The back end of the nuclear fuel cycle: technical and economic analysis-Part 1

International Nuclear Information System (INIS)

Roglans-Ribas, J.; Spinrad, B.I.

1990-01-01

The back end of the nuclear fuel cycle has been analyzed under current conditions in the United States, taking into consideration the framework defined by the Nuclear Waste Policy Act of 1982 and its amendments. The different steps of the back end of the fuel cycle are studied and different alternatives are compared under technical and economic criteria. Several technical issues have been analyzed for their impact on the economics of the fuel cycle. The bases for the analysis are explained, and the results for a once-through cycle are presented. The results show that a repository in tuff represents the minimum cost situation. The economic model appears very sensitive to several parameters, in particular the period of retrievability and the storage costs

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

Advanced steam cycles for light water reactors. Final report

International Nuclear Information System (INIS)

Mitchell, R.C.

1975-07-01

An appraisal of the potential of adding superheat to improve the overall LWR plant cycle performance is presented. The study assesses the economic and technical problems associated with the addition of approximately 500 0 F of superheat to raise the steam temperature to 1000 0 F. The practicality of adding either nuclear or fossil superheat to LWR's is reviewed. The General Electric Company Boiling Water Reactor (BWR) model 238-732 (BWR/6) is chosen as the LWR starting point for this evaluation. The steam conditions of BWR/6 are representative of LWR's. The results of the fossil superheat portion of the evaluation are considered directly applicable to all LWR's. In spite of the potential of a nuclear superheater to provide a substantial boost to the LWR cycle efficiency, nuclear superheat offers little promise of development at this time. There are difficult technical problems to resolve in the areas of superheat fuel design and emergency core cooling. The absence of a developed high integrity, high temperature fuel for operation in the steam/water environment is fundamental to this conclusion. Fossil superheat offers the potential opportunity to utilize fossil fuel supplies more efficiently than in any other mode of central station power generation presently available. Fossil superheat topping cycles evaluated included atmospheric fluidized beds (AFB), pressurized fluidized beds, pressurized furnaces, conventional furnaces, and combined gas/steam turbine cycles. The use of an AFB is proposed as the preferred superheat furnace. Fossil superheat provides a cycle efficiency improvement for the LWR of two percentage points, reduces heat rejection by 15 percent per kWe generated, increases plant electrical output by 54 percent, and burns coal with an incremental net efficiency of approximately 40 percent. This compares with a net efficiency of 36--37 percent which might be achieved with an all-fluidized bed fossil superheat plant design

A method for strategic technical life cycle management of real estates

OpenAIRE

Koskelo, Taina

2005-01-01

This research study focuses on the strategic technical life cycle management (TLCM) of real estate. In the early phases of the study it became clear that very often the performance of TLCM was not perceived as satisfactory: there were problems in the purchasing and provision of technical services, TLCM was not performed according to real estate specific needs and objective-setting for building characteristics did not serve cost-effective ownership. The study focuses on four research quest...

DOE final technical report 3/1997 to 2/2005

International Nuclear Information System (INIS)

Gross, Franz L.

2005-01-01

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

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

Science.gov (United States)

2012-08-08

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

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

International Nuclear Information System (INIS)

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

1993-08-01

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

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

Science.gov (United States)

2011-04-04

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

'BACO' code: Cogeneration cycles heat balance

International Nuclear Information System (INIS)

Huelamo Martinez, E.; Conesa Lopez, P.; Garcia Kilroy, P.

1993-01-01

This paper presents a code, developed by Empresarios Agrupados, sponsored by OCIDE, CSE and ENHER, that, with Electrical Utilities as final users, allows to make combined and cogeneration cycles technical-economical studies. (author)

AIMES Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2017-01-31

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

NCSU reactor sharing program. Final technical report

International Nuclear Information System (INIS)

Perez, P.B.

1997-01-01

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

Super Phenix 1 fuel cycle, technical and economical outlooks

International Nuclear Information System (INIS)

Mougniot, J.C.; Baumier, J.; Duchatelle, L.

1982-01-01

An analysis of the costs of the various parts of the Super Phenix 1 fuel cycle is presented. The basis for calculating the mean levelized present unit cost used in French economic analyses is described. A description of the fuel cycle which follows includes the physical characteristics and management of the fuel and the costs of fuel services and raw materials. The results of calculations about Super Phenix mean levelized present fuel cycle unit cost are indicated and a comparison with two, four and six 1500 MWe units and PWR units is made. Finally conclusions are drawn about the economic possibility of FBR deployment. (U.K.)

CSNI Technical Opinion Papers No. 15 - Ageing management of nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Nocture, Pierre; Daubard, Jean-Paul; Lhomme, Veronique; Martineau, Dominique; Blundell, Neil; Conte, Dorothee; Dobson, Martin; Gmal, Bernhard; Hiltz, Thomas; Ueda, Yoshinori

2012-01-01

Managing the ageing of fuel cycle facilities (FCFs) means, as for other nuclear installations, ensuring the availability of required safety functions throughout their service life while taking into account the changes that occur with time and use. This technical opinion paper identifies a set of good practices by benchmarking strategies and good practices on coping with physical ageing and obsolescence from the facility design stage until decommissioning. It should be of particular interest to nuclear safety regulators, fuel cycle facilities operators and fuel cycle researchers [fr

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objectives of the meeting were: • To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; • To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; • To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; • To discuss the results of studies and ongoing R&D activities that address cost reduction and the future economic competitiveness of fast reactors; • To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

The nuclear fuel cycle including essential aspects of safety

International Nuclear Information System (INIS)

Warnemuende, R.; May, H.

1978-11-01

When judging nuclear energy not only the reactor but also the whole fuel cycle is of importance. The fuel cycle consists of the supply, i.e. the process from uranium ore to the insertion of fuel elements into the reactor and the waste management, the removal of fuel elements from the reactor and the final storage of radioactive waste. The different stages of the nuclear fuel cycle are well known with regard to their technical difficulties, their problems of industrial safety and pollution. Although it is possible to compare them qualitatively, they still differ partly to a considerable extent, from a quantitative point of view. However, the fact that technical solutions are available for all kinds of tasks can be stated. It is significant for the Federal Republic of Germany that all essential preparatory work for closing the nuclear fuel cycle has been carried out and that safety problems will no longer be in the way of the large-scale realization of uranium enrichment, reprocessing of nuclear fuels and final storage of radioactive waste. Further research and development activities will serve its technical and economic optimization. (orig.) [de

Computer simulation of transitional process to the final stable Brayton cycle in magnetic refrigeration

International Nuclear Information System (INIS)

Numasawa, T.; Hashimoto, T.

1981-01-01

The final working cycle in the magnetic refrigeration largely depends on the heat transfer coefficient β in the system, the parameter γ of the heat inflow from the outer system to this cycle and the period tau of the cycle. Therefore, so as to make clear this dependence, the time variation of the Brayton cycle with β, γ and tau has been investigated. In the present paper the transitional process of this cycle and the dependence of the final cooling temperature of the heat load on β, γ and tau have all been shown. (orig.)

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

International Nuclear Information System (INIS)

Williams, H.H.

1995-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Williams, H.H.

1995-10-01

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

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

International Nuclear Information System (INIS)

2013-01-01

The objectives of the meeting were: - To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; - To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; - To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; - To discuss the results of studies and on-going R&D activities that address cost reduction and the future economic competitiveness of fast reactors; and - To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

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

Science.gov (United States)

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

2017-11-01

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

Technical 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

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

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.

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

International Nuclear Information System (INIS)

2013-01-01

In recent years, engineering oriented work, rather than basic research and development (R&D), has led to significant progress in improving the economics of innovative fast reactors and associated fuel cycle facilities, while maintaining and even enhancing the safety features of these systems. Optimization of plant size and layout, more compact designs, reduction of the amount of plant materials and the building volumes, higher operating temperatures to attain higher generating efficiencies, improvement of load factor, extended core lifetimes, high fuel burnup, etc. are good examples of achievements to date that have improved the economics of fast neutron systems. The IAEA, through its Technical Working Group on Fast Reactors (TWG-FR) and Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWG-NFCO), devotes many of its initiatives to encouraging technical cooperation and promoting common research and technology development projects among Member States with fast reactor and advanced fuel cycle development programmes, with the general aim of catalysing and accelerating technology advances in these fields. In particular the theme of fast reactor deployment, scenarios and economics has been largely debated during the recent IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, held in Paris in March 2013. Several papers presented at this conference discussed the economics of fast reactors from different national and regional perspectives, including business cases, investment scenarios, funding mechanisms and design options that offer significant capital and energy production cost reductions. This Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics addresses Member States’ expressed need for information exchange in the field, with the aim of identifying the main open issues and launching possible initiatives to help and

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

Science.gov (United States)

2013-02-26

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

Technical Issues in the development of high burnup and long cycle fuel pellets

Energy Technology Data Exchange (ETDEWEB)

