s cellulosic ethanol were only 25 percent that of petroleum-based gasoline. They found the potassium acetate runway de-icer coproduct generates up to 45 percent less greenhouse gases than the production of conventional potassium acetate. The Alpena Biorefinery project created 31 permanent jobs for direct employees and helped retain 200 jobs associated with the existing Decorative Panels International facility, by increasing its economic viability through significant savings in waste water treatment costs. The AB project has been declared a Michigan Center of Energy Excellence and was awarded a $4 million State of Michigan grant. The project also received New Market Tax Credit financing for locating in an economically distressed community. All other equity funds

  4. Baseload Nitrate Salt Central Receiver Power Plant Design Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Tilley, Drake [Abengoa Solar LLC, Lakewood, CO (United States); Kelly, Bruce [Abengoa Solar LLC, Lakewood, CO (United States); Burkholder, Frank [Abengoa Solar LLC, Lakewood, CO (United States)

    2014-12-12

    The objectives of the work were to demonstrate that a 100 MWe central receiver plant, using nitrate salt as the receiver coolant, thermal storage medium, and heat transport fluid in the steam generator, can 1) operate, at full load, for 6,400 hours each year using only solar energy, and 2) satisfy the DOE levelized energy cost goal of $0.09/kWhe (real 2009 $). To achieve these objectives the work incorporated a large range of tasks relating to many different aspects of a molten salt tower plant. The first Phase of the project focused on developing a baseline design for a Molten Salt Tower and validating areas for improvement. Tasks included a market study, receiver design, heat exchanger design, preliminary heliostat design, solar field optimization, baseline system design including PFDs and P&IDs and detailed cost estimate. The baseline plant met the initial goal of less than $0.14/kWhe, and reinforced the need to reduce costs in several key areas to reach the overall $0.09/kWhe goal. The major improvements identified from Phase I were: 1) higher temperature salt to improve cycle efficiency and reduce storage requirements, 2) an improved receiver coating to increase the efficiency of the receiver, 3) a large receiver design to maximize storage and meet the baseload hours objective, and 4) lower cost heliostat field. The second Phase of the project looked at advancing the baseline tower with the identified improvements and included key prototypes. To validate increasing the standard solar salt temperature to 600 °C a dynamic test was conducted at Sandia. The results ultimately proved the hypothesis incorrect and showed high oxide production and corrosion rates. The results lead to further testing of systems to mitigate the oxide production to be able to increase the salt temperature for a commercial plant. Foster Wheeler worked on the receiver design in both Phase I and Phase II looking at both design and lowering costs utilizing commercial fossil boiler

  5. Vehicle infrastructure integration proof of concept : technical description--vehicle : final report

    Science.gov (United States)

    2009-05-19

    This report provides the technical description of the VII system developed for the Cooperative Agreement VII Program between the USDOT and the VII Consortium. The basic architectural elements are summarized and detailed descriptions of the hardware a...

  6. Strengthening the fission reactor nuclear science and engineering program at UCLA. Final technical report

    International Nuclear Information System (INIS)

    Okrent, D.

    1997-01-01

    This is the final report on DOE Award No. DE-FG03-92ER75838 A000, a three year matching grant program with Pacific Gas and Electric Company (PG and E) to support strengthening of the fission reactor nuclear science and engineering program at UCLA. The program began on September 30, 1992. The program has enabled UCLA to use its strong existing background to train students in technological problems which simultaneously are of interest to the industry and of specific interest to PG and E. The program included undergraduate scholarships, graduate traineeships and distinguished lecturers. Four topics were selected for research the first year, with the benefit of active collaboration with personnel from PG and E. These topics remained the same during the second year of this program. During the third year, two topics ended with the departure o the students involved (reflux cooling in a PWR during a shutdown and erosion/corrosion of carbon steel piping). Two new topics (long-term risk and fuel relocation within the reactor vessel) were added; hence, the topics during the third year award were the following: reflux condensation and the effect of non-condensable gases; erosion/corrosion of carbon steel piping; use of artificial intelligence in severe accident diagnosis for PWRs (diagnosis of plant status during a PWR station blackout scenario); the influence on risk of organization and management quality; considerations of long term risk from the disposal of hazardous wastes; and a probabilistic treatment of fuel motion and fuel relocation within the reactor vessel during a severe core damage accident

  7. Radiation effects on organic materials in nuclear plants. Final report

    International Nuclear Information System (INIS)

    Bruce, M.B.; Davis, M.V.

    1981-11-01

    A literature search was conducted to identify information useful in determining the lowest level at which radiation causes damage to nuclear plant equipment. Information was sought concerning synergistic effects of radiation and other environmental stresses. Organic polymers are often identified as the weak elements in equipment. Data on radiation effects are summarized for 50 generic name plastics and 16 elastomers. Coatings, lubricants, and adhesives are treated as separate groups. Inorganics and metallics are considered briefly. With a few noted exceptions, these are more radiation resistant than organic materials. Some semiconductor devices and electronic assemblies are extremely sensitive to radiation. Any damage threshold including these would be too low to be of practical value. With that exception, equipment exposed to less than 10 4 rads should not be significantly affected. Equipment containing no Teflon should not be significantly affected by 10 5 rads. Data concerning synergistic effects and radiation sensitization are discussed. The authors suggest correlations between the two effects

  8. Trimode optimizes hybrid power plants. Final report: Phase 2

    Energy Technology Data Exchange (ETDEWEB)

    O`Sullivan, G.A.; O`Sullivan, J.A. [Abacus Controls, Inc., Somerville, NJ (United States)

    1998-07-01

    In the Phase 2 project, Abacus Controls Inc. did research and development of hybrid systems that combine the energy sources from photovoltaics, batteries, and diesel-generators and demonstrated that they are economically feasible for small power plants in many parts of the world. The Trimode Power Processor reduces the fuel consumption of the diesel-generator to its minimum by presenting itself as the perfect electrical load to the generator. A 30-kW three-phase unit was tested at Sandia National Laboratories to prove its worthiness in actual field conditions. The use of photovoltaics at remote locations where reliability of supply requires a diesel-generator will lower costs to operate by reducing the run time of the diesel generator. The numerous benefits include longer times between maintenance for the diesel engine and better power quality from the generator. 32 figs.

  9. Power plant system assessment. Final report. SP-100 Program

    International Nuclear Information System (INIS)

    Anderson, R.V.; Atkins, D.F.; Bost, D.S.

    1983-01-01

    The purpose of this assessment was to provide system-level insights into 100-kWe-class space reactor electric systems. Using these insights, Rockwell was to select and perform conceptual design studies on a ''most attractive'' system that met the preliminary design goals and requirements of the SP-100 Program. About 4 of the 6 months were used in the selection process. The remaining 2 months were used for the system conceptual design studies. Rockwell completed these studies at the end of FY 1983. This report summarizes the results of the power plant system assessment and describes our choice for the most attractive system - the Rockwell SR-100G System (Space Reactor, 100 kWe, Growth) - a lithium-cooled UN-fueled fast reactor/Brayton turboelectric converter system

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

    International Nuclear Information System (INIS)

    George, H.J.

    1980-07-01

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

  11. 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.)

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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.)

  18. 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.)

  19. Funding nuclear-power-plant decommissioning. Final report

    International Nuclear Information System (INIS)

    Burns, R.E.; Henderson, J.S.; Pollard, W.; Pryor, T.; Chen, Y.M.

    1982-10-01

    The report is organized according to the steps that one might go through when analyzing funding of decommissioning costs. The first step in analyzing decommissioning costs might be to review the present regulatory framework within which decommissioning cost decisions must be made. A description is presented of the present NRC regulations that address the decommissioning of a nuclear power plant. A description is also presented of recent public utility commission activities concerning funding the costs of decommissioning. Possible future trends in NRC regulation are also discussed. The estimation of decommmissioning costs is analyzed. A description of each of the possible decommissoining options is presented. The options of decommissioning include immediate dismantlement, various types of safe storage, and entombment. A discussion is presented of cost estimations for each decommissioning option for nuclear units containing pressurized water reactors and boiling water reactors. A description is included of the various methods of collecting funds for decommissioning as well as a discussion of their possible regulatory treatment. Material is presented which will provide the reader with background information that might assist state utility commissioners or their staffs in choosing or evaluating one of the financial mechanisms for covering decommissioning costs

  20. Final environmental impact statement. Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1980-10-01

    In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text

  1. Final environmental impact statement. Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text.

  2. BACA Project: geothermal demonstration power plant. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1982-12-01

    The various activities that have been conducted by Union in the Redondo Creek area while attempting to develop the resource for a 50 MW power plant are described. The results of the geologic work, drilling activities and reservoir studies are summarized. In addition, sections discussing the historical costs for Union's involvement with the project, production engineering (for anticipated surface equipment), and environmental work are included. Nineteen geothermal wells have been drilled in the Redondo Creek area of the Valles Caldera: a prominent geologic feature of the Jemez mountains consisting of Pliocene and Pleistocene age volcanics. The Redondo Creek area is within a complex longitudinal graben on the northwest flank of the resurgent structural dome of Redondo Peak and Redondo Border. The major graben faults, with associated fracturing, are geologically plausible candidates for permeable and productive zones in the reservoir. The distribution of such permeable zones is too erratic and the locations too imprecisely known to offer an attractive drilling target. Log analysis indicates there is a preferred mean fracture strike of N31W in the upper portion of Redondo Creek wells. This is approximately perpendicular to the major structure in the area, the northeast-striking Redondo Creek graben. The geothermal fluid found in the Redondo Creek reservoir is relatively benign with low brine concentrations and moderate H/sub 2/S concentrations. Geothermometer calculations indicate that the reservoir temperature generally lies between 500/sup 0/F and 600/sup 0/F, with near wellbore flashing occurring during the majority of the wells' production.

  3. 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)

  4. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility

    International Nuclear Information System (INIS)

    Kirchner, Thomas B.

    2002-01-01

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  5. Final Technical Report Power through Policy: "Best Practices" for Cost-Effective Distributed Wind

    Energy Technology Data Exchange (ETDEWEB)

    Rhoads-Weaver, Heather; Gagne, Matthew; Sahl, Kurt; Orrell, Alice; Banks, Jennifer

    2012-02-28

    Power through Policy: 'Best Practices' for Cost-Effective Distributed Wind is a U.S. Department of Energy (DOE)-funded project to identify distributed wind technology policy best practices and to help policymakers, utilities, advocates, and consumers examine their effectiveness using a pro forma model. Incorporating a customized feed from the Database of State Incentives for Renewables and Efficiency (DSIRE), the Web-based Distributed Wind Policy Comparison Tool (Policy Tool) is designed to assist state, local, and utility officials in understanding the financial impacts of different policy options to help reduce the cost of distributed wind technologies. The project's final products include the Distributed Wind Policy Comparison Tool, found at www.windpolicytool.org, and its accompanying documentation: Distributed Wind Policy Comparison Tool Guidebook: User Instructions, Assumptions, and Case Studies. With only two initial user inputs required, the Policy Tool allows users to adjust and test a wide range of policy-related variables through a user-friendly dashboard interface with slider bars. The Policy Tool is populated with a variety of financial variables, including turbine costs, electricity rates, policies, and financial incentives; economic variables including discount and escalation rates; as well as technical variables that impact electricity production, such as turbine power curves and wind speed. The Policy Tool allows users to change many of the variables, including the policies, to gauge the expected impacts that various policy combinations could have on the cost of energy (COE), net present value (NPV), internal rate of return (IRR), and the simple payback of distributed wind projects ranging in size from 2.4 kilowatts (kW) to 100 kW. The project conducted case studies to demonstrate how the Policy Tool can provide insights into 'what if' scenarios and also allow the current status of incentives to be examined or defended when

  6. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility

    Energy Technology Data Exchange (ETDEWEB)

    Thomas B. Kirchner

    2002-03-22

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  7. 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

  8. 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.