Kim, Dong Joo; Yang, Jae Ho; Oh, Jang Soo; Kim, Keon Sik; Rhee, Young Woo; Kim, Jong Hun; Nam, Ik Hui [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-10-15

Over the last half century, a nuclear fuel cycle, a fuel discharged burnup and a uranium enrichment of the LWR (Light Water Reactor) fuel have continuously increased. It was the efforts to reduce the LWR fuel cycle cost, and to make reactor operation more efficiently. Improved fuel and reactor performance contribute further to the reduction and management efficiency of spent fuels. The primary incentive for operating nuclear reactor fuel to higher burnup and longer cycle is the economic benefits. The fuel cycle costs could be reduced by extending fuel discharged burnup and fuel cycle length. The higher discharged burnup can increase the energy production per unit fuel mass or fuel assembly. The longer fuel cycle can increase reactor operation flexibility and reduce the fuel changing operation and the spent fuel management burden. The margin to storage capacity limits would be also increased because high burnup and long cycle fuel reduces the mass of spent fuels. However, increment of fuel burnup and cycle length might result in the acceleration of material aging consisting fuel assembly. Then, the safety and integrity of nuclear fuel will be degraded. Therefore, to simultaneously enhance the safety and economics of the LWR fuel through the fuel burnup and cycle extension, it is indispensable to develop the innovative nuclear fuel material concepts and technologies which can overcome degradation of fuel safety. New fuel research project to extend fuel discharged burnup and cycle length has been launched in KAERI. Main subject is to develop innovative LWR fuel pellets which can provide required fuel performance and safety at extended fuel burnup and cycle length. In order to achieve the mission, we need to know that what the impediments are and how to break through current limit of fuel pellet properties. In this study, the technical issues related to fuel pellets at high burnup were surveyed and summarized. We have collected the technical issues in the literatures

Technical Issues in the development of high burnup and long cycle fuel pellets

International Nuclear Information System (INIS)

Kim, Dong Joo; Yang, Jae Ho; Oh, Jang Soo; Kim, Keon Sik; Rhee, Young Woo; Kim, Jong Hun; Nam, Ik Hui

2012-01-01

Over the last half century, a nuclear fuel cycle, a fuel discharged burnup and a uranium enrichment of the LWR (Light Water Reactor) fuel have continuously increased. It was the efforts to reduce the LWR fuel cycle cost, and to make reactor operation more efficiently. Improved fuel and reactor performance contribute further to the reduction and management efficiency of spent fuels. The primary incentive for operating nuclear reactor fuel to higher burnup and longer cycle is the economic benefits. The fuel cycle costs could be reduced by extending fuel discharged burnup and fuel cycle length. The higher discharged burnup can increase the energy production per unit fuel mass or fuel assembly. The longer fuel cycle can increase reactor operation flexibility and reduce the fuel changing operation and the spent fuel management burden. The margin to storage capacity limits would be also increased because high burnup and long cycle fuel reduces the mass of spent fuels. However, increment of fuel burnup and cycle length might result in the acceleration of material aging consisting fuel assembly. Then, the safety and integrity of nuclear fuel will be degraded. Therefore, to simultaneously enhance the safety and economics of the LWR fuel through the fuel burnup and cycle extension, it is indispensable to develop the innovative nuclear fuel material concepts and technologies which can overcome degradation of fuel safety. New fuel research project to extend fuel discharged burnup and cycle length has been launched in KAERI. Main subject is to develop innovative LWR fuel pellets which can provide required fuel performance and safety at extended fuel burnup and cycle length. In order to achieve the mission, we need to know that what the impediments are and how to break through current limit of fuel pellet properties. In this study, the technical issues related to fuel pellets at high burnup were surveyed and summarized. We have collected the technical issues in the literatures

Technical planning activity: Final report

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

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

Technical planning activity: Final report

International Nuclear Information System (INIS)

1987-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1993-08-01

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

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

Science.gov (United States)

2012-05-23

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

An assessment of twelve- versus eighteen-month cycles for PWRs

International Nuclear Information System (INIS)

Momsen, B.F.; Dale, R.

1983-01-01

This paper discusses the technical and economic factors involved in 18-month cycles for Zion pressurized water reactors (PWRs). The technical factors are divided into the factors that define input to the economic analysis and factors that are combined with the economic results in the final decisionmaking process. The economic analysis was performed by using a Present Value of the Revenue Requirements (PVRR) method and a complementary cash flow examination. The PVRR analysis examined total costs associated with both the 12- and 18-month cycles. The only significant technical problem that was identified was the relatively low new fuel enrichment limit of 3.2 w/o U 235 . The economic analysis demonstrated that 18-month cycles yielded significant PVRR savings over the 15-year study period. The economic benefits of 18-month cycles decreased as the fuel cost increased, the operating capacity factor decreased, the refueling outage length decreased, the differential 18-month cycle outage length increased, the replacement power cost decreased, and the escalation rate decreased

Several remarks on the fuel cycle economy

International Nuclear Information System (INIS)

Roman Kubin; Rudolf Vespalec

2007-01-01

Present paper deals with some aspects influencing significantly cost of nuclear fuel and possibilities of its usage in optimal fuel cycle technology. Our discussion is focused on the phase of fuel procurement that means financial parts of the contract as well as its technical Appendices. Typically the fuel fabrication price is taken as the main economy indicator; nevertheless also many other financial and technical features of the contract must be taken into account in order to reach the best price of electricity sold into public energy grid. Our experience from several international tenders shows that the consistent complex of commercial and technical parameters of the contract is necessary to achieve optimal economic results and prepare proper conditions for advanced fuel cycle technology. Among those essential characteristics are payment conditions and schedule and extent of vendor's services and assistance to the operator. Very important role play also technical parameters, as safety and operational limits, influencing loading pattern quality and operating flexibility. Obviously also a level of operator's fuel cycle technology is a crucial point that is necessary for usage of technical quality of the fuel at the power plant. The final electricity price, produced by the plant, and uranium consumption are the only objective criteria to evaluate economic level of the fuel contract and the fuel cycle at all (Authors)

"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.

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.

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

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

Life cycle assessment of waste management systems: Assessing technical externalities

DEFF Research Database (Denmark)

Brogaard, Line Kai-Sørensen

The life cycle assessment (LCA) of a waste management system relies on many internal characteristics such as pollution control systems and recovery efficiencies. It also relies on technical externalities supporting the waste management system in terms of capital goods and energy and material...... for the primary and secondary production of materials, 366 datasets were gathered. The materials in focus were: paper, newsprint, cardboard, corrugated board, glass, aluminium, steel and plastics (HDPE, LDPE, LLDPE, PET, PS, PVC). Only one quarter of these data concerned secondary production, thus underlining...

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

International Nuclear Information System (INIS)

1987-01-01

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

Final Technical Report, Wind Generator Project (Ann Arbor)

Energy Technology Data Exchange (ETDEWEB)

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

2017-03-20

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

Iowa Hill Pumped Storage Project Investigations - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-01

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

Admiralty Inlet Pilot Tidal Project Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2015-09-14

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

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...

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.

General characteristics and technical subjects on helium closed cycle gas turbine

International Nuclear Information System (INIS)

Shimomura, Hiroaki

1996-06-01

Making the subjects clarified on nuclear-heated gas turbine that will apply the inherent features of HTGR, the present paper discusses the difference of the helium closed cycle gas turbine, which is a candidate of nuclear gas turbine, with the open cycle gas turbine and indicates inherent problems of closed cycle gas turbine, its effects onto thermal efficiency and turbine output and difficulties due to the pressure ratio and specific speed from use of helium. The paper also discusses effects of the external pressure losses onto the efficiencies of compressor and turbine that are major components of the gas turbine. According to the discussions above, the paper concludes indicating the key idea on heat exchangers for the closed cycle gas turbine and design basis to solve the problems and finally offers new gas turbine conception using nitrogen or air that is changeable into open cycle gas turbine. (author)

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

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.

Clean Energy Works Oregon Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2013-12-31

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

Energy Impact Illinois - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2014-02-18

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

Technical project of complex fast cycle heat treatment of hydrogenous coal preparation

OpenAIRE

Moiseev, V. A.; Andrienko, V. G.; Pileckij, V. G.; Urvancev, A. I.; Gvozdyakov, Dmitry Vasilievich; Gubin, Vladimir Evgenievich; Matveev, Aleksandr Sergeevich; Savostiyanova, Ludmila Viktorovna

2015-01-01

Problems of heat-treated milled hydrogenous coal preparation site creation in leading fast cycle heat treatment complex were considered. Conditions for effective use of electrostatic methods of heat-treated milled hydrogenous coal preparation were set. Technical project of heat treatment of milled hydrogenous coal preparation site was developed including coupling of working equipment complex on fast heat treatment and experimental samples of equipment being designed for manufacturing. It was ...

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

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)

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-08-17

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

DE-FG02-04ER63746 FinalTechnicalReport

Energy Technology Data Exchange (ETDEWEB)

Lidstrom, M.E.

2009-09-05

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

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.