  9. 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)

  10. 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

  11. Final Technical Close out Report University Research Program in Robotics for Environmental Restoration and Waste Management

    International Nuclear Information System (INIS)

    James S. Tulenko; Carl Crane

    2004-01-01

    The report covers the 2003-04 contract period, with a retrospective of the 11 years for the contract, from 1993 to 2004. This includes personnel, technical publications and reports, plus research laboratories employed. Specific information is given in eight research areas, reporting on all technology developed and/or deployed by the University of Florida

  12. Technical procedures for land use, Deaf Smith County site, Texas: Environmental Field Program: Final draft

    International Nuclear Information System (INIS)

    1987-09-01

    This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including land use data acquisition, land use/land cover map compilation, verification of land use/land cover map accuracy, and land use/land cover data analysis. 22 refs., 5 figs

  13. 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

  14. 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

  15. 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)

  16. 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

  17. Final disposal of radioactive wastes. Site selection criteria. Technical and economical factors

    International Nuclear Information System (INIS)

    Granero, J.J.

    1984-01-01

    General considerations, geological and socioeconomical criteria for final disposal of radioactive wastes in geological formations are treated. More attention is given to the final disposal of high level radioactive wastes and different solutions searched abroad which seems of interest for Spain. (author)

  18. Application of a Barrier Filter at a High Purity Synthetic Graphite Plant, CRADA 99-F035, Final Report; FINAL

    International Nuclear Information System (INIS)

    National Energy Technology Laboratory

    2000-01-01

    Superior Graphite Company and the US Department of Energy have entered into a Cooperative Research and Development Agreement (CRADA) to study the application of ceramic barrier filters at its Hopkinsville, Kentucky graphite plant. Superior Graphite Company is a worldwide leader in the application of advanced thermal processing technology to produce high purity graphite and carbons. The objective of the CRADA is to determine the technical and economic feasibility of incorporating the use of high-temperature filters to improve the performance of the offgas treatment system. A conceptual design was developed incorporating the ceramic filters into the offgas treatment system to be used for the development of a capital cost estimate and economic feasibility assessment of this technology for improving particulate removal. This CRADA is a joint effort of Superior Graphite Company, Parsons Infrastructure and Technology Group, and the National Energy Technology Laboratory (NETL) of the US Department of Energy (DOE)

  19. 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

  20. 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

  1. 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

  2. Technical description and evaluation of BWR hybrid power shape monitoring system. Final report

    International Nuclear Information System (INIS)

    Frogner, B.; Ipaktchi, A.; Yang, C.; Grow, R.; Ho, C.; Kiguchi, T.

    1982-03-01

    This report discusses the method for monitoring BWR cores that has been implemented in the Power Shape Monitoring System (PSMS). The approach has been benchmarked to TIP data from three plants and five fuel cycles and the accuracy of the calculations has been evaluated by using gamma scan data from two plants. A coupled neutronics/thermal-hydraulic nodal code (NODE-B/THERM-B) is used in the PSMS. It has been demonstrated that adaptation of this code to partially fit the TIP readings followed by a statistical characterization of the remaining errors results in better accuracy and improved sensitivity for anomaly detection compared to an approach that is entirely dependent upon the detector readings. The computed power distribution has a one-sigma uncertainty of 6% for the nodal power and 4% for the bundle power. This is significantly better than the plant process computers that actually were used for monitoring those two plants where comparisons were made

  3. Final Technical Report: Effects of Changing Water and Nitrogen Inputs on a Mojave Desert Ecosystem

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Stanley, D.; Nowak, Robert S.; Fenstermaker, Lynn, F.; Young, Michael,H.

    2007-11-30

    In order to anticipate the effects of global change on ecosystem function, it is essential that predictive relationships be established linking ecosystem function to global change scenarios. The Mojave Desert is of considerable interest with respect to global change. It contains the driest habitats in North America, and thus most closely approximates the world’s great arid deserts. In order to examine the effects of climate and land use changes, in 2001 we established a long-term manipulative global change experiment, called the Mojave Global Change Facility. Manipulations in this study include the potential effects of (1) increased summer rainfall (75 mm over three discrete 25 mm events), (2) increased nitrogen deposition (10 and 40 kg ha-1), and (3) the disturbance of biological N-fixing crusts . Questions addressed under this grant shared the common hypothesis that plant and ecosystem performance will positively respond to the augmentation of the most limiting resources to plant growth in the Mojave Desert, e.g., water and nitrogen. Specific hypotheses include (1) increased summer rainfall will significantly increase plant production through an alleviation of moisture stress in the dry summer months, (2) N-deposition will increase plant production in this N-limited system, particularly in wet years or in concert with added summer rain, and (3) biological crust disturbance will gradually decrease bio-available N, with concomitant long-term reductions in photosynthesis and ANPP. Individual plant and ecosystem responses to global change may be regulated by biogeochemical processes and natural weather variability, and changes in plant and ecosystem processes may occur rapidly, may occur only after a time lag, or may not occur at all. During the first PER grant period, we observed changes in plant and ecosystem processes that would fall under each of these time-response intervals: plant and ecosystem processes responded rapidly to added summer rain, whereas most

  4. Final Scientific/Technical Report for award DE-FC--07-00AL67053

    International Nuclear Information System (INIS)

    Dixon, Cathy

    2005-01-01

    The project ''Creating an Educational Consortium to Support the Recruitment and Retention of Expertise for the Nuclear Weapons Complex'' was also known as the Advanced Fuel Cycle Initiative (AFCI) University Fellowship Program. Since its inception, the Advanced Fuel Cycle Initiative program and its predecessor, the Advanced Accelerator Applications (AAA) program, have engaged university researchers and students in the sciences necessary to answer technical questions related to reducing high-level waste volumes, optimizing the economics and performance of Yucca Mountain, reducing the technical need for a second repository, reducing the long-term inventories of plutonium in spent fuel, and enabling the proliferation-resistant recovery of the energy contained in spent fuel. The Advanced Fuel Cycle University Fellowship Program is intended to support top students across the nation in a variety of disciplines that will be required to support transmutation research and technology development in the coming decades

  5. Final Technical Report: "Achieving Regional Energy Efficiency Potential in the Southeast”

    Energy Technology Data Exchange (ETDEWEB)

    Mahoney, Mandy [Southeast Energy Efficiency Alliance (SEEA), Atlanta, GA (United States)

    2018-03-07

    The overall objective of this award was to facilitate sharing of DOE resources and best practices as well as provide technical assistance to key stakeholders to support greater compliance with energy efficiency standards and increased energy savings. The outcomes of this award include greater awareness among key stakeholders on energy efficiency topics, increased deployment and utilization of DOE resources, and effective policies and programs to support energy efficiency in the Southeast.

  6. National Alliance for Advanced Biofuels and Bio-Products Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Olivares, Jose A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Baxter, Ivan [US Dept. of Agriculture (USDA)., Washington, DC (United States); Brown, Judith [Univ. of Arizona, Tucson, AZ (United States); Carleton, Michael [Matrix Genetics, Seattle, WA (United States); Cattolico, Rose Anne [Univ. of Washington, Seattle, WA (United States); Taraka, Dale [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Detter, John C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Devarenne, Timothy P. [Texas Agrilife Research, College Station, TX (United States); Dutcher, Susan K. [Washington Univ., St. Louis, MO (United States); Fox, David T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Goodenough, Ursula [Washington Univ., St. Louis, MO (United States); Jaworski, Jan [Donald Danforth Plant Science Center, St. Louis, MO (United States); Kramer, David [Michigan State Univ., East Lansing, MI (United States); Lipton, Mary S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); McCormick, Margaret [Matrix Genetics, Seattle, WA (United States); Merchant, Sabeeha [Univ. of California, Los Angeles, CA (United States); Molnar, Istvan [Univ. of Arizona, Tucson, AZ (United States); Panisko, Ellen A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pellegrini, Matteo [Univ. of California, Los Angeles, CA (United States); Polle, Juergen [City Univ. (CUNY), NY (United States). Brooklyn College; Sabarsky, Martin [Cellana, Inc., San Diego, CA (United States); Sayre, Richard T. [New Mexico Consortium, Los Alamos, NM (United States); Starkenburg,, Shawn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stormo, Gary [Washington Univ., St. Louis, MO (United States); Twary, Scott N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Unkefer, Clifford J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Unkefer, Pat J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yuan, Joshua S. [Texas Agrilife Research, College Station, TX (United States); Arnold, Bob [Univ. of Arizona, Tucson, AZ (United States); Bai, Xuemei [Cellana, Inc., San Diego, CA (United States); Boeing, Wiebke [New Mexico State Univ., Las Cruces, NM (United States); Brown, Lois [Texas Agrilife Research, College Station, TX (United States); Gujarathi, Ninad [Reliance Industries Limited, Mumbai (India); Huesemann, Michael [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lammers, Pete [New Mexico State Univ., Las Cruces, NM (United States); Laur, Paul [Eldorado Biofuels, Santa Fe, NM (United States); Khandan, Nirmala [New Mexico State Univ., Las Cruces, NM (United States); Parsons, Ronald [Solix BioSystems, Fort Collins, CO (United States); Samocha, Tzachi [Texas Agrilife Research, College Station, TX (United States); Thomasson, Alex [Texas Agrilife Research, College Station, TX (United States); Unc, Adrian [New Mexico State Univ., Las Cruces, NM (United States); Waller, Pete [Univ. of Arizona, Tucson, AZ (United States); Bonner, James [Clarkson Univ., Potsdam, NY (United States); Coons, Jim [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fernando, Sandun [Texas Agrilife Research, College Station, TX (United States); Goodall, Brian [Valicor Renewables, Dexter, MI (United States); Kadam, Kiran [Valicor Renewables, Dexter, MI (United States); Lacey, Ronald [Texas Agrilife Research, College Station, TX (United States); Wei, Liu [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Marrone, Babs [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Nikolov, Zivko [Texas Agrilife Research, College Station, TX (United States); Trewyn, Brian [Colorado School of Mines, Golden, CO (United States); Albrecht, Karl [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Capareda, Sergio [Texas Agrilife Research, College Station, TX (United States); Cheny, Scott [Diversified Energy, Gilbert, AZ (United States); Deng, Shuguang [New Mexico State Univ., Las Cruces, NM (United States); Elliott, Douglas [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cesar, Granda [Terrabon, LLC, Bryan, TX (United States); Hallen, Richard [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lupton, Steven [UOP Honeywell Co, LLC, Des Plaines, IL (United States); Lynch, Sharry [UOP Honeywell Co, LLC, Des Plaines, IL (United States); Marchese, Anthony [Colorado State Univ., Fort Collins, CO (United States); Nieweg, Jennifer [Albemarle Catilin, Ames, IA (United States); Ogden, Kimberly [Univ. of Arizona, Tucson, AZ (United States); Oyler, James [Genifuel, Salt Lake City, UT (United States); Reardon, Ken [Colorado State Univ., Fort Collins, CO (United States); Roberts, William [North Carolina State Univ., Raleigh, NC (United States); Sams, David [Albemarle Catilin, Ames, IA (United States); Schaub, Tanner [New Mexico State Univ., Las Cruces, NM (United States); Silks, Pete [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Archibeque, Shawn [Colorado State Univ., Fort Collins, CO (United States); Foster, James [Texas Agrilife Research, College Station, TX (United States); Gaitlan, Delbert [Texas Agrilife Research, College Station, TX (United States); Lawrence, Addison [Texas Agrilife Research, College Station, TX (United States); Lodge-Ivey, Shanna [New Mexico State Univ., Las Cruces, NM (United States); Wickersham, Tyron [Texas Agrilife Research, College Station, TX (United States); Blowers, Paul [Univ. of Arizona, Tucson, AZ (United States); Davis, Ryan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Downes, C. Meghan [New Mexico State Univ., Las Cruces, NM (United States); Dunlop, Eric [Pan Pacific Technologies Pty. Ltd., Adelaide (Australia); Frank, Edward [Argonne National Lab. (ANL), Argonne, IL (United States); Handler, Robert [Michigan Technological Univ., Houghton, MI (United States); Newby, Deborah [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pienkos, Philip [National Renewable Energy Lab. (NREL), Golden, CO (United States); Richardson, James [Texas Agrilife Research, College Station, TX (United States); Seider, Warren [Univ. of Pennsylvania, Philadelphia, PA (United States); Shonnard, David [Michigan Technological Univ., Houghton, MI (United States); Skaggs, Richard [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-09-30

    The main objective of NAABB was to combine science, technology, and engineering expertise from across the nation to break down critical technical barriers to commercialization of algae-based biofuels. The approach was to address technology development across the entire value chain of algal biofuels production, from selection of strains to cultivation, harvesting, extraction, fuel conversion, and agricultural coproduct production. Sustainable practices and financial feasibility assessments ununderscored the approach and drove the technology development.

  7. Development of a Foam OTEC System. Final technical report for Fiscal Year 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    Research on Development of a Foam OTEC System, as carried out at Carnegie-Mellon University from October 1, 1978 through September 30, 1979, is described. To a brief section summarizing highlights of research results are appended 12 technical reports which detail specific sections of the program. The work described is continuing and a proposal is currently being submitted to provide support in fiscal 1980.

  8. International Standards Development for Marine and Hydrokinetic Renewable Energy - Final Report on Technical Status

    Energy Technology Data Exchange (ETDEWEB)

    Rondorf, Neil E.; Busch, Jason; Kimball, Richard

    2011-10-29

    This report summarizes the progress toward development of International Standards for Marine and Hydrokinetic Renewable Energy, as funded by the U.S. Department of Energy (DOE) under the International Electrotechnical Commission (IEC) Technical Committee 114. The project has three main objectives: 1. Provide funding to support participation of key U.S. industry technical experts in 6 (originally 4) international working groups and/or project teams (the primary standards-making committees) and to attend technical meetings to ensure greater U.S. involvement in the development of these standards. 2. Provide a report to DOE and industry stakeholders summarizing the IEC standards development process for marine and hydrokinetic renewable energy, new international standards and their justifications, and provide standards guidance to industry members. 3. Provide a semi-annual (web-based) newsletter to the marine renewable energy community. The newsletter will educate industry members and stakeholders about the processes, progress, and needs of the US efforts to support the international standards development effort. The newsletter is available at www.TC114.us

  9. 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.

  10. Technical report on material selection and processing guidelines for BWR [boiling water reactor] coolant pressure boundary piping: Final report

    International Nuclear Information System (INIS)

    Hazelton, W.S.; Koo, W.H.

    1988-01-01

    This report provides the technical bases for the NRC staff's revised recommended methods to control the intergranular stress corrosion cracking susceptibility of BWR piping. For piping that does not fully comply with the material selection, testing, and processing guideline combinations of this document, varying degrees of augmented inservice inspection are recommended. This revision also includes guidance and NRC staff recommendations (not requirements) regarding crack evaluation and weld overlay repair methods for long-term operation or for continuing interim operation of plants until a more permanent solution is implemented

  11. 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)

  12. Final Technical Report to proposal DE-FG02-95ER20187

    Energy Technology Data Exchange (ETDEWEB)

    Dangl, Jeff [Univ. of North Carolina, Chapel Hill, NC (United States)

    2015-03-01

    Our long term aim over our many years of generous DOE-BES funding was to understand mechanisms by which the pathogen virulence factors (called ‘type III effectors’) AvrRpm1 and AvrB activate the plant NLR immune receptor RPM1. In general effectors are delivered from the infecting bacteria into host cells by the type III pilus, where they manipulate host machinery to help pathogens overcome host defense. Delivery of effectors to increase virulence is a general feature of all classes of plant pathogens, from fungi to insects to oomcyetes and bacteria. Hence, understanding the overall diversity of effectors, their myriad delivery systems and their effectors on host cell biology, is of central importance in plant immunology.

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

    International Nuclear Information System (INIS)

    Kofron, K.L.

    1994-01-01

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

  14. 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

  15. The SocioEconomic Analysis of Repository Siting (SEARS): Technical description: Final draft

    International Nuclear Information System (INIS)

    1984-11-01

    Socioeconomic impacts must be assessed both for the near term and for the future. One means of addressing the need for the assessment of such impacts has been through the development of the computerized socioeconomic assessment model called the SocioEconomic Analysis of Repository Siting (SEARS) model. The SEARS model was developed for the Battelle Project Management Division. It was refined and adapted from state-of-the-art computerized projection models and thoroughly validated and is now available for use in projecting the likely socioeconomic impacts of a repository facility. This Technical Description is one of six major products that describe the SEARS modeling system. 61 refs., 11 figs., 9 tabs

  16. Technical analysis of US Army Weapons Systems and related advanced technologies of military interest. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-06-14

    This report summarizes the activities and accomplishments of an US Army technology security project designed to identify and develop effective policy guidelines for militarily critical technologies in specific Army systems and in broad generic technology areas of military interest, Individual systems analyses are documented in separate Weapons Systems Technical Assessments (WSTAs) and the general generic technology areas are evaluated in the Advanced Technology Assessment Reports (ATARs), However, specific details of these assessments are not addressed here, only recommendations regarding aspects of the defined approach, methodology, and format are provided and discussed.

  17. Tectonic history of the terrestrial planets. Final technical report, 1 October 1976-30 September 1989

    International Nuclear Information System (INIS)

    Solomon, S.C.

    1990-02-01

    It is impossible in a single brief summary to convey the full range of research results that have come from this project over the last 13 years. The sweep of subjects covered ranges widely over the broad areas of the thermal and tectonic evolution of the terrestrial planets. A full list of all publications supported by this grant is presented. The list includes 48 published journal articles, 2 papers currently in press, 3 chapters of books, 4 M.I.T. theses, 1 technical report, and 107 published abstracts and extended abstracts. All of these publications were submitted separately to NASA at the time of publication or submission

  18. Final Technical Report of the project "Controlling Quantum Information by Quantum Correlations"

    Energy Technology Data Exchange (ETDEWEB)

    Girolami, Davide [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-01-17

    The report describes hypotheses, aims, methods and results of the project 20170675PRD2, “Controlling Quantum Information by Quantum Correlations”, which has been run from July 31, 2017 to January 7, 2018. The technical work has been performed by Director’s Fellow Davide Girolami of the T-4 Division, Physics of Condensed Matter and Complex Systems, under the supervision of Wojciech Zurek (T-4), Lukasz Cincio (T-4), and Marcus Daniels (CCS-7). The project ended as Davide Girolami has been converted to J. R. Oppenheimer Fellow to work on the project 20180702PRD1, “Optimal Control of Quantum Machines”, started on January 8, 2018.

  19. Achieving Hydrogen Storage Goals through High-Strength Fiber Glass - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Li, Hong [PPG Industries, Inc., Cheswick, PA (United States); Johnson, Kenneth I. [PPG Industries, Inc., Cheswick, PA (United States); Newhouse, Norman L. [PPG Industries, Inc., Cheswick, PA (United States)

    2017-06-05

    Led by PPG and partnered with Hexagon Lincoln and Pacific Northwest National Laboratory (PNNL), the team recently carried out a project “Achieving Hydrogen Storage Goals through High-Strength Fiber Glass”. The project was funded by DOE’s Fuel Cell Technologies office within the Office of Energy Efficiency and Renewable Energy, starting on September 1, 2014 as a two-year project to assess technical and commercial feasibilities of manufacturing low-cost, high-strength glass fibers to replace T700 carbon fibers with a goal of reducing the composite total cost by 50% of the existing, commercial 700 bar hydrogen storage tanks used in personal vehicles.

  20. 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.

  1. 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.

  2. Combined cycle solar central receiver hybrid power system study. Volume III. Appendices. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-11-01

    A design study for a 100 MW gas turbine/steam turbine combined cycle solar/fossil-fuel hybrid power plant is presented. This volume contains the appendices: (a) preconceptual design data; (b) market potential analysis methodology; (c) parametric analysis methodology; (d) EPGS systems description; (e) commercial-scale solar hybrid power system assessment; and (f) conceptual design data lists. (WHK)

  3. Final technical report: Commercialization of the Biofine technology for levulinic acid production from paper sludge

    Energy Technology Data Exchange (ETDEWEB)

    Fitzpatrick, Stephen W.

    2002-04-23

    This project involved a three-year program managed by BioMetics, Inc. (Waltham, MA) to demonstrate the commercial feasibility of Biofine thermochemical process technology for conversion of cellulose-containing wastes or renewable materials into levulinic acid, a versatile platform chemical. The program, commencing in October 1995, involved the design, procurement, construction and operation of a plant utilizing the Biofine process to convert 1 dry ton per day of paper sludge waste. The plant was successfully designed, constructed, and commissioned in 1997. It was operated for a period of one year on paper sludge from a variety of source paper mills to collect data to verify the design for a commercial scale plant. Operational results were obtained for four different feedstock varieties. Stable, continuous operation was achieved for two of the feedstocks. Continuous operation of the plant at demonstration scale provided the opportunity for process optimization, development of operational protocols, operator training and identification of suitable materials of construction for scale up to commercial operation . Separated fiber from municipal waster was also successfully processed. The project team consisted of BioMetics Inc., Great Lakes Chemical Corporation (West Lafayette, IN), and New York State Energy Research and Development Authority (Albany, NY).

  4. Enzymology and Molecular Biology of Cell Wall Biosynthesis. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Peter M. Ray

    2000-04-01

    The following aspects of enzymology of cell wall synthesis were pursued under this cited grant: (1) Isolation of plasma membrane-localized glucan synthase II (GS-II) of pea; (2) Cloning of genes for possible plant GS-II components; (3) Golgi glucan synthase-I (GS-I); and (4) Golgi reversibly glycosylated protein 1 (RGP1).