10-75-kWe-reactor-powered organic Rankine-cycle electric power systems (ORCEPS) study. Final technical report

Energy Technology Data Exchange (ETDEWEB)

1977-03-30

This 10-75 kW(e) Reactor-ORCEPS study was concerned with the evaluation of several organic Rankine cycle energy conversion systems which utilized a /sup 235/U-ZrH reactor as a heat source. A liquid metal (NaK) loop employing a thermoelectric converter-powered EM pump was used to transfer the reactor energy to the organic working fluid. At moderate peak cycle temperatures (750/sup 0/F), power conversion unit cycle efficiencies of up to 25% and overall efficiencies of 20% can be obtained. The required operating life of seven years should be readily achievable. The CP-25 (toluene) working fluid cycle was found to provide the highest performance levels at the lowest system weights. Specific weights varies from 100 to 50 lb/kW(e) over the power level range 10 to 75 kW(e). (DLC)

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

2010-07-01

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

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

NUFACTS-nuclear fuel cycle activity simulator: reference manual. Final report

International Nuclear Information System (INIS)

Triplett, M.B.; Waddell, J.D.; Breese, T.A.

1978-01-01

The Nuclear Fuel Cycle Activity Simulator (NUFACTS) is a package of FORTRAN subroutines which facilitate the simulation of a diversity of nuclear power growth scenarios. An approach to modeling the nuclear fuel cycle has been developed that is highly adaptive and capable of addressing a variety of problems. Being a simulation model rather than an optimization model, NUFACTS mimics the events and processes that are characteristic of the nuclear fuel cycle. This approach enables the model user to grasp the modeling approach rather quickly. Within this report descriptions of the model and its components are provided with several emphases. First, a discussion of modeling approach and basic assumptions is provided. Next, instructions are provided for generating data, inputting the data properly, and running the code. Finally, detailed descriptions of individual program element are given as an aid to modifying and extending the present capabilities

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.

Feasibility study on commercialization of fast breeder reactor cycle systems interim report of phase II. Technical study report for nuclear fuel cycle systems

International Nuclear Information System (INIS)

Sato, Koji; Amamoto, Ippei; Inoue, Akira

2004-06-01

As a part of the feasibility study on commercialization of fast breeder reactor cycle systems, the plant concept concerning the fuel cycle systems (combination of the reprocessing and the fuel fabrication) has been constructed to reduce their total cost by the introduction of various innovative techniques and to apply their utmost superior efficiency from such standpoints of a decrease in the environmental burden, better resource utilization and proliferation resistance improvement by the low decontamination transuranium element (TRU) recycle. This interim report of Phase II describes the results of an on-going study which will cover a five-year period. For oxide fuels, the system which combines the use of the advanced aqueous reprocessing using three main methods such as the crystallization method, the simplified solvent extraction method, and the extraction chromatography method for minor actinide (MA) recovery, as well as the simplified pelletizing fuel fabrication which rationalized a powder mixing process etc., has abundant current results and a high technical feasibility for the basic process. Though this system faces difficulties in the technical development of control technology of the extraction chromatography and the fabrication technology of low decontamination TRU fuel etc., its expected practical use is possible at an early stage. As for the super-critical direct extraction reprocessing, it is necessary to fulfill more basic data although further economical improvement of an advanced aqueous reprocessing is expected. The system which combines the advanced aqueous reprocessing and the gelation sphere packing fuel fabrication has the advantage of lesser dispersion of the fine powder due to the use of solution and granule in the fuel fabrication process. However, this system will shoulder additional cost for the reagent recovery process and the waste liquid treatment process due to need to dispose of a large bulk of process waste liquid. The system which

Issues in the selection of the LMFBR steam cycle

International Nuclear Information System (INIS)

Buschman, H.W.; McConnell, R.J.

1983-01-01

Unlike the light-water reactor, the liquid-metal fast breeder reactor (LMFBR) allows the designer considerable latitude in the selection of the steam cycle. This latitude in selection has been exercised by both foreign and domestic designers, and thus, despite the fact that over 25 LMFBR's have been built or are under construction, a consensus steam cycle has not yet evolved. This paper discusses the LMFBR steam cycles of interest to the LMFBR designer, reviews which of these cycles have been employed to date, discusses steam-cycle selection factors, discusses why a consensus has not evolved, and finally, concludes that the LMFBR steam-cycle selection is primarily one of technical philosophy with several options available

Using Model-Based System Engineering to Provide Artifacts for NASA Project Life-Cycle and Technical Reviews Presentation

Science.gov (United States)

Parrott, Edith L.; Weiland, Karen J.

2017-01-01

This is the presentation for the AIAA Space conference in September 2017. It highlights key information from Using Model-Based Systems Engineering to Provide Artifacts for NASA Project Life-cycle and Technical Reviews paper.

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

Synthesizing Huber's Problem Solving and Kolb's Learning Cycle: A Balanced Approach to Technical Problem Solving

Science.gov (United States)

Kamis, Arnold; Khan, Beverly K.

2009-01-01

How do we model and improve technical problem solving, such as network subnetting? This paper reports an experimental study that tested several hypotheses derived from Kolb's experiential learning cycle and Huber's problem solving model. As subjects solved a network subnetting problem, they mapped their mental processes according to Huber's…

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

de Szoeke, Simon P. [Oregon State Univ., Corvallis, OR (United States)

2018-03-02

The investigator and DOE-supported student [1] retrieved vertical air velocity and microphysical fall velocity retrieval for VOCALS and CAP-MBL homogeneous clouds. [2] Calculated in-cloud and cloud top dissipation calculation and diurnal cycle computed for VOCALS. [3] Compared CAP-MBL Doppler cloud radar scenes with (Remillard et al. 2012) automated classification.

Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-05-01

The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately

Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-05-01

The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately.

'BACO' code: Cogeneration cycles heat balance; El programa BACO (Balance de Ciclos de Cogeneracion)

Energy Technology Data Exchange (ETDEWEB)

Huelamo Martinez, E; Conesa Lopez, P; Garcia Kilroy, P [Empresarios Agrupados, A.I.E., Madrid (Spain)

1993-12-15

This paper presents a code, developed by Empresarios Agrupados, sponsored by OCIDE, CSE and ENHER, that, with Electrical Utilities as final users, allows to make combined and cogeneration cycles technical-economical studies. (author)

Models for waste life cycle assessment: Review of technical assumptions

DEFF Research Database (Denmark)

Gentil, Emmanuel; Damgaard, Anders; Hauschild, Michael Zwicky

2010-01-01

A number of waste life cycle assessment (LCA) models have been gradually developed since the early 1990s, in a number of countries, usually independently from each other. Large discrepancies in results have been observed among different waste LCA models, although it has also been shown that results...... from different LCA studies can be consistent. This paper is an attempt to identify, review and analyse methodologies and technical assumptions used in various parts of selected waste LCA models. Several criteria were identified, which could have significant impacts on the results......, such as the functional unit, system boundaries, waste composition and energy modelling. The modelling assumptions of waste management processes, ranging from collection, transportation, intermediate facilities, recycling, thermal treatment, biological treatment, and landfilling, are obviously critical when comparing...

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-03-29

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-02-29

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

Long-term alternatives for nuclear fuel cycles

International Nuclear Information System (INIS)

Vira, J.; Vieno, T.

1981-07-01

Several technical alternatives have been proposed to the nuclear spent fuel management but the practical experience on any of these is small or totally lacking. Since the management method is also connected with the composition of fresh fuel, the comparison of the alternatives must include the whole fuel cycle of a nuclear power plant. In the planning of the nuclear fuel cycle over a time range of several decades a consideration must be given, in addition, to the potential of the new reactor types with increased efficiency of uranium utilization. For analyses and mutual comparisons of the fuel cycle alternatives a number of computer models have been designed and implemented at the Technical Research Centre of Finland. Given the estimated boundary conditions the models can be used to study the impact of different goals and requirements on the fuel cycle decisions. Further, they facilitate cost predictions and display information on the role of the intrinsic uncertainties in the decision-making. The conclusions of the study are tied to the questions of price and availability of uranium. Hence, for instance, the benefits from the reprocessing of spent fuel might prove to be small when compared to the costs required, especially as the current reprocessing contracts do not allow the custemer to dismiss the duty of building the final disposal facilities for high level radioactive waste. For a few decades the final decisions can be postponed by extending the interim storage period. Farther in the future the decisions in the nuclear fuel cycle arrangements will more link to the introduction of the fast breeder reactors. (author)

EXPERIMENTAL AND THEORETICAL INVESTIGATIONS OF NEW POWER CYCLES AND ADVANCED FALLING FILM HEAT EXCHANGERS; FINAL

International Nuclear Information System (INIS)