  5. Harnessing Light: Capitalizing on Optical Science Trends and Challenges for Future Research. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Svedberg, Erik

    2014-02-06

    The committee has during the earlier period finalized their work on the report, Optics and Photonics: Essential Technologies for Our Nation (2013) . The report did undergo review and initial editorial processing. The NRC released a pre-publication report on August 13, 2012. A final report is now available. The study director has been able to practice his skills in running a national academies committee. From a research perspective the grant has generated a report with recommendations to the government. The work itself is the meetings where the committee convened to hear presenters and to discuss the status of optics and photonics as well as writing the report.

  6. Technical program plan for the transitioning, decommissioning, and final disposition focus area

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    Hundreds of aging nuclear materials processing facilities within the Department of Energy`s (DOE) Weapons Complex are now being shut down and deactivated. These facilities, situated throughout the United States, will require a monumental effort to clean up safely and with minimal environmental insult. Current cleanup technologies tend to be labor intensive and expensive, they produce an unacceptably large volume of waste, and they expose workers to radioactive and other hazardous substances. This document describes an emerging program designed to develop and demonstrate new technical approaches to the decontamination and decommissioning (D&D) program for DOE`s nuclear materials processing facilities. Sponsored by the DOE Office of Technology Development within the Office of Environmental Restoration and Waste Management (EM), the program seeks to integrate the strengths of DOE`s technical, managerial, and systems engineering capabilities with those of industry, universities, and other government agencies. Once developed, these technologies will help to provide US industry with a competitive edge in the worldwide market that exists for improved environmental restoration and D&D services.

  7. Final Scientific/Technical Report Solar America Initiative: Solar Outreach and Communications

    Energy Technology Data Exchange (ETDEWEB)

    Weissman, Jane M

    2011-09-10

    The purpose of the Solar America Initiative: Solar Outreach and Communications grant was to promote better communications among stakeholders; address infrastructure barriers to solar energy; and coordinate with industry, the U.S. Department of Energy, national laboratories, states, cities and counties. The Interstate Renewable Energy Council (IREC), a non-profit organization formed in 1982, approached this grant project by establishing a wide range of communication and outreach activities including newsletters, workshops, webinars, model practices and publications; by advancing easy and fair hook-up rules to the utility grid; and by upgrading training based on industry competency standards. The Connecting to the Grid project and the Solar Codes and Standards Public Hearings project offered communication coupled with technical assistance to overcome interconnection, net metering and other regulatory and program barriers. The Workforce Development Project tackled building a strong workforce through quality training and competency assessment programs. IREC's web site, the semi-monthly state and stakeholder newsletter and the metrics report resulted in better communications among stakeholders. Workshops and phone seminars offered technical assistance and kept stakeholders up-to-date on key issues. All of these activities resulted in implementing sustainable solutions to institutional and market barriers to solar energy and getting the right information to the right people.

  8. Technical program plan for the transitioning, decommissioning, and final disposition focus area

    International Nuclear Information System (INIS)

    1994-01-01

    Hundreds of aging nuclear materials processing facilities within the Department of Energy's (DOE) Weapons Complex are now being shut down and deactivated. These facilities, situated throughout the United States, will require a monumental effort to clean up safely and with minimal environmental insult. Current cleanup technologies tend to be labor intensive and expensive, they produce an unacceptably large volume of waste, and they expose workers to radioactive and other hazardous substances. This document describes an emerging program designed to develop and demonstrate new technical approaches to the decontamination and decommissioning (D ampersand D) program for DOE's nuclear materials processing facilities. Sponsored by the DOE Office of Technology Development within the Office of Environmental Restoration and Waste Management (EM), the program seeks to integrate the strengths of DOE's technical, managerial, and systems engineering capabilities with those of industry, universities, and other government agencies. Once developed, these technologies will help to provide US industry with a competitive edge in the worldwide market that exists for improved environmental restoration and D ampersand D services

  9. Final report of the UMTRA independent technical review of TAC audit programs

    International Nuclear Information System (INIS)

    1994-10-01

    This report details the findings of an Independent Technical Review (ITR) of practices and procedures for the Uranium Mill Tailings Remedial Action (UMTRA) Project audit program. The audit program is conducted by Jacobs Engineering Group Inc., the Technical Assistance Contractor (TAC) for the UMTRA Project. The purpose of the ITR was to ensure that the TAC audit program is effective and is conducted efficiently. The ITR was conducted from May 16-20, 1994. A review team observed audit practices in the field, reviewed the TAC audit program's documentation, and discussed the program with TAC staff and management. The format of this report has been developed around EPA guidelines; they comprise most of the major section headings. Each section begins by identifying the criteria that the TAC program is measured against, then describing the approach used by the ITR team to measure each TAC audit program against the criteria. An assessment of each type of audit is then summarized for each component in the following order: Radiological audit summary; Health and safety audit summary; Environmental audit summary; Quality assurance audit summary

  10. 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

  11. 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.

  12. Ion anomalous transport and feedback control. Final technical report, September 1, 1987 - August 31, 1997

    International Nuclear Information System (INIS)

    Sen, A.K.

    1998-01-01

    This final report is comprised of the following six progress reports: Ion Temperature Gradient Instability and Anomalous Transport, July 1989; Ion Temperature Gradient Instability and Anomalous Transport, August 1991; Ion Temperature Gradient Instability and Anomalous Transport, July 1993; Ion Anomalous Transport and Feedback Control, May 1994; Ion Anomalous Transport and Feedback Control, April 1995; and Ion Anomalous Transport and Feedback Control, December 1997

  13. 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.)

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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…

  19. 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

  20. 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

  1. 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

  2. The influence of grazing on surface climatological variables of tallgrass prairie. Final Technical Report

    International Nuclear Information System (INIS)

    Seastedt, T.R.; Dyer, M.I.; Turner, C.L.

    1992-01-01

    Mass and energy exchange between most grassland canopies and the atmosphere are mediated by grazing activities. Ambient temperatures can be increased or decreased by grazers. Data have been assembled from simulated grazing experiments on Konza Prairie Research Natural Area and observations on adjacent pastures grazed by cattle show significant changes in primary production, nutrient content, and bidirectional reflectance characteristics as a function of grazing intensity. The purpose of this research was to provide algorithms that would allow incorporation of grazing effects into models of energy budgets using remote sensing procedures. The approach involved: (1) linking empirical measurements of plant biomass and grazing intensities to remotely sensed canopy reflectance, and (2) using a higher resolution, mechanistic grazing model to derive plant ecophysiological parameters that influence reflectance and other surface climatological variables

  3. Technical Exchange on Improved Design and Performance of High Level Waste Melters - Final Report

    Energy Technology Data Exchange (ETDEWEB)

    SK Sundaram; ML Elliott; D Bickford

    1999-11-19

    SIA Radon is responsible for management of low- and intermediate-level radioactive waste (LILW) produced in Central Russia. In cooperation with Minatom organizations Radon carries out R and D programs on treatment of simulated high level waste (HLW) as well. Radon scientists deal with a study of materials for LILW, HLW, and Nuclear Power Plants (NPP) wastes immobilization, and development and testing of processes and technologies for waste treatment and disposal. Radon is mostly experienced in LILW vitrification. This experience can be carried over to HLW vitrification especially in field of melting systems. The melter chosen as a basic unit for the vitrification plant is a cold crucible. Later on Radon experience in LILW vitrification as well as our results on simulated HLW vitrification are briefly described.

  4. Technical Exchange on Improved Design and Performance of High Level Waste Melters - Final Report

    International Nuclear Information System (INIS)

    Sundaram, S.K.; Elliott, M.L.; Bickford, D.

    1999-01-01

    SIA Radon is responsible for management of low- and intermediate-level radioactive waste (LILW) produced in Central Russia. In cooperation with Minatom organizations Radon carries out R and D programs on treatment of simulated high level waste (HLW) as well. Radon scientists deal with a study of materials for LILW, HLW, and Nuclear Power Plants (NPP) wastes immobilization, and development and testing of processes and technologies for waste treatment and disposal. Radon is mostly experienced in LILW vitrification. This experience can be carried over to HLW vitrification especially in field of melting systems. The melter chosen as a basic unit for the vitrification plant is a cold crucible. Later on Radon experience in LILW vitrification as well as our results on simulated HLW vitrification are briefly described

  5. Mark III LOCA-related hydrodynamic load definition. Generic technical activity B-10. Final report

    International Nuclear Information System (INIS)

    Fields, M.B.; Kudrick, J.A.

    1984-08-01

    This report, prepared by the staff of the Office of Nuclear Reactor Regulation and its consultants at the Brookhaven National Laboratory, provides a discussion of LOCA-related suppression pool hydrodynamic loads in boiling water reactor (BWR) facilities with the Mark III pressure-suppression containment design. Its issuance completes NRC Generic Technical Activity B-10, Behavior of BWR Mark III Containment. On the basis of certain large-scale tests conducted between 1973 and 1979, the General Electric Company developed LOCA-related hydrodynamic load definitions for use in the design of the standard Mark III containment. The staff and its consultants have reviewed these load definitions and their bases and conclude that, with a few specified changes, the proposed load definitions provide conservative loading conditions. The staff approved acceptance criteria for LOCA-related hydrodynamic loads are provided in an appendix

  6. 7th BOC Priestley Conference. Final technical report, May 1, 1994--April 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The 1994 BOC Priestly Conference was held at Bucknell University in Lewisburg, PA, from June 24 through June 27, 1994. This conference, managed by the American Chemical Society (ACS), was a joint celebration with the Royal Society of Chemistry (RSC) commemorating Joseph Priestley`s arrival in the US and his discovery of oxygen. There were 120 attendees. The basic theme of the conference was Oxidants and Oxidation in the Earth`s Atmosphere, with a keynote lecture on the history of ozone. A distinguished group of US and international atmospheric chemists addressed the issues dominating current research and policy agendas. Topics crucial to the atmospheric chemistry of global change and local and regional air pollution were discussed. The program for the conference included four technical sessions on the following topics: Oxidative fate of atmospheric pollutants; Photochemical smog and ozone; Stratospheric ozone; and, Global tropospheric ozone.

  7. Combined cycle solar central receiver hybrid power system study. Final technical report. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-11-01

    This study develops the conceptual design for a commercial-scale (nominal 100 MWe) central receiver solar/fossil fuel hybrid power system with combined cycle energy conversion. A near-term, metallic heat pipe receiver and an advanced ceramic tube receiver hybrid system are defined through parametric and market potential analyses. Comparative evaluations of the cost of power generation, the fuel displacement potential, and the technological readiness of these two systems indicate that the near-term hybrid system has better potential for commercialization by 1990. Based on the assessment of the conceptual design, major cost and performance improvements are projected for the near-term system. Constraints preventing wide-spread use were not identified. Energy storage is not required for this system and analyses show no economic advantages with energy storage provisions. It is concluded that the solar hybrid system is a cost effective alternative to conventional gas turbines and combined cycle generating plants, and has potential for intermediate-load market penetration at 15% annual fuel escalation rate. Due to their flexibility, simple solar/nonsolar interfacing, and short startup cycles, these hybrid plants have significant operating advantages. Utility company comments suggest that hybrid power systems will precede stand-alone solar plants.