Arsalan Razani; Kwang J. Kim

2001-01-01

The final report for the DOE/UNM grant number DE-FG26-98FT40148 discusses the accomplishments of both the theoretical analysis of advanced power cycles and experimental investigation of advanced falling film heat exchangers. This final report also includes the progress report for the third year (period of October 1, 2000 to September 30, 2001). Four new cycles were studied and two cycles were analyzed in detail based on the second law of thermodynamics. The first cycle uses a triple combined cycle, which consists of a topping cycle (Brayton/gas), an intermediate cycle (Rankine/steam), and a bottoming cycle (Rankine/ammonia). This cycle can produce high efficiency and reduces the irreversibility of the Heat Recovery Steam Generator (HRSC) of conventional combined power cycles. The effect of important system parameters on the irreversibility distribution of all components in the cycle under reasonable practical constraints was evaluated. The second cycle is a combined cycle, which consists of a topping cycle (Brayton/gas) and a bottoming cycle (Rankine/ammonia) with integrated compressor inlet air cooling. This innovative cycle can produce high power and efficiency. This cycle is also analyzed and optimized based on the second the second law to obtain the irreversibility distribution of all components in the cycle. The results of the studies have been published in peer reviewed journals and ASME conference proceeding. Experimental investigation of advanced falling film heat exchangers was conducted to find effective additives for steam condensation. Four additives have been selected and tested in a horizontal tube steam condensation facility. It has been observed that heat transfer additives have been shown to be an effective way to increase the efficiency of conventional tube bundle condenser heat exchangers. This increased condensation rate is due to the creation of a disturbance in the liquid condensate surround the film. The heat transfer through such a film has

Fuel cycle and waste newsletter, Vol. 3, No. 3, December 2007

International Nuclear Information System (INIS)

2007-12-01

This issue of the Fuel Cycle and Waste Newsletter reports on the IAEA's International Conference on Research Reactors which focused on sharing the latest scientific, technical and safety information related to research reactors including projects on design, construction and commissioning of new research facilities. This issue further covers reports of some of the activities performed by the Division of Nuclear Fuel Cycle and Waste Technology including information on upgrading radioactive waste management facilities, aqueous homogeneous reactors for isotope production, activities of the contact experts group in 2007, current activities related to HEU minimization, repatriation of radioactive sources in Nigeria, the 2007 TWGNFCO (Nuclear Fuel Cycle Options and Spent Fuel Management) meeting, the stakeholder involvement in decommissioning (draft technical report in preparation), initial activities of the International Decommissioning Network (IDN), spent fuel publications, the thorium fuel cycle, the Nuclear Fuel Cycle Simulation System (NFCSS). Finally, it presents a bibliography of recent publications of IAEA's Division of Nuclear Fuel Cycle and Waste Technology as well as a list of Meetings in 2008

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.

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)

Technical ability of new MTR high-density fuel alloys regarding the whole fuel cycle

International Nuclear Information System (INIS)

Durand, J.P.; Maugard, B.; Gay, A.

1998-01-01

The development of new fuel alloys could provide a good opportunity to improve drastically the fuel cycle on the neutronic performances and the reprocessing point of view. Nevertheless, those parameters can only be considered if the fuel manufacture feasibility has been previously demonstrated. As a matter of fact, a MTR work group involving French partners (CEA, CERCA, COGEMA) has been set up in order to evaluate the technical ability of new fuels considering the whole fuel cycle. In this paper CERCA is presenting the preliminary results of UMo and UNbZr fuel plate manufacture, CEA is comparing to U 3 Si 2 the neutronic performances of fuels such as UMo, UN, UNbZr, while COGEMA is dealing with the reprocessing feasibility. (author)

Engineering Technical Review Planning Briefing

Science.gov (United States)

Gardner, Terrie

2012-01-01

The general topics covered in the engineering technical planning briefing are 1) overviews of NASA, Marshall Space Flight Center (MSFC), and Engineering, 2) the NASA Systems Engineering(SE) Engine and its implementation , 3) the NASA Project Life Cycle, 4) MSFC Technical Management Branch Services in relation to the SE Engine and the Project Life Cycle , 5) Technical Reviews, 6) NASA Human Factor Design Guidance , and 7) the MSFC Human Factors Team. The engineering technical review portion of the presentation is the primary focus of the overall presentation and will address the definition of a design review, execution guidance, the essential stages of a technical review, and the overall review planning life cycle. Examples of a technical review plan content, review approaches, review schedules, and the review process will be provided and discussed. The human factors portion of the presentation will focus on the NASA guidance for human factors. Human factors definition, categories, design guidance, and human factor specialist roles will be addressed. In addition, the NASA Systems Engineering Engine description, definition, and application will be reviewed as background leading into the NASA Project Life Cycle Overview and technical review planning discussion.

Life cycle management of analytical methods.

Science.gov (United States)

Parr, Maria Kristina; Schmidt, Alexander H

2018-01-05

In modern process management, the life cycle concept gains more and more importance. It focusses on the total costs of the process from invest to operation and finally retirement. Also for analytical procedures an increasing interest for this concept exists in the recent years. The life cycle of an analytical method consists of design, development, validation (including instrumental qualification, continuous method performance verification and method transfer) and finally retirement of the method. It appears, that also regulatory bodies have increased their awareness on life cycle management for analytical methods. Thus, the International Council for Harmonisation of Technical Requirements for Pharmaceuticals for Human Use (ICH), as well as the United States Pharmacopeial Forum discuss the enrollment of new guidelines that include life cycle management of analytical methods. The US Pharmacopeia (USP) Validation and Verification expert panel already proposed a new General Chapter 〈1220〉 "The Analytical Procedure Lifecycle" for integration into USP. Furthermore, also in the non-regulated environment a growing interest on life cycle management is seen. Quality-by-design based method development results in increased method robustness. Thereby a decreased effort is needed for method performance verification, and post-approval changes as well as minimized risk of method related out-of-specification results. This strongly contributes to reduced costs of the method during its life cycle. Copyright © 2017 Elsevier B.V. All rights reserved.

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

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

International Nuclear Information System (INIS)

John Tanis

2005-01-01

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

FERMI(at)Elettra FEL Design Technical Optimization Final Report

International Nuclear Information System (INIS)

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

2006-01-01

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

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

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.

Economic analysis of fast reactor fuel cycle with different modes

International Nuclear Information System (INIS)

Ding Xiaoming

2014-01-01

Because of limitations on the access to technical and economic data and the lack of effective verification, the lack of in-depth study on the economy of fast reactor fuel cycle in China. This paper introduces the analysis and calculation results of the levelized cost of electricity (LCOE) under three different fuel cycle modes including fast reactor fuel cycle carried out by Massachusetts Institute of Technology (MIT). The author used the evaluation method and hypothesis parameters provided by the MIT to carry out the sensitivity analysis for the impact of the overnight cost, the discount rate and changes of uranium price on the LCOE under three fuel cycle modes. Finally, some suggestions are proposed on the study of economy in China's fast reactor fuel cycle. (authors)

Eukaryotic Cell Cycle as a Test Case for Modeling Cellular Regulation in a Collaborative Problem-Solving Environment

Science.gov (United States)

2007-03-01

computer models of cell cycle regulation in a variety of organisms, including yeast cells, amphibian embryos, bacterial cells and human cells. These...and meiosis ), but they do not nullify the central role played by irreversible, alternating START and FINISH transitions in the cell cycle. 32...AFRL-IF-RS-TR-2007-69 Final Technical Report March 2007 EUKARYOTIC CELL CYCLE AS A TEST CASE FOR MODELING CELLULAR REGULATION IN A

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

AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle; AREVA Technical Days (ATD) session 2: les activites du pole Aval du cycle du combustible nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1999-11-01

In the second half of the 20th century nuclear power has evolved from the research and development environment to an industry that supplies 16% of the world's electricity. By the end of 1997, over 8500 reactor-years of operating experience had been accumulated. Global environmental change, and the continuing increase in global energy supply required to provide increasing populations with an improving standard of living, make the contribution from nuclear energy even more important for the next century. For nuclear power to achieve its full potential and make its needed contribution, it must be safe, economical, reliable and sustainable. All of these factors can be enhanced by judicious choice and development of advanced fuel cycle options. The Technical Committee Meeting (TCM) on Fuel Cycle Options for Light Water Reactors and Heavy Water Reactors was hosted by Atomic Energy of Canada Limited (AECL) on behalf of the Canadian Government and was jointly conducted within the frame of activities of the IAEA International Working Group on Advanced Technologies for Light Water Reactors (IWG-LWR) and the IAEA International Working Group on Advanced Technologies for Heavy Water Reactors (IWG-HWR). The TCM provided the opportunity to have in-depth discussions on important technical topics which were highlighted in the International Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities, held in Vienna, 3-6 June 1997. The main results and conclusions of the TCM were presented as input for discussion at the first meeting of the IAEA newly formed International Working Group on Fuel Cycle Options

Using Model-Based Systems Engineering To Provide Artifacts for NASA Project Life-Cycle and Technical Reviews

Science.gov (United States)

Parrott, Edith L.; Weiland, Karen J.