  8. Final Technical Report for GO17004 Regulatory Logic: Codes and Standards for the Hydrogen Economy

    Energy Technology Data Exchange (ETDEWEB)

    Nakarado, Gary L. [Regulatory Logic LLC, Golden, CO (United States)

    2017-02-22

    The objectives of this project are to: develop a robust supporting research and development program to provide critical hydrogen behavior data and a detailed understanding of hydrogen combustion and safety across a range of scenarios, needed to establish setback distances in building codes and minimize the overall data gaps in code development; support and facilitate the completion of technical specifications by the International Organization for Standardization (ISO) for gaseous hydrogen refueling (TS 20012) and standards for on-board liquid (ISO 13985) and gaseous or gaseous blend (ISO 15869) hydrogen storage by 2007; support and facilitate the effort, led by the NFPA, to complete the draft Hydrogen Technologies Code (NFPA 2) by 2008; with experimental data and input from Technology Validation Program element activities, support and facilitate the completion of standards for bulk hydrogen storage (e.g., NFPA 55) by 2008; facilitate the adoption of the most recently available model codes (e.g., from the International Code Council [ICC]) in key regions; complete preliminary research and development on hydrogen release scenarios to support the establishment of setback distances in building codes and provide a sound basis for model code development and adoption; support and facilitate the development of Global Technical Regulations (GTRs) by 2010 for hydrogen vehicle systems under the United Nations Economic Commission for Europe, World Forum for Harmonization of Vehicle Regulations and Working Party on Pollution and Energy Program (ECE-WP29/GRPE); and to Support and facilitate the completion by 2012 of necessary codes and standards needed for the early commercialization and market entry of hydrogen energy technologies.

  9. 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)

  10. The chirped-pulse free-electron laser: Final technical report, September 1987--October 1988

    International Nuclear Information System (INIS)

    Moore, G.T.

    1989-01-01

    This is the final report of a theoretical and numerical investigation into the operation of pulsed free-electron lasers in which the electron energy depends on the time of injection into the wiggler. Such energy ''chirping'' over each of a train of electron micropulses injected into an FEL oscillator is expected to give rise to a laser pulse inside the optical resonator with a chirped carrier frequency ω/sub s/(/tau/). 8 refs., 7 figs

  11. 1993-1994 Final technical report for establishing the SECME Model in the District of Columbia

    Energy Technology Data Exchange (ETDEWEB)

    Vickers, R.G.

    1995-12-31

    This is the final report for a program to establish the SECME Model in the District of Columbia. This program has seen the development of a partnership between the District of Columbia Public Schools, the University of the District of Columbia, the Department of Energy, and SECME. This partnership has demonstrated positive achievement in mathematics and science education and learning in students within the District of Columbia.

  12. 'Advancement of KHPS to DOE TRL 7/8' Project - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Adonizio, Mary Ann [Verdant Power Inc., New York, NY (United States); Corren, Dean [Verdant Power Inc., New York, NY (United States); Smith, Ron [Verdant Power Inc., New York, NY (United States); Colby, Jonathan [Verdant Power Inc., New York, NY (United States); Hernandez, Aaron [Verdant Power Inc., New York, NY (United States)

    2016-04-08

    Final Report describing activities performed under the 'Advancement of the KHPS to DOE TRL 7/8' project, including the development of critical component test protocols, testing and analysis of the Gen5 KHPS main shaft seal, and continuing compliance work on approved operational environmental monitoring plans in anticipation of KHPS turbine installation at Verdant Power's Roosevelt Island Tidal Energy (RITE) Project site in New York, NY.

  13. The Institute for Sustained Performance, Energy, and Resilience, University of North Carolina, Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, Robert [Univ. of North Carolina, Chapel Hill, NC (United States)

    2018-01-20

    This is the final report for the UNC component of the SciDAD Institute for Sustained Performance, Energy, and Resilience. In this report, we describe activities on the SUPER project at RENCI at the University of North Carolina at Chapel Hill. While we focus particularly on UNC, we touch on project-wide activities as well as, on interactions with, and impacts on, other projects.

  14. 1993-1994 Final technical report for establishing the SECME Model in the District of Columbia

    International Nuclear Information System (INIS)

    Vickers, R.G.

    1995-01-01

    This is the final report for a program to establish the SECME Model in the District of Columbia. This program has seen the development of a partnership between the District of Columbia Public Schools, the University of the District of Columbia, the Department of Energy, and SECME. This partnership has demonstrated positive achievement in mathematics and science education and learning in students within the District of Columbia

  15. 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

  16. 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

  17. 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

  18. 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.

  19. 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.

  20. 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

  1. 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

  2. Solar central receiver prototype heliostat CDRL item B. d. Final technical report, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Easton, C. R.

    1978-08-01

    This is volume II of a two volume report which presents the results of a study to define a low-cost approach to the production, installation, and operation of heliostats for central receiver solar thermal power plants. Performance and cost analyses are presented, and critical R and D areas are identified. Also, computer printed work sheets are included for heliostat investment, maintenance equipment investment, initial spares investment, and first years operations and maintenance for 2,500, 25,000, 250,000, and 1,000,000 units per year production. (WHK)

  3. Evaluation of the technical and economic feasibility of mirror fusion devices. Final report

    International Nuclear Information System (INIS)

    1976-08-01

    The following four task-reports are included: (1) cost analysis of potassium vapor topping cycle and conventional steam cycle, (2) heat transport and energy conversion system analysis and conceptual cost estimate, (3) plant arrangement, and reactor containment structural design and cost estimate, and (4) coil restraint structure conceptual design and cost estimate. Each of the reports is complete in itself with respect to the particular task concerned. With the exception of Task 1, which was a preliminary examination of potassium topping cycle and steam cycle costs, the cost estimates for Tasks 2, 3, and 4 were performed using the same basic costing guidelines

  4. Evaluation of the technical and economic feasibility of mirror fusion devices. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1976-08-01

    The following four task-reports are included: (1) cost analysis of potassium vapor topping cycle and conventional steam cycle, (2) heat transport and energy conversion system analysis and conceptual cost estimate, (3) plant arrangement, and reactor containment structural design and cost estimate, and (4) coil restraint structure conceptual design and cost estimate. Each of the reports is complete in itself with respect to the particular task concerned. With the exception of Task 1, which was a preliminary examination of potassium topping cycle and steam cycle costs, the cost estimates for Tasks 2, 3, and 4 were performed using the same basic costing guidelines.

  5. Final Technical Report for DOE Grant DE-FG02-91ER20038

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, T. M.

    2001-03-15

    The existence of species within the plant genus Flaveria with differing leaf cell arrangements and photosynthetic schemes (C3, C4, C3-C4) enabled us to identify genetic elements (promoters, 3'UTRs) that are responsible for the regulation of pre-existing metabolic genes in the pattern required for the high-efficiency C4 photosynthetic scheme. We analyzed DNA elements regulating the rbcS, malic enzyme, and malate dehydrogenase gene families in several species of Flaveria, using transient and stable transformation methods.

  6. 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)

  7. Regular Recycling of Wood Ash to Prevent Waste Production (RecAsh). Technical Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Lars E-mail: lars.t.andersson@skogsstyreslen.se

    2007-03-15

    At present, the extraction of harvest residues is predicted to increase in Sweden and Finland. As an effect of the intensified harvesting, the export of nutrients and acid buffering substances from the growth site is also increased. Wood ash could be used to compensate forest soils for such losses. Most wood fuel ash is today often deposited in landfills. If the wood ash is recycled, wood energy is produced without any significant waste production. Ash recycling would therefore contribute to decreasing the production of waste, and to maintaining the chemical quality of forest waters and biological productivity of forest soils in the long term. The project has developed, analysed and demonstrated two regular ash-recycling systems. It has also distributed knowledge gathered about motives for ash recycling as well as technical and administrative solutions through a range of media (handbooks, workshops, field demonstrations, reports, web page and information videos). Hopefully, the project will contribute to decreasing waste problems related to bio-energy production in the EU at large. The project has been organised as a separate structure at the beneficiary and divided in four geographically defined subprojects, one in Finland and three in Sweden (Central Sweden, Northern Sweden, and South-western Sweden). The work in each subproject has been lead by a subproject leader. Each subproject has organised a regional reference group. A project steering committee has been established consisting of senior officials from all concerned partners. The project had nine main tasks with the following main expected deliverables and output: 1. Development of two complete full-scale ash-recycling systems; 2. Production of handbooks of the ash recycling system; 3. Ash classification study to support national actions for recommendations; 4. Organise regional demonstrations of various technical options for ash treatment and spreading; 5. Organise national seminars and demonstrations of

  8. Final Technical Report for "High Energy Physics at The University of Iowa"

    Energy Technology Data Exchange (ETDEWEB)

    Mallik, Usha; Meurice, Yannick; Nachtman, Jane; Onel, Yasar; Reno, Mary

    2013-07-31

    Particle Physics explores the very fundamental building blocks of our universe: the nature of forces, of space and time. By exploring very energetic collisions of sub-nuclear particles with sophisticated detectors at the colliding beam accelerators (as well as others), experimental particle physicists have established the current theory known as the Standard Model (SM), one of the several theoretical postulates to explain our everyday world. It explains all phenomena known up to a very small fraction of a second after the Big Bang to a high precision; the Higgs boson, discovered recently, was the last of the particle predicted by the SM. However, many other phenomena, like existence of dark energy, dark matter, absence of anti-matter, the parameters in the SM, neutrino masses etc. are not explained by the SM. So, in order to find out what lies beyond the SM, i.e., what conditions at the earliest fractions of the first second of the universe gave rise to the SM, we constructed the Large Hadron Collider (LHC) at CERN after the Tevatron collider at Fermi National Accelerator Laboratory. Each of these projects helped us push the boundary further with new insights as we explore a yet higher energy regime. The experiments are extremely complex, and as we push the boundaries of our existing knowledge, it also requires pushing the boundaries of our technical knowhow. So, not only do we pursue humankind’s most basic intellectual pursuit of knowledge, we help develop technology that benefits today’s highly technical society. Our trained Ph.D. students become experts at fast computing, manipulation of large data volumes and databases, developing cloud computing, fast electronics, advanced detector developments, and complex interfaces in several of these areas. Many of the Particle physics Ph.D.s build their careers at various technology and computing facilities, even financial institutions use some of their skills of simulation and statistical prowess. Additionally, last

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  10. Properties of parameter estimation techniques for a beta-binomial failure model. Final technical report

    International Nuclear Information System (INIS)

    Shultis, J.K.; Buranapan, W.; Eckhoff, N.D.