2017-01-01

The ability of systems engineers to use model-based systems engineering (MBSE) to generate self-consistent, up-to-date systems engineering products for project life-cycle and technical reviews is an important aspect for the continued and accelerated acceptance of MBSE. Currently, many review products are generated using labor-intensive, error-prone approaches based on documents, spreadsheets, and chart sets; a promised benefit of MBSE is that users will experience reductions in inconsistencies and errors. This work examines features of SysML that can be used to generate systems engineering products. Model elements, relationships, tables, and diagrams are identified for a large number of the typical systems engineering artifacts. A SysML system model can contain and generate most systems engineering products to a significant extent and this paper provides a guide on how to use MBSE to generate products for project life-cycle and technical reviews. The use of MBSE can reduce the schedule impact usually experienced for review preparation, as in many cases the review products can be auto-generated directly from the system model. These approaches are useful to systems engineers, project managers, review board members, and other key project stakeholders.

Sensitivity of nuclear fuel-cycle cost to uncertainties in nuclear data. Final report

International Nuclear Information System (INIS)

Becker, M.; Harris, D.R.

1980-11-01

An improved capability for assessing the economic implications of uncertainties in nuclear data and methods on the power reactor fuel cycle was developed. This capability is applied to the sensitivity analysis of fuel-cycle cost with respect to changes in nuclear data and related computational methods. Broad group sensitivities for both a typical BWR and a PWR are determined under the assumption of a throwaway fuel cycle as well as for a scenario under which reprocessing is allowed. Particularly large dollar implications are found for the thermal and resonance cross sections of fissile and fertile materials. Sensitivities for the throwaway case are found to be significantly larger than for the recycle case. Constrained sensitivities obtained for cases in which information from critical experiments or other benchmarks is used in the design calculation to adjust a parameter such as anti ν are compared with unconstrained sensitivities. Sensitivities of various alternate fuel cycles were examined. These included the extended-burnup (18-month) LWR cycle, the mixed-oxide (plutonium) cycle, uranium-thorium and denatured uranium-thorium cycles, as well as CANDU-type reactor cycles. The importance of the thermal capture and fission cross sections of 239 Pu is shown to be very large in all cases. Detailed, energy dependent sensitivity profiles are provided for the thermal range (below 1.855 eV). Finally, sensitivity coefficients are combined with data uncertainties to determine the impact of such uncertainties on fuel-cycle cost parameters

Air bottoming cycle, an alternative to combined cycles. Final report

Energy Technology Data Exchange (ETDEWEB)

Kaikko, J. [Royal Inst. of Techn., Stockholm (Sweden). Dept. of Energy Technology

2001-10-01

In this work, the idea of Air Bottoming Cycle (ABC) has been studied. The objectives for the work have been to establish an understanding of the concept for power and heat generation as well as to find - if possible - feasible concepts for future use in the Swedish energy system. Combined cycle in power generation is an established technology. In the conventional combined cycle, a gas turbine works as a topping cycle together with the steam (Rankine) bottoming cycle. In the ABC the steam bottoming cycle is replaced with a gas turbine (Brayton) bottoming cycle having air as a working fluid. The two gas turbines are thermally connected over a gas-to-gas heat exchanger. This concept promises savings in weight and cost, as well as operating benefits, compared to the Rankine bottoming technology. The ABC has been modelled using a heat balance program, and a parametric study for the concept optimisation as well as for off-design analysis has been performed. Performance of the ABC has been compared to other, established technologies. A preliminary economic evaluation has been made. As a result of the study, it is clarified that the Rankine bottoming cycle with steam remains superior to the ABC as regards electrical efficiency in the medium and large power scale. For small-scale applications (<10 MW{sub e}) where the thermodynamic advantage of the Rankine cycle is not dominating any longer and its economy is burdened by the heavy investment structure, the ABC becomes the better alternative for energy utilisation. A preliminary economic evaluation shows that (at energy prices autumn 2000) the ABC is at the same level as the comparable small-scale cogeneration installations. Due to high power-to-heat ratio however, higher electricity prices will favour the ABC. One interesting feature of the ABC is that about 50% of the dissipated low-value heat from the cycle is carried by clean (sterile) air at the temperature around 200 deg C. This air can be utilised for space heating or

DOE FINAL TECHNICAL REPORT RP

Energy Technology Data Exchange (ETDEWEB)

RUSS PETERMAN

2012-01-01

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

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

International Nuclear Information System (INIS)

1992-11-01

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

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

Energy Technology Data Exchange (ETDEWEB)

1992-11-01

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

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

Fuel cycle technologies - The next 50 years

International Nuclear Information System (INIS)

Chamberlain, L.N.; Ion, S.E.; Patterson, J.

1997-01-01

World energy demands are set to increase through the next Millennium. As fossil fuel reserves fall and environmental concerns increase there is likely to be a growing dependence on nuclear and renewable sources for electricity generation. This paper considers some of the desirable attributes of the nuclear fuel cycle in the year 2050 and emphasises the importance of considering the whole of the fuel cycle in an integrated way - the concept of the 'holistic' fuel cycle. We then consider how some sectors of the fuel cycle will develop, through a number of multi- national contributions covering: enrichment, fuel, aqueous reprocessing, non-aqueous reprocessing, P and T, MOX, direct disposal, waste. Finally, we summarize some of the key technical and institutional challenges that lie ahead if nuclear power is going to play its part in ensuring that planet Earth is a safe and hospitable place to live. (author)

Technical assistance contractor Management Plan. Final [report

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

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

Materials reliability in the back end of the nuclear fuel cycle

International Nuclear Information System (INIS)

1987-05-01

Operating experience of nuclear fuel cycle facilities has proved that the performance and availability of key equipment largely depend on the reliability of its construction materials. In general, the materials of construction have performed well in accordance with the design criteria of equipment. In some cases, however, materials failure problems have been encountered, the causes of which are related to their corrosion and mechanical degradation. In response to the growing interest in these topics, the IAEA convened the Technical Committee Meeting on ''Materials Reliability in the Back-End of the Nuclear Fuel Cycle'' at its Headquarters from September 2 to 5, 1986. This Technical Document contains the 15 papers presented during the Meeting. Material aspects of the following fields of the back-end of the nuclear fuel cycle are covered: interim and long-term storage of spent fuel; final disposal of spent fuel; storage and vitrification of High Level Liquid Wastes (HLLW); long-term storage of High Level Wastes (HLW); and spent fuel treatment

Air bottoming cycle, an alternative to combined cycles. Final report

Energy Technology Data Exchange (ETDEWEB)

Kaikko, J. [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Energy Technology

2002-02-01

In this work, the idea of Air Bottoming Cycle (ABC) has been studied. The objectives for the work have been to establish an understanding of the concept for power and heat generation as well as to find - if possible - feasible concepts for future use in the Swedish energy system. Combined cycle in power generation is an established technology. In the conventional combined cycle, a gas turbine works as a topping cycle together with the steam (Rankine) bottoming cycle. In the ABC the steam bottoming cycle is replaced with a gas turbine (Brayton) bottoming cycle having air as a working fluid. The two gas turbines are thermally connected over a gas-to-gas heat exchanger. This concept promises savings in weight and cost, as well as operating benefits, compared to the Rankine bottoming technology. The ABC has been modelled using a heat balance program, and a parametric study for the concept optimisation as well as for off-design analysis has been performed. Performance of the ABC has been compared to other, established technologies. A preliminary economic evaluation has been made. As a result of the study, it is clarified that the Rankine bottoming cycle with steam remains superior to the ABC as regards electrical efficiency in the medium and large power scale. For small-scale applications (<10 MW{sub e}) where the thermodynamic advantage of the Rankine cycle is not dominating any longer and its economy is burdened by the heavy investment structure, the ABC becomes the better alternative for energy utilisation. A preliminary economic evaluation shows that (at energy prices autumn 2000) the ABC is at the same level as the comparable small-scale cogeneration installations. Due to high power-to-heat ratio however, higher electricity prices will favour the ABC. One interesting feature of the ABC is that about 50% of the dissipated low-value heat from the cycle is carried by clean (sterile) air at the temperature around 200 deg C. This air can be utilised for space heating or

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.

Nuclear fuel cycle system analysis

International Nuclear Information System (INIS)

Ko, W. I.; Kwon, E. H.; Kim, S. G.; Park, B. H.; Song, K. C.; Song, D. Y.; Lee, H. H.; Chang, H. L.; Jeong, C. J.

2012-04-01

The nuclear fuel cycle system analysis method has been designed and established for an integrated nuclear fuel cycle system assessment by analyzing various methodologies. The economics, PR(Proliferation Resistance) and environmental impact evaluation of the fuel cycle system were performed using improved DB, and finally the best fuel cycle option which is applicable in Korea was derived. In addition, this research is helped to increase the national credibility and transparency for PR with developing and fulfilling PR enhancement program. The detailed contents of the work are as follows: 1)Establish and improve the DB for nuclear fuel cycle system analysis 2)Development of the analysis model for nuclear fuel cycle 3)Preliminary study for nuclear fuel cycle analysis 4)Development of overall evaluation model of nuclear fuel cycle system 5)Overall evaluation of nuclear fuel cycle system 6)Evaluate the PR for nuclear fuel cycle system and derive the enhancement method 7)Derive and fulfill of nuclear transparency enhancement method The optimum fuel cycle option which is economical and applicable to domestic situation was derived in this research. It would be a basis for establishment of the long-term strategy for nuclear fuel cycle. This work contributes for guaranteeing the technical, economical validity of the optimal fuel cycle option. Deriving and fulfillment of the method for enhancing nuclear transparency will also contribute to renewing the ROK-U.S Atomic Energy Agreement in 2014

Feasibility study on commercialization of fast breeder reactor cycle system. Interim report of phase 2. Technical study report on synthetic evaluation for FBR cycle

International Nuclear Information System (INIS)

Shiotani, Hiroki; Ohtaki, Akira; Ono, Kiyoshi; Yasumatsu, Naoto; Kubota, Sadae; Heta, Masanori

2004-09-01

This report presents the outline of the development and the results of Synthetic evaluation on the candidate Fast Reactor (FR) cycle system concepts, scenario study on FR cycle deployment and cost-benefit analysis on the candidate FR cycle system concepts in the interim evaluation (FY2001 through FY2003) of the phase 2 of the Japanese 'Feasibility Study on Commercialization of Fast Reactor Cycle System (FS)'. The characteristic evaluation extended to evaluate a new view point of social acceptance besides the viewpoints of safety, economics, reduction of environmental burden, efficient utilization of uranium resource, proliferation resistance, and technical feasibility, which has been considered since the phase 1 of FS. As for the six view points, hierarchy structures and utility functions for quantitative evaluation have been developed and/or improved. Furthermore, the methodology for weighing the viewpoints, which was also developed, made it possible to examine the characteristics of the candidate concepts from all the seven viewpoints. Generally, the FR cycles with sodium-cooled FR were highly evaluated. The characteristic evaluation for alternative power supply systems was also tried in this report for the first time. FR cycle deployment scenarios clarified the necessity of FR cycle deployment and the desirable core features, etc. through the long-term mass flow analysis, which includes comparison among other nuclear fuel cycle schemes and analysis for evaluating the degree to meet future needs, on the typical FR cycle systems. Regarding cost-benefit analysis, both the amount of the cost estimated by the past R and D and the cost in the Road map of FS are used as the investment for FR cycle research and development (R and D), the results showed that the benefit derived from the commercialization of FR cycle will be more than the investment. (author)

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

Heterogenic final cell cycle by chicken retinal Lim1 horizontal progenitor cells leads to heteroploid cells with a remaining replicated genome.

Directory of Open Access Journals (Sweden)

Shahrzad Shirazi Fard

Full Text Available Retinal progenitor cells undergo apical mitoses during the process of interkinetic nuclear migration and newly generated post-mitotic neurons migrate to their prospective retinal layer. Whereas this is valid for most types of retinal neurons, chicken horizontal cells are generated by delayed non-apical mitoses from dedicated progenitors. The regulation of such final cell cycle is not well understood and we have studied how Lim1 expressing horizontal progenitor cells (HPCs exit the cell cycle. We have used markers for S- and G2/M-phase in combination with markers for cell cycle regulators Rb1, cyclin B1, cdc25C and p27Kip1 to characterise the final cell cycle of HPCs. The results show that Lim1+ HPCs are heterogenic with regards to when and during what phase they leave the final cell cycle. Not all horizontal cells were generated by a non-apical (basal mitosis; instead, the HPCs exhibited three different behaviours during the final cell cycle. Thirty-five percent of the Lim1+ horizontal cells was estimated to be generated by non-apical mitoses. The other horizontal cells were either generated by an interkinetic nuclear migration with an apical mitosis or by a cell cycle with an S-phase that was not followed by any mitosis. Such cells remain with replicated DNA and may be regarded as somatic heteroploids. The observed heterogeneity of the final cell cycle was also seen in the expression of Rb1, cyclin B1, cdc25C and p27Kip1. Phosphorylated Rb1-Ser608 was restricted to the Lim1+ cells that entered S-phase while cyclin B1 and cdc25C were exclusively expressed in HPCs having a basal mitosis. Only HPCs that leave the cell cycle after an apical mitosis expressed p27Kip1. We speculate that the cell cycle heterogeneity with formation of heteroploid cells may present a cellular context that contributes to the suggested propensity of these cells to generate cancer when the retinoblastoma gene is mutated.

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.

AGR-3/4 Final Data Qualification Report for ATR Cycles 151A through 155B-1

Energy Technology Data Exchange (ETDEWEB)

Pham, Binh T. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

Analysis System (NDMAS). The AGR 3/4 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates, pressure, and moisture content), and Fission Product Monitoring System (FPMS) data (release rates, release to birth rate ratios [R/Bs], and particle failure counts) for each of the twelve capsules in the AGR 3/4 experiment. During Outage Cycle 155A, fourteen flow meters were installed downstream from fourteen FPMS monitors to measure flows from the monitors; qualification status of these data are also included in the report. The final data qualification status for these data streams is determined by a Data Review Committee (DRC) composed of AGR technical leads, Sitewide Quality Assurance (QA), and NDMAS analysts. For ATR Cycles 151A through 154B, the DRC convened on February 12, 2014, reviewed the data acquisition process, and considered whether the data met the requirements for data collection as specified in QA approved INL ART TDO data collection plans. The DRC also examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in this report. The qualification status of AGR-3/4 irradiation data during the first six cycles were previously reported in INL/EXT-14-31186 document. This report presents data qualification status for the entire AGR-3/4 irradiation.

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

Science.gov (United States)

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

2012-01-01

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

Final Technical Report for SISGR: Ultrafast Molecular Scale Chemical Imaging

Energy Technology Data Exchange (ETDEWEB)

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

2017-04-10

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

Alternative fuel cycles and non-proliferation aspects

International Nuclear Information System (INIS)

Kessler, G.

1980-10-01

The most important physical characteristics of the U/Pu and the Th/U fuel cycles and the technical data of the most significant converter reactors operating with Th/U fuel are outlined in the report. Near breeders as well as breeders with a thermal neutron spectrum are briefly discussed, and the potential of breeders with fast neutron spectra in the Th/U fuel is outlined. The essential criteria for the comparison of the alternative fuel cycles with the reference Pu/U cycle are the consumption of natural uranium, the numbers of U-233 producing and U-233 consuming converter reactors and the amounts of fission material transported and handled within the fuel cycle (reprocessing, refabrication). Although the alternative U/Th fuel cycles are feasible with some advantages and some disadvantages as compared to the reference U/Pu cycle, not much experience has so far been gathered with pilot plants of the fuel cycle. The respective status in reprocessing, refabrication and waste disposal is briefly discussed. Finally, a comparison of the risk potential inherent in secular storage is presented and questions of resistance to proliferation and of safeguards of the U/Th cycle are discussed

Safety of and regulations for nuclear fuel cycle facilities. Report of a technical committee meeting

International Nuclear Information System (INIS)

2001-05-01

In order to compile information on the nature of the safety concerns and current status of the regulations concerning nuclear fuel cycle facilities in Member States, an IAEA Technical Committee meeting on this topic was convened from 8 to 12 May 2000 in Vienna. The present publication contains the results of this meeting. The contributions of the participants in Annex 3 exemplify the work done in some Member States to develop an adequate regulatory framework to oversee the safe operation of these facilities

Treatment and final storage of radioactive wastes from the nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Krause, H [Kernforschungszentrum Karlsruhe (Germany, F.R.)

1977-05-01

Types, amounts and activity concentrations of the radioactive wastes arising from the different sections of the fuel cycle are described as well as the methods of their treatment and final disposal. By conversion to glass products, highly active fission product solutions can be transferred into a form well suited for final disposal. Low and medium level waste waters are purified so far that safe discharge or reuse is possible. The concentrates thus produced are incorporated into concrete or bitumen. Baling lends itself for treatment of non-combustible solid wastes. Combustible wastes can be incinerated, the residues are incorporated into concrete. For final storage of the conditioned wastes, salt formations in the deep underground are chosen in the Federal Republic of Germany. They offer a series of favourable preconditions for this purpose and guarantee the isolation of the radionuclides from the biocycle over secular periods of time.

Evaluation of technical feasibility of closed-cycle non-equilibrium MHD power generation with direct coal firing. Final report, Task I

Energy Technology Data Exchange (ETDEWEB)

1981-11-01

Program accomplishments in a continuing effort to demonstrate the feasibility of direct coal-fired, closed-cycle MHD power generation are reported. This volume contains the following appendices: (A) user's manual for 2-dimensional MHD generator code (2DEM); (B) performance estimates for a nominal 30 MW argon segmented heater; (C) the feedwater cooled Brayton cycle; (D) application of CCMHD in an industrial cogeneration environment; (E) preliminary design for shell and tube primary heat exchanger; and (F) plant efficiency as a function of output power for open and closed cycle MHD power plants. (WHK)

DIMEC - Final Report

DEFF Research Database (Denmark)

Conrad, Finn

1997-01-01

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

Energy generation and the sulfur-carbon cycles: Final technical report for period March 1981 thru February 1985

International Nuclear Information System (INIS)

Zeikus, J.G.