    1981-12-01

    Of considerable importance in the safety analysis of nuclear power plants are methods to estimate the probability of failure-on-demand, p, of a plant component that normally is inactive and that may fail when activated or stressed. Properties of five methods for estimating from failure-on-demand data the parameters of the beta prior distribution in a compound beta-binomial probability model are examined. Simulated failure data generated from a known beta-binomial marginal distribution are used to estimate values of the beta parameters by (1) matching moments of the prior distribution to those of the data, (2) the maximum likelihood method based on the prior distribution, (3) a weighted marginal matching moments method, (4) an unweighted marginal matching moments method, and (5) the maximum likelihood method based on the marginal distribution. For small sample sizes (N = or < 10) with data typical of low failure probability components, it was found that the simple prior matching moments method is often superior (e.g. smallest bias and mean squared error) while for larger sample sizes the marginal maximum likelihood estimators appear to be best

  11. CHARM COST-EFFECTIVE HIGH-EFFICIENCY ADVANCED REFORMING MODULE FINAL TECHNICAL REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Pollica, Darryl; Cross, James C; Sharma, Atul; Shi, Yanlong; Clawson, Lawrence; O' Brien, Chris; Gilhooly, Kara; Kim, Changsik; Quet, Pierre-Francois

    2009-09-02

    Background Creation of a hydrogen infrastructure is an important prerequisite of widespread fuel cell commercialization, especially for the automotive market. Hydrogen is an attractive fuel since it offers an opportunity to replace petroleum-based fuels, but hydrogen occurs naturally only in chemical compounds like water or hydrocarbons that must be chemically converted to produce it. While an ultimate goal is to produce hydrogen through renewable energy sources, steam methane reforming (SMR) of natural gas is currently the most economical solution to initiate the transition to a hydrogen economy. Centralized hydrogen generation using large industrial SMR plants is already in place to serve customers. Yet, because of the weight and size of cylinders needed to contain hydrogen gas or liquid, transportation of hydrogen may only be economical for short distances. Consequently, distributed natural gas reforming, which trades off the economies of scale of large plants for simplified delivery logistics, is an attractive alternative that could address immediate problems with the lack of hydrogen infrastructure.

  12. Gastroenterology-Urology Devices; Manual Gastroenterology-Urology Surgical Instruments and Accessories. Final rule; technical amendment.

    Science.gov (United States)

    2017-03-01

    The Food and Drug Administration (FDA) is amending the identification of manual gastroenterology-urology surgical instruments and accessories to reflect that the device does not include specialized surgical instrumentation for use with urogyencologic surgical mesh specifically intended for use as an aid in the insertion, placement, fixation, or anchoring of surgical mesh during urogynecologic procedures ("specialized surgical instrumentation for use with urogynecologic surgical mesh"). These amendments are being made to reflect changes made in the recently issued final reclassification order for specialized surgical instrumentation for use with urogynecologic surgical mesh.

  13. Final technical report for DE-SC00012633 AToM (Advanced Tokamak Modeling)

    Energy Technology Data Exchange (ETDEWEB)

    Holland, Christopher [Univ. of California, San Diego, CA (United States); Orlov, Dmitri [Univ. of California, San Diego, CA (United States); Izzo, Valerie [Univ. of California, San Diego, CA (United States)

    2018-02-05

    This final report for the AToM project documents contributions from University of California, San Diego researchers over the period of 9/1/2014 – 8/31/2017. The primary focus of these efforts was on performing validation studies of core tokamak transport models using the OMFIT framework, including development of OMFIT workflow scripts. Additional work was performed to develop tools for use of the nonlinear magnetohydrodynamics code NIMROD in OMFIT, and its use in the study of runaway electron dynamics in tokamak disruptions.

  14. Medium-energy nuclear physics research. Final technical progress report, May 1, 1971-November 30, 1981

    International Nuclear Information System (INIS)

    Willard, H.B.

    1981-01-01

    Final results are summarized for this program with the primary emphasis on measurement of ten independent parameters for proton-proton elastic scattering at 800 MeV and four independent such parameters at 650 MeV. Inelastic proton-proton reactions have also been measured at 800 MeV. Proton-deuteron elastic scattering cross sections and polarization analyzing powers have been obtained at 800 MeV. Proton-nucleus total and total reaction cross sections were measured at 700 MeV for a number of nuclei. Major instrumentation was designed and constructed to carry out this program

  15. Hollow ceramic block: containment of water for thermal storage in passive solar design. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Winship, C.T.

    1983-12-27

    The project activity has been the development of designs, material compositions and production procedures to manufacture hollow ceramic blocks which contain water (or other heat absorptive liquids). The blocks are designed to serve, in plurality, a dual purpose: as an unobtrusive and efficient thermal storage element, and as a durable and aesthetically appealing surface for floors and walls of passive solar building interiors. Throughout the grant period, numerous ceramic formulas have been tested for their workabilty, thermal properties, maturing temperatures and color. Blocks have been designed to have structural integrity, and textured surfaces. Methods of slip-casting and extrusion have been developed for manufacturing of the blocks. The thermal storage capacity of the water-loaded block has been demonstrated to be 2.25 times greater than that of brick and 2.03 times greater than that of concrete (taking an average of commonly used materials). Although this represents a technical advance in thermal storage, the decorative effects provided by application of the blocks lend them a more significant advantage by reducing constraints on interior design in passive solar architecture.

  16. Final Scientific/Technical Report for Program Title: Solar Powered Dewvaporation Desalination System

    Energy Technology Data Exchange (ETDEWEB)

    Ranganathan, Shashidhar [Polestar Technologies Inc., Needham Heights, MA (United States)

    2017-03-24

    Desalination technologies have been used increasingly throughout the world to produce the drinking water from the brackish ground and sea water for the past few decades. Among the commercially available desalination technologies, reverse osmosis (RO) and multi-stage flash distillation are the most widely used technologies globally. However, these technologies are difficult to be directly integrated with green energies without converting them to electricity. Dewvaporation, a desalination process, uses saturated steam as a carrier-gas to evaporate water from saline feeds and form pure condensate. It has the major technical benefit of reusing energy, released from vapor condensation, multiple times. The current proposal has been planned to address this issue. In Phase I, we have successfully demonstrated the feasibility of a new plasmonic nanoparticle based approach through fabrication and evaluation of a solar powered water vapor generation module. The water vapor generation module allows generation of high temperature plasmon on a fiber bundle end, where strong water and plasmon interaction occurs generating water vapor. Plasmon enhanced water evaporation has been realized on plasmonic nanoparticle immobilized substrate with an energy conversion efficiency of over 50%.

  17. STTR Phase 1 Final Technical Report for Project Entitled "Developing a Mobile Torrefaction Machine"

    Energy Technology Data Exchange (ETDEWEB)

    James, Joseph J. [President, ATP

    2014-03-11

    The goal of this project, sponsored by Agri-Tech Producers, LLC (ATP), the small business grantee, was to determine if the torrefaction technology, developed by North Carolina State University (NCSU), which ATP has licensed, could be feasibly deployed in a mobile unit. The study adds to the area investigated, by having ATP’s STTR Phase I team give thoughtful consideration to how to use NCSU’s technology in a mobile unit. The findings by ATP’s team were that NCSU’s technology would best perform in units 30’ by 80’ (See Spec Sheet for the Torre-Tech 5.0 Unit in the Appendix) and the technical effectiveness and economic feasibility investigation suggested that such units were not easily, efficiently or safely utilized in a forest or farm setting. (Note rendering of possible mobile system in the Appendix) Therefore, the findings by ATP’s team were that NCSU’s technology could not feasibly be deployed as a mobile unit.

  18. Regional analysis of potential energy production from agricultural wastes: technical and economic study. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Have, H

    1981-01-01

    The possibilities for utilization of agricultural wastes for energy production are analyzed in two Danish counties, Ringkoebing and Vestsjaelland, which have different agricultural production patterns. The quantitative analysis shows that the major waste products, surplus straw, waste wood and animal waste, in total with present technique can cover about 28% of the demand for heat energy (mostly space heating) in both counties. The potential coverage from straw, wood and animal waste is about 3, 3 and 22% in Ringkoebing and 18, 2 and 8% in Vestsjaelland respectively. A technical analysis indicates that direct combustion is the most favorable conversion method for straw and wood while biological conversion at present is best suited for animal waste. An economic analysis based on costs of collection, storage, transport and conversion of wastes and costs of corresponding oil and oil conversion were made. From a community point of view only straw and wood are found to be competitive to the expensive gas fuel oil when burned in automatically stoked furnaces. From a heating station point of view waste utilization is more attractive because of the sales tax on oil products. Here straw and wood are competitive fuels to both gas and heavy fuel oil in all the analyzed systems except from the small manually stoked furnaces. Animal waste seems to be competitive only when replacing gas fuel oil in medium size (500 kW) well utilized aerobic fermenters.

  19. An innovative fuel design concept for improved light water reactor performance and safety. Final technical report

    International Nuclear Information System (INIS)

    Tulenko, J.S.; Connell, R.G.

    1995-07-01

    Light water reactor (LWR) fuel performance is limited by thermal and mechanical constraints associated with the design, fabrication, and operation of fuel in a nuclear reactor. The purpose of this research was to explore a technique for extending fuel performance by thermally bonding LWR fuel with a non-alkaline liquid metal alloy. Current LWR fuel rod designs consist of enriched uranium oxide (UO 2 ) fuel pellets enclosed in a zirconium alloy cylindrical clad. The space between the pellets and the clad is filled by an inert gas. Due to the thermal conductivity of the gas, the gas space thermally insulates the fuel pellets from the reactor coolant outside the fuel rod, elevating the fuel temperatures. Filling the gap between the fuel and clad with a high conductivity liquid metal thermally bonds the fuel to the cladding, and eliminates the large temperature change across the gap, while preserving the expansion and pellet loading capabilities. The resultant lower fuel temperature directly impacts fuel performance limit margins and also core transient performance. The application of liquid bonding techniques to LWR fuel was explored for the purposes of increasing LWR fuel performance and safety. A modified version of the ESCORE fuel performance code (ESBOND) has been developed under the program to analyze the in-reactor performance of the liquid metal bonded fuel. An assessment of the technical feasibility of this concept for LWR fuel is presented, including the results of research into materials compatibility testing and the predicted lifetime performance of Liquid Metal Bonded LWR fuel

  20. National Solar Radiation Data Base, Vol. 2 - Final Technical Report (1961-1990)

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, E. L.; Marion, W.; Myers, D.; Rymes, M.; Wilcox, S.

    1995-01-01

    This technical report explains the procedures used during the 4-year production of the National Solar Radiation Data Base (NSRDB) (1961-1990). It is the second volume in a two-volume report on the NSRDB. The first volume, User's Guide-National Solar Radiation Data Base, provides the information needed to use the data base products. Volume 2 concentrates on results from the R&D required to producea solar radiation data base that would represent a significant update of a previous data base (SOLMET). More than 90% of the data in the NSRDB were estimated using a model--the Meteorological/Statistical (METSTAT) model. Much of Volume 2 concerns the METSTAT model and the sources of its input data. In addition, it contains results of comparisons of the NSRBD with the previous SOLMET data base.Results of the model evaluations and data base comparisons favor the use of NSRDB data over SOLMET data to select optimum sites and estimate performance for solar energy systems. The report noted that to improve data on solar radiation, 'measured' data need to become the mainstav of future data bases.