1987-05-01

The aim of this research was to understand the role of anaerobic bacteria in natural and man-influenced carbon cycles in nature. The major goal was to elucidate how sulfur metabolism influenced organic decomposition in aquatic sediments. The research compared these processes in two different anaerobic ecosystems: the sulfate-depleted sediments of Lake Mendota, Wisconsin and the sulfate-saturated sediments of Great Salt Lake, Utah. The approach was both ecological and physiological, and employed both in situ characterization of carbon and sulfur metabolism with radiotracers and laboratory species isolation-characterization studies with pure and defined mixed cultures to demonstrate the prevalent environmental paths of carbon electrons, and sulfur during the anaerobic decomposition of organic matter. The significance of this research encompassed fundamental knowledge of the carbon sulfur cycles, applied knowledge on the microbial genesis of flammable gas and oil and extended knowledge on the diversity and metabolic activity of obligately anaerobic bacteria in nature. 13 refs

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.

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

Current concept of the nuclear fuel cycle in the Czech Republic

International Nuclear Information System (INIS)

Priman, V.; Vesely, P.; Sedina, M.

2001-01-01

The article provides an overview of the major activities within the nuclear fuel cycle as practised by the Czech utility CEZ, a. s. Efforts in the fuel cycle practice are focused on the implementation of standard business principles with CEZ's contractual suppliers; application of new legislation and international design standards; and on achieving a higher technical standard of nuclear fuel and its better overall utilisation by nuclear power plants. Business activities in the procurement of nuclear materials and their diversification are discussed. The last part of the article, which is devoted to the fuel cycle back-end, describes the adopted strategy of extended spent fuel storage associated with a postponement of the final disposal. The basic principles of the CEZ's fuel cycle back-end strategy are also summarised. (author)

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.

Evaluating Indicators and Life Cycle Inventories for Processes in Early Stages of Technical Readiness

Energy Technology Data Exchange (ETDEWEB)

Tan, Eric C [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Smith, Raymond [U.S. Environmental Protection Agency (EPA); Ruiz-Mercado, Gerardo [U.S. Environmental Protection Agency (EPA)

2017-11-01

This presentation examines different methods for analyzing manufacturing processes in the early stages of technical readiness. Before developers know much detail about their processes, it is valuable to apply various assessments to evaluate their performance. One type of assessment evaluates performance indicators to describe how closely processes approach desirable objectives. Another type of assessment determines the life cycle inventories (LCI) of inputs and outputs for processes, where for a functional unit of product, the user evaluates the resources used and the releases to the environment. These results can be compared to similar processes or combined with the LCI of other processes to examine up-and down-stream chemicals. The inventory also provides a listing of the up-stream chemicals, which permits study of the whole life cycle. Performance indicators are evaluated in this presentation with the U.S. Environmental Protection Agency's GREENSCOPE (Gauging Reaction Effectiveness for ENvironmental Sustainability with a multi-Objective Process Evaluator) methodology, which evaluates processes in four areas: Environment, Energy, Economics, and Efficiency. The method develops relative scores for indicators that allow comparisons across various technologies. In this contribution, two conversion pathways for producing cellulosic ethanol from biomass, via thermochemical and biochemical routes, are studied. The information developed from the indicators and LCI can be used to inform the process design and the potential life cycle effects of up- and down-stream chemicals.

AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle

International Nuclear Information System (INIS)

2002-01-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

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

International Nuclear Information System (INIS)

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

2015-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-12-31

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

AeroPropulsoServoElasticity: Dynamic Modeling of the Variable Cycle Propulsion System

Science.gov (United States)

Kopasakis, George

2012-01-01

This presentation was made at the 2012 Fundamental Aeronautics Program Technical Conference and it covers research work for the Dynamic Modeling of the Variable cycle Propulsion System that was done under the Supersonics Project, in the area of AeroPropulsoServoElasticity. The presentation covers the objective for the propulsion system dynamic modeling work, followed by the work that has been done so far to model the variable Cycle Engine, modeling of the inlet, the nozzle, the modeling that has been done to model the affects of flow distortion, and finally presenting some concluding remarks and future plans.

Development status and operational features of the high temperature gas-cooled reactor. Final report

International Nuclear Information System (INIS)

Winkleblack, R.K.

1976-04-01

The objective of this study is to investigate the maturity of HTR-technology and to look out for possible technical problems, concerning introduction of large HTR power plants into the market. Further state and problems of introducing and closing the thorium fuel cycle is presented and judged. Finally, the state of development of advanced HTR-concepts for electricity production, the direct cycle HTR with helium turbine, and the gas-cooled fast breeder is discussed. In preparing the study, both HTR concepts with spherical and block-type fuel elements have been considered

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

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

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

International Nuclear Information System (INIS)

1998-01-01

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

Technical review of externalities issues. Final report

International Nuclear Information System (INIS)

Niemeyer, V.

1994-12-01

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

Evaluation of technical feasibility of closed-cycle non-equilibrium MHD power generation with direct coal firing. Final report, Task 1

Energy Technology Data Exchange (ETDEWEB)

1981-11-01

Program accomplishments in a continuing effort to demonstrate the feasibility of direct coal fired, closed cycle, magnetohydrodynamic power generation are detailed. These accomplishments relate to all system aspects of a CCMHD power generation system including coal combustion, heat transfer to the MHD working fluid, MHD power generation, heat and cesium seed recovery and overall systems analysis. Direct coal firing of the combined cycle has been under laboratory development in the form of a high slag rejection, regeneratively air cooled cyclone coal combustor concept, originated within this program. A hot bottom ceramic regenerative heat exchanger system was assembled and test fired with coal for the purposes of evaluating the catalytic effect of alumina on NO/sub x/ emission reduction and operability of the refractory dome support system. Design, procurement, fabrication and partial installation of a heat and seed recovery flow apparatus was accomplished and was based on a stream tube model of the full scale system using full scale temperatures, tube sizes, rates of temperature change and tube geometry. Systems analysis capability was substantially upgraded by the incorporation of a revised systems code, with emphasis on ease of operator interaction as well as separability of component subroutines. The updated code was used in the development of a new plant configuration, the Feedwater Cooled (FCB) Brayton Cycle, which is superior to the CCMHD/Steam cycle both in performance and cost. (WHK)

Development and application of basis database for materials life cycle assessment in china

Science.gov (United States)

Li, Xiaoqing; Gong, Xianzheng; Liu, Yu

2017-03-01

As the data intensive method, high quality environmental burden data is an important premise of carrying out materials life cycle assessment (MLCA), and the reliability of data directly influences the reliability of the assessment results and its application performance. Therefore, building Chinese MLCA database is the basic data needs and technical supports for carrying out and improving LCA practice. Firstly, some new progress on database which related to materials life cycle assessment research and development are introduced. Secondly, according to requirement of ISO 14040 series standards, the database framework and main datasets of the materials life cycle assessment are studied. Thirdly, MLCA data platform based on big data is developed. Finally, the future research works were proposed and discussed.

The nuclear fuel cycle light and shadow

International Nuclear Information System (INIS)

Giraud, A.

1977-01-01

The nuclear fuel cycle industry has a far reaching effect on future world energy developments. The growth in turnover of this industry follows a known patterm; by 1985 this turnover will have reached a figure of 2 billion dollars. Furthermore, the fuel cycle plays a determining role in ensuring the physical continuity of energy supplies for countries already engaged in the nuclear domain. Finally, the development of this industry is subject to economic and political constraints which imply the availability of raw materials, technological know-how, and production facilities. Various factors which could have an adverse influence on the cycle: technical, economic, or financial difficulties, environmental impact, nuclear safety, theft or diversion of nuclear materials, nuclear weapon, proliferation risks, are described, and the interaction between the development of the cycle, energy independance, and the fulfillment of nuclear energy programs is emphasized. It is concluded that the nuclear fuel cycle industry is confronted with difficulties due to its extremely rapid growth rate (doubling every 5 years); it is a long time since such a growth rate has been experienced by any heavy industry. The task which lays before us is difficult, but the fruit is worth the toil, as it is the fuel cycle which will govern the growth of the nuclear industry [fr

Final Technical Report. Supporting carbon cycle and earth systems modeling with measurements and analysis from the Howland AmeriFlux Site

Energy Technology Data Exchange (ETDEWEB)

Hollinger, David [USDA Forest Service, Washington, DC (United States); Davidson, E. [Woods Hole Research Center, Falmouth, MA (United States); Dail, D. B. [Univ. of Maine, Orono, ME (United States); Richardson, A. [Harvard Univ., Cambridge, MA (United States)

2016-01-11

This report provides and overview of the work carried out and lists the products produced under the terms of agreement SC0005578 with the USDA Forest Service. This relates to scientific investigation of the carbon cycle at the Howland Forest AmeriFlux site located in central Maine, USDA. The overall goal of this work was to understand the various (and interacting) impacts of a changing climate on carbon cycling at the Howland AmeriFlux site, representative of an important component of the North American boreal forest.

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

Technical Meeting on Grading of the Application of Management System Requirements. Presentations

International Nuclear Information System (INIS)

2012-01-01

The objectives of this Technical Meeting are threefold: - to share international experiences and lessons learned, as well as exchange views on best practices and strategies to overcome the difficulties encountered; - to review and discuss the draft technical report on 'Grading the Application of Management System Requirements, to allow the participants to contribute to the improvement of the document and to enrich it with practical examples; and - to strengthen the international networking of specialists in the field. The topics covered during the meeting will include: - Examples and case studies presented by participants from countries with nuclear facilities (mainly focused on NPPs, and, where appropriate, from research reactors, fuel cycle and waste management facilities) on grading the application of management system requirements and lessons learned. - Reviewing and improving the final draft of a technical report on 'Grading the Application of Management System Requirements', which will supersede the previous guidance: Grading of Quality Assurance Requirement: A Manual (Technical Reports Series No. 328)

Evaluation of duty cycles for heavy-duty urban vehicles : final report of IEA AMF Annex 29

Energy Technology Data Exchange (ETDEWEB)

Nylund, N.O.; Erkkila, K. [VTT Technical Research Centre of Finland, Espoo (Finland); Clark, N. [West Virginia Univ., Morgantown, WV (United States); Rideout, G. [Environment Canada, Ottawa, ON (Canada). Environmental Technology Centre, Emissions Research and Measurement Div

2007-07-01

Heavy-duty vehicles in Europe and North America will require incylinder measures or exhaust gas after-treatment technology to control emissions and meet ever stringent emission requirements. Alternatively, manufacturers can choose clean burning alternative fuels such as natural gas. Although there are no international standards for heavy-duty vehicle chassis dynamometer testing at present, the IEA Implementing Agreements offer excellent platforms for international collaborative research. Harmonization of test methods for vehicles and fuels is one important task. This paper reported on the work of 3 laboratories that have produced emission results for complete heavy-duty vehicles. VTT Technical Research of Finland, Environment Canada and West Virginia University measured standard size urban buses driving various duty cycles on chassis dynamometers. The number of transient test cycles per laboratory varied from 6 to 16. European and North American diesel and natural gas vehicles were included in the vehicle matrix. The objective was to demonstrate how the driving cycle affects the emission performance of conventional and advanced urban buses. Several driving cycles were run on urban buses to better understand the characteristics of different duty cycles; produce a key for cross-interpretation of emission results generated with different cycles; and study the interaction between vehicle, exhaust after-treatment and fuel technologies and test procedures. Fuel consumption and exhaust emissions were measured. The results varied significantly not only by test cycle, but also by vehicle technology. In general, vehicles emissions were directly proportioned to the amount of fuel consumed, with the exception of NOx-emissions from SCR-vehicles. There was a clear difference in the emission profiles of European and North American vehicles. In Europe, fuel efficiency was emphasized, while in North America, more focus was given to regulated exhaust emissions, especially low

Technical and economic feasibility of thermal energy storage. Thermal energy storage application to the brick/ceramic industry. Final report

Energy Technology Data Exchange (ETDEWEB)

Glenn, D.R.

1976-10-01

An initial project to study the technical and economic feasibility of thermal energy storage (TES) in the three major consumer markets, namely, the residential, commercial and industrial sectors is described. A major objective of the study was to identify viable TES applications from which a more concise study could be launched, leading to a conceptual design and in-depth validation of the TES energy impacts. This report documents one such program. The brick/ceramic industries commonly use periodic kilns which by their operating cycle require time-variant energy supply and consequently variable heat rejection. This application was one of the numerous TES opportunities that emerged from the first study, now available from the ERDA Technical Information Center, Oak Ridge, Tennessee, identified as Report No. COO-2558-1.

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...

Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

Seinfeld, John H. [California Inst. of Technology (CalTech), Pasadena, CA (United States)

2015-08-06

This project addressed the following research need in the Atmospheric System Research (ASR) Science and Program Plan: "Measurements downwind of urban sources of aerosol particles and precursor gases have shown that the mass concentration of secondary organic aerosol (SOA) can be several-fold greater than can be explained on the basis of current model calculations using observed precursor concentrations. ASR will continue conducting laboratory experiments on both gas-phase and aqueous-phase SOA formation to characterize the particle formation and the organic gases that react to form new organic aerosol material on aerosol seeds. ASR will use these experiments to guide the development of comprehensive chemical mechanisms... to guide the development of parameterizations that are simple enough to be applied to aerosol life cycle models."

Technical support for open-cycle MHD program

Energy Technology Data Exchange (ETDEWEB)

None

1978-05-01

The support program for open-cycle MHD at Argonne National Lab is developing the analytical tools needed to investigate the performance of the major components in the combined-cycle MHD/steam power system. The analytical effort is centered on the primary components of the system that are unique to MHD and also on the integration of these analytical representations into a model of the entire power producing system. The present project activities include modeling of the combustor, MHD channel, slag separator, and the high-temperature air preheater. In addition, these models are combined into a complete system model, which is at present capable of carrying out optimizations of the entire system on either thermodynamic efficiency or with less confidence, cost of electrical power. Also, in support of the open-cycle program, considerable effort has gone into the formulation of a CDIF Test Plan and a National MHD Test Program.

Survey of the nuclear fuel cycle

International Nuclear Information System (INIS)

Zech, H.J.; Pickert, F.K.

1975-01-01

A brief outline of the technical aspects of the fuel cycle, starting from the mining of uranium up to fuel element fabrication, is followed by a more detailed description of the management of the outer fuel cycle. This includes the system of contracts and their reciprocal technical and chronological interdepence, as well as financial aspects, market conditions and trends. (RB) [de

Closed fuel cycle and contemporary tendencies of the nuclear facilities development

International Nuclear Information System (INIS)

Lelek, V.; Hron, M.

2003-01-01

The decision to develop nuclear facility is given not only through technical and financial arguments, but sometimes even the greater weight is on political, general safety and public acceptance reasons. Moreover a responsible statement about financial needs is at the beginning of the study possible only with a great error (roughly speaking - factor of two) and a time estimation up to the industrial facilities is about fifteen or even more years. If the technical development and realization is successful, we can express a more responsible conclusion only in such long time intervals. During such long periods, the criteria for political and financial decisions could be changed and the technical development will necessary follow the new situation with a change in the stream of money. On the other side, the stream of money into technology leads to a more precise forecast and a more responsible decision for future realizations. We shall try, in the paper, to reflect technical problems in the closed fuel cycle (like solid and liquid fuel options) with the public demands (refusing of nuclear energy and spent fuel disposal generally, preferring waste less technologies) and political safety aspects (nonproliferation, spent fuel storages). There will be a special attention devoted to such problems in smaller countries, where demands for energy cannot be covered by local classical sources and nuclear energy and spent fuel are already long time reality. The organizational measures and tendencies will be analyzed how to compose sufficiently great and qualified collectives to be able to overcome from the local final disposal development to the common technology realizing practically closed fuel cycle and enabling decomposition of water for the hydrogen production during the first half of this century. Overview information will be given about the Czech national technical program within the EU Program (MOST Project) and within the cooperation with Russian institutes in the molten

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

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.

Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving VHTR Efficiency and Testing Material Compatibility - Final Report

International Nuclear Information System (INIS)

Chang H. Oh

2006-01-01

Generation IV reactors will need to be intrinsically safe, having a proliferation-resistant fuel cycle and several advantages relative to existing light water reactor (LWR). They, however, must still overcome certain technical issues and the cost barrier before it can be built in the U.S. The establishment of a nuclear power cost goal of 3.3 cents/kWh is desirable in order to compete with fossil combined-cycle, gas turbine power generation. This goal requires approximately a 30 percent reduction in power cost for state-of-the-art nuclear plants. It has been demonstrated that this large cost differential can be overcome only by technology improvements that lead to a combination of better efficiency and more compatible reactor materials. The objectives of this research are (1) to develop a supercritical carbon dioxide Brayton cycle in the secondary power conversion side that can be applied to the Very-High-Temperature Gas-Cooled Reactor (VHTR), (2) to improve the plant net efficiency by using the carbon dioxide Brayton cycle, and (3) to test material compatibility at high temperatures and pressures. The reduced volumetric flow rate of carbon dioxide due to higher density compared to helium will reduce compression work, which eventually increase plant net efficiency

The last twenty years of the IAEA technical cooperation on the uranium production cycle in Argentina

International Nuclear Information System (INIS)

Lopez, L.

2014-01-01

Since 1993, the National Atomic Energy Commission (Argentina) has been involved in several IAEA Technical Cooperation Projects at interregional, regional and national levels, covering different aspects of the uranium production cycle. The TC referred projects can be listed as follows: - INT 2/015 “Supporting Uranium Exploration