  1. Final Technical Report: Thermoelectric-Enhanced Cookstove Add-on (TECA) for Clean Biomass Cookstoves

    Energy Technology Data Exchange (ETDEWEB)

    Stokes, David [RTI International, Research Triangle Park, NC (United States)

    2015-09-29

    This program seeks to demonstrate a solution to enhance existing biomass cookstove performance through the use of RTI’s Thermoelectric Enhanced Cookstove Add-on (TECA) device. The self-powered TECA device captures a portion of heat from the stove and converts it to electricity through a thermoelectric (TE) device to power a blower. Colorado State University and Envirofit International are partners to support the air injection design and commercialization to enhance combustion in the stove and reduce emissions. Relevance: By demonstrating a proof of concept of the approach with the Envirofit M-5000 stove and TECA device, we hope to apply this technology to existing stoves that are already in use and reduce emissions for stoves that have already found user acceptance to provide a true health benefit. Challenges: The technical challenges include achieving Tier 4 emissions from a biomass stove and for such a stove to operate reliably in the harsh field environment. Additional challenges include the fact that it is difficult to develop a cost effective solution and insure adoption and proper use in the field. Outcomes: In this program we have demonstrated PM emissions at 82 mg/MJd, a 70% reduction as compared to baseline stove operation. We have also developed a stove optimization approach that reduces the number of costly experiments. We have evaluated component-level reliability and will be testing the stove prototype in the field for performance and reliability.

  2. Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum

    Energy Technology Data Exchange (ETDEWEB)

    Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

    1980-05-23

    This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.

  3. Final Technical Report: "New Tools for Physics with Low-energy Antimatter"

    Energy Technology Data Exchange (ETDEWEB)

    Surko, Clifford M. [U. C. San Diego

    2013-10-02

    The objective of this research is to develop new tools to manipulate antimatter plasmas and to tailor them for specific scientific and technical uses. The work has two specific objectives. One is establishing the limits for positron accumulation and confinement in the form of single-component plasmas in Penning-Malmberg traps. This technique underpins a wealth of antimatter applications. A second objective is to develop an understanding of the limits for formation of cold, bright positron beams. The research done in this grant focused on particular facets of these goals. One focus was extracting tailored beams from a high-field Penning-Malmberg trap from the magnetic field to form new kinds of high-quality electrostatic beams. A second goal was to develop the technology for colder trap-based beams using a cryogenically cooled buffer gas. A third objective was to conduct the basic plasma research to develop a new high-capacity multicell trap (MCT) for research with antimatter. Progress is reported here in all three areas. While the goal of this research is to develop new tools for manipulating positrons (i.e., the antiparticles of electrons), much of the work was done with test electron plasmas for increased data rate. Some of the techniques developed in the course of this work are also relevant to the manipulation and use of antiprotons.

  4. Final environmental assessment: TRU waste drum staging building, Technical Area 55, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    1996-01-01

    Much of the US Department of Energy's (DOE's) research on plutonium metallurgy and plutonium processing is performed at Los Alamos National Laboratory (LANL), in Los Alamos, New Mexico. LANL's main facility for plutonium research is the Plutonium Facility, also referred to as Technical Area 55 (TA-55). The main laboratory building for plutonium work within the Plutonium Facility (TA-55) is the Plutonium Facility Building 4, or PF-4. This Environmental Assessment (EA) analyzes the potential environmental effects that would be expected to occur if DOE were to stage sealed containers of transuranic (TRU) and TRU mixed waste in a support building at the Plutonium Facility (TA-55) that is adjacent to PF-4. At present, the waste containers are staged in the basement of PF-4. The proposed project is to convert an existing support structure (Building 185), a prefabricated metal building on a concrete foundation, and operate it as a temporary staging facility for sealed containers of solid TRU and TRU mixed waste. The TRU and TRU mixed wastes would be contained in sealed 55-gallon drums and standard waste boxes as they await approval to be transported to TA-54. The containers would then be transported to a longer term TRU waste storage area at TA-54. The TRU wastes are generated from plutonium operations carried out in PF-4. The drum staging building would also be used to store and prepare for use new, empty TRU waste containers

  5. Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum

    International Nuclear Information System (INIS)

    Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

    1980-01-01

    This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive

  6. Technical assistance for an evaluation of international schemes to promote biomass sustainability. Final report

    International Nuclear Information System (INIS)

    Londo, M.

    2009-12-01

    In this technical assistance report to the title subject report is given of Task 1: Review of GREEN-X assumptions on biomass availability and costs; Task 2: Impacts of sustainability criteria on biomass availability and costs; Task 3: Applicability of existing certification schemes; Task 4: Identification of feasible verification options; and Task 5: summary, integration. The key objective of Task 1 is to validate the present and future availability (up to 2020) and costs of biomass energy in the EU 27. The GREEN-X model forecasts the deployment of renewable energy systems under various scenarios in terms of supporting policy instruments, the availability of resources and generation technologies and energy, technology and resource price developments. Objective of task 2 is to assess to what extent the sustainability criteria as specified in the Renewable Energy Directive (RED (EP/EC 2009)) affect availability and costs of biofuels. The objective of task 3 is to assess to what extent national and international certification schemes (existing and under development) would be applicable for safeguarding the sustainability criteria as mentioned in the Renewable Energy Sources (RES) directive. The objective of Task 4 is to identify and analyse feasible options to verify compliance with biomass sustainability criteria, in the case of forest biomass.

  7. Integrated Energy System with Beneficial Carbon Dioxide (CO2) Use - Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Sun, Xiaolei; Rink, Nancy T

    2011-04-29

    This report presents an integrated energy system that combines the production of substitute natural gas through coal hydrogasification with an algae process for beneficial carbon dioxide (CO2) use and biofuel production (funded under Department of Energy (DOE) contract DE-FE0001099). The project planned to develop, test, operate and evaluate a 2 ton-per-day coal hydrogasification plant and 25-acre algae farm at the Arizona Public Service (APS) 1000 Megawatt (MW) Cholla coal-fired power plant in Joseph City, Arizona. Conceptual design of the integrated system was undertaken with APS partners Air Liquide (AL) and Parsons. The process engineering was separated into five major areas: flue gas preparation and CO2 delivery, algae farming, water management, hydrogasification, and biofuel production. The process flow diagrams, energy and material balances, and preliminary major equipment needs for each major area were prepared to reflect integrated process considerations and site infrastructure design basis. The total project also included research and development on a bench-scale hydrogasifier, one-dimensional (1-D) kinetic-model simulation, extensive algae stressing, oil extraction, lipid analysis and a half-acre algae farm demonstration at APS?s Redhawk testing facility. During the project, a two-acre algae testing facility with a half-acre algae cultivation area was built at the APS Redhawk 1000 MW natural gas combined cycle power plant located 55 miles west of Phoenix. The test site integrated flue gas delivery, CO2 capture and distribution, algae cultivation, algae nursery, algae harvesting, dewatering and onsite storage as well as water treatment. The site environmental, engineering, and biological parameters for the cultivators were monitored remotely. Direct biodiesel production from biomass through an acid-catalyzed transesterification reaction and a supercritical methanol transesterification reaction were evaluated. The highest oil-to-biodiesel conversion of 79

  8. Rocky Flats Plant site, Golden, Jefferson County, Colorado. Final environmental impact statement (final statement to ERDA 1545-D)

    International Nuclear Information System (INIS)

    1980-04-01

    This final Environmental Impact Statement (FEIS) incorporates a number of changes as a result of the comments and suggestions received on the Draft Environmental Impact Statement. The major additions and revisions of this first of the three-volume statement are discussed. Chapter titles are: summary; background; environmental impacts; unavoidable adverse environmental effects; alternatives; relationship between short-term uses and long-term productivity; relationship to land-use plans; irreversible and irretrievable commitments of resources; and, environmental trade-off analysis. Chapter 2 includes updated information on seismic stability of the area and seismic design criteria are presented. A mechanism for dissemination of the data from seismic studies in progress is specified. The Plant's personnel protection program with respect to nonradioactive materials, Plant security systems, and the emergency plans of the Plant and the State of Colorado are discussed in greater detail. Material on the environmental monitoring program was updated to reflect current monitoring and measuring conditions. Discussions of various soil sampling methods, plutonium background levels in soil, and plutonium soil standards, are presented. The dose calculations in Chapter 3 were extended to include comparisons of organ doses to natural background organ doses as well as the dose to the whole body. Doses to women and children are considered by exposure pathway as well as those for Standard Man. All credible accident scenarios were reviewed and details updated. A comprehensive discussion of genetic and health effects is presented in Appendices G-2 through G-4. Chapter 5 was revised to reflect the effort and cost involved in decontaminating soil, both on-site and offsite, relative to various decontamination criteria which might be employed

  9. Developing Association Mapping in Polyploid Perennial Biofuel Grasses: Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Buckler, Edward S; Casler, Michael D; Cherney, Jerome H

    2012-01-20

    This project had six objectives, four of which have been completed: 1) Association panels of diverse populations and linkage populations for switchgrass and reed canarygrass (~1,000 clones each) were assembled and planted in two sites (Ithaca, NY and Arlington, WI); 2) Key biofeedstock characteristics were evaluated in these panels for three field seasons; 3) High density SNP markers were developed in switchgrass; and 4) Switchgrass association panels and linkage populations were genotyped. The remaining two original objectives will be met in the next year, as the analyses are completed and papers published: 5) Switchgrass population structure and germplasm diversity will be evaluated; and 6) Association mapping will be established and marker based breeding values estimated in switchgrass. We also completed a study of the chromosome-number variation found in switchgrass.

  10. Final Technical Report - Autothermal Styrene Manufacturing Process with Net Export of Energy

    Energy Technology Data Exchange (ETDEWEB)

    Trubac, Robert , E.; Lin, Feng; Ghosh, Ruma: Greene, Marvin

    2011-11-29

    The overall objectives of the project were to: (a) develop an economically competitive processing technology for styrene monomer (SM) that would reduce process energy requirements by a minimum 25% relative to those of conventional technology while achieving a minimum 10% ROI; and (b) advance the technology towards commercial readiness. This technology is referred to as OMT (Oxymethylation of Toluene). The unique energy savings feature of the OMT technology would be replacement of the conventional benzene and ethylene feedstocks with toluene, methane in natural gas and air or oxygen, the latter of which have much lower specific energy of production values. As an oxidative technology, OMT is a net energy exporter rather than a net energy consumer like the conventional ethylbenzene/styrene (EB/SM) process. OMT plants would ultimately reduce the cost of styrene monomer which in turn will decrease the costs of polystyrene making it perhaps more cost competitive with competing polymers such as polypropylene.

  11. 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

  12. Safety-technical characteristics of biomass, coal and straw. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Wilen, C.; Rautalin, A.

    1995-12-31

    Safety-technical factors related to spontaneous ignition and dust explosions of biomasses were investigated. Parametres of dust explosions and effect of inertisation on the maximum pressure (pmax) and the maximum rate of pressure rise (Kstmax) were studied at elevated initial pressure (1-9 bar). The level of inertisation required to prevent dust explosions totally was determined at different initial pressures. The sensitivity of fuels to spontaneous ignition and the effect of pressure on the sensitivity to and temperature of spontaneous ignition were studied on a pressurised dynamic self-ignition equipment. The effect of inertisation on the self-ignition temperature and alternatives of preventing spontaneous ignition by effective inertisation in the pressure ranges of 1 and 25 bar were investigated. As an example of application, results obtained with the laboratory test equipment were extrapolated to bin sizes used in practice. As a factor contributing to spontaneous ignition, the flowability of different fuels in bins and lock-hoppers (stagnant fuel layers are especially sensitive to spontaneous ignition) in continuous flow and in flow stopped for a storage time of 1 hour was also studied. Walker`s rotating ring shear equipment and Jenike`s linear shear equipment based on shearing the fuel were used in the flowability measurements. The effect of fuel temperature (22 deg C, 40 deg C) on flowability was determined for forest residue chips. Dynamic friction coefficients between fuels and handling equipment were determined for stainless steel and rusty metal surface. As an example of application, results obtained with laboratory test equipment were extrapolated to a bin size of 21 m{sup 3} by calculating the size of the minimum discharge opening required by mass flow of different coals and forest residue chips and the minimum angle of repose of the conical part for a bin of stainless steel

  13. Technical program plan for the transitioning, decommissioning, and final disposition focus area

    International Nuclear Information System (INIS)

    1994-01-01

    The end of the Cold War and the decision to reduce the size of the nuclear weapons production complex have created a need for DOE to deactivate, decontaminate, and decommission (D ampersand D) a large number of aging, surplus facilities. The nature and magnitude of the facility D ampersand D problems require EM to facilitate the development and application of technologies that will address these problems quickly and cost-effectively. The needed technologies can best be provided by integrating the strengths of DOE's national laboratories with those of industry, universities, and other government agencies. To help focus and direct these activities toward achieving DOE's goals, the EM Office of Technology Development (OTD) devised the strategic concept of an Integrated Demonstration (ID), which involves selecting, demonstrating, testing, and evaluating an integrated set of technologies tailored to provide a complete solution to specific EM problems, such as those posed by D ampersand D. The ID approach allows optimal use of DOE's resources by avoiding duplication of effort and ensuring rapid demonstration of applicable technologies. Many technologies, including both the commercially mature and the innovative, are combined and evaluated for a cradle-to-grave solution to specific EM problems in areas such as D ampersand D. The process will involve transforming an existing problem condition to a desired end state, recycling waste materials generated, wherever feasible, and minimizing requirements for waste disposal. The D ampersand D ID Strategic Plan has been prepared by a Technical Support Group (TSG) assembled from various sites within the DOE Complex and intended to identify cross-cutting problem areas amenable to applications of the D ampersand D ID concept and to develop specific ID proposals for these problem areas

  14. Microalgae as a source of liquid fuels. Final technical report. [200 references

    Energy Technology Data Exchange (ETDEWEB)

    Benemann, J.R.; Goebel, R.P.; Weissman, J.C.; Augenstein, D.C.

    1982-05-15

    The economics of liquid-fuels production from microalgae was evaluated. A detailed review of published economic analyses of microalgae biomass production revealed wide variations in the published costs, which ranged from several dollars per pound for existing commercial health-food production in the Far East, to less than .05/lb costs projected for microalgae biomass for fuel conversion. As little design information or specific cost data has been published, a credible cost estimate required the conceptual engineering design and cost estimating of microalgae to liquid-fuels processes. Two systems were analyzed, shallow (2 to 3'') covered ponds and deeper (1 ft) open ponds. Only the latter was selected for an in-depth analysis due to the many technical shortcomings of the former approach. Based on the cost analysis of a very simple and low cost process, the most optimistic costs extrapolated were about $60/barrel. These were based on many optimistic assumptions. Additional, more detailed, engieering and cost analyses would be useful. However, the major emphasis in future work in this area should be on demonstrating the basic premises on which this design was based: high productivity and oil content of microalgae strains that can dominate in open ponds and which can be harvested by a simple bioflocculation process. Several specific basic research needs were identified: (1) Fundamentals of species selection and control in open pond systems. Effects of environmental variables on species dominance is of particular interest. (2) Mechanisms of algae bioflocculation. (3) Photosynthetic pathways and efficiency under conditions of high lipid production. (4) Effects of non-steady state operating conditions, particularly pH (CO/sub 2/ availability), on productivity. 18 figures, 47 tables.

  15. Improving measurement quality assurance for photon irradiations at Department of Energy facilities. Final technical report

    International Nuclear Information System (INIS)

    1996-01-01

    For radiation-instrument calibration to be generally acceptable throughout the US, direct or indirect traceability to a primary standard is required. In most instances, one of the primary standards established at NIST is employed for this purpose. The Department of Energy Laboratory Accreditation Program (DOELAP) is an example of a program employing dosimetry based on the NIST primary photon-, beta particle- and neutron-dosimetry standards. The NIST primary dosimetry standards for bremsstrahlung were first established in the 1950s. They have been updated since then on several occasions. In the 1970s, Technical Committee 85 of the International Standards Organization (ISO) started its work on establishing sets of internationally acceptable, well-characterized photon beams for the calibration of radiation-protection instruments. It is the intent of this paper to make a detailed comparison between the current NIST and the most up-to-date ISO techniques. At present, 41 bremsstrahlung techniques are specified in ISO 4037 while NIST supports a total of 32 techniques. Given the existing equivalences, it makes sense to try to extend the NIST techniques to cover more of the ISO Narrow Spectrum and High Air-Kerma Rate Series. These extensions will also allow the possibility for use of ISO beam techniques in future revisions of the DOELAP standard, which has been suggested by DOE. To this end, NIST was funded by DOE to procure material and make adaptations to the existing NIST x-ray calibration ranges to allow NIST to have the capability of producing all the ISO bremsstrahlung techniques. The following sections describe the steps that were taken to achieve this

  16. Safety-technical characteristics of biomass, coal and straw. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Wilen, C; Rautalin, A

    1996-12-31

    Safety-technical factors related to spontaneous ignition and dust explosions of biomasses were investigated. Parametres of dust explosions and effect of inertisation on the maximum pressure (pmax) and the maximum rate of pressure rise (Kstmax) were studied at elevated initial pressure (1-9 bar). The level of inertisation required to prevent dust explosions totally was determined at different initial pressures. The sensitivity of fuels to spontaneous ignition and the effect of pressure on the sensitivity to and temperature of spontaneous ignition were studied on a pressurised dynamic self-ignition equipment. The effect of inertisation on the self-ignition temperature and alternatives of preventing spontaneous ignition by effective inertisation in the pressure ranges of 1 and 25 bar were investigated. As an example of application, results obtained with the laboratory test equipment were extrapolated to bin sizes used in practice. As a factor contributing to spontaneous ignition, the flowability of different fuels in bins and lock-hoppers (stagnant fuel layers are especially sensitive to spontaneous ignition) in continuous flow and in flow stopped for a storage time of 1 hour was also studied. Walker`s rotating ring shear equipment and Jenike`s linear shear equipment based on shearing the fuel were used in the flowability measurements. The effect of fuel temperature (22 deg C, 40 deg C) on flowability was determined for forest residue chips. Dynamic friction coefficients between fuels and handling equipment were determined for stainless steel and rusty metal surface. As an example of application, results obtained with laboratory test equipment were extrapolated to a bin size of 21 m{sup 3} by calculating the size of the minimum discharge opening required by mass flow of different coals and forest residue chips and the minimum angle of repose of the conical part for a bin of stainless steel

  17. Final Technical Report - Advanced Optical Sensors to Minimize Energy Consumption in Polymer Extrusion Processes

    Energy Technology Data Exchange (ETDEWEB)

    Susan J. Foulk

    2012-07-24

    Project Objective: The objectives of this study are to develop an accurate and stable on-line sensor system to monitor color and composition on-line in polymer melts, to develop a scheme for using the output to control extruders to eliminate the energy, material and operational costs of off-specification product, and to combine or eliminate some extrusion processes. Background: Polymer extrusion processes are difficult to control because the quality achieved in the final product is complexly affected by the properties of the extruder screw, speed of extrusion, temperature, polymer composition, strength and dispersion properties of additives, and feeder system properties. Extruder systems are engineered to be highly reproducible so that when the correct settings to produce a particular product are found, that product can be reliably produced time after time. However market conditions often require changes in the final product, different products or grades may be processed in the same equipment, and feed materials vary from lot to lot. All of these changes require empirical adjustment of extruder settings to produce a product meeting specifications. Optical sensor systems that can continuously monitor the composition and color of the extruded polymer could detect process upsets, drift, blending oscillations, and changes in dispersion of additives. Development of an effective control algorithm using the output of the monitor would enable rapid corrections for changes in materials and operating conditions, thereby eliminating most of the scrap and recycle of current processing. This information could be used to identify extruder systems issues, diagnose problem sources, and suggest corrective actions in real-time to help keep extruder system settings within the optimum control region. Using these advanced optical sensor systems would give extruder operators real-time feedback from their process. They could reduce the amount of off-spec product produced and

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

    International Nuclear Information System (INIS)

    Mayberry, J.L.; Huebner, T.L.; Ross, W.; Nakaoka, R.; Schumacher, R.; Cunnane, J.; Singh, D.; Darnell, R.; Greenhalgh, W.

    1993-08-01

    This report presents information on low-level mixed waste forms.The descriptions of the low-level mixed waste (LLMW) streams that are considered by the Mixed Waste Integrated Program (MWIP) are given in Appendix A. This information was taken from descriptions generated by the Mixed Waste Treatment Program (MWTP). Appendix B provides a list of characteristic properties initially considered by the Final Waste Form (FWF) Working Group (WG). A description of facilities available to test the various FWFs discussed in Volume I of DOE/MWIP-3 are given in Appendix C. Appendix D provides a summary of numerous articles that were reviewed on testing of FWFS. Information that was collected by the tests on the characteristic properties considered in this report are documented in Appendix D. The articles reviewed are not a comprehensive list, but are provided to give an indication of the data that are available

  19. Final Scientific/Technical Report Carbon Capture and Storage Training Northwest - CCSTNW

    Energy Technology Data Exchange (ETDEWEB)

    Workman, James

    2013-09-30

    This report details the activities of the Carbon Capture and Storage Training Northwest (CCSTNW) program 2009 to 2013. The CCSTNW created, implemented, and provided Carbon Capture and Storage (CCS) training over the period of the program. With the assistance of an expert advisory board, CCSTNW created curriculum and conducted three short courses, more than three lectures, two symposiums, and a final conference. The program was conducted in five phases; 1) organization, gap analysis, and form advisory board; 2) develop list serves, website, and tech alerts; 3) training needs survey; 4) conduct lectures, courses, symposiums, and a conference; 5) evaluation surveys and course evaluations. This program was conducted jointly by Environmental Outreach and Stewardship Alliance (dba. Northwest Environmental Training Center – NWETC) and Pacific Northwest National Laboratories (PNNL).

  20. DOE SBIR Phase II Final Technical Report - Assessing Climate Change Effects on Wind Energy

    Energy Technology Data Exchange (ETDEWEB)

    Whiteman, Cameron [Vertum Partners LP, Los Angeles, CA (United States); Capps, Scott [Vertum Partners LP, Los Angeles, CA (United States)

    2014-11-05

    Specialized Vertum Partners software tools were prototyped, tested and commercialized to allow wind energy stakeholders to assess the uncertainties of climate change on wind power production and distribution. This project resulted in three commercially proven products and a marketing tool. The first was a Weather Research and Forecasting Model (WRF) based resource evaluation system. The second was a web-based service providing global 10m wind data from multiple sources to wind industry subscription customers. The third product addressed the needs of our utility clients looking at climate change effects on electricity distribution. For this we collaborated on the Santa Ana Wildfire Threat Index (SAWTi), which was released publicly last quarter. Finally to promote these products and educate potential users we released “Gust or Bust”, a graphic-novel styled marketing publication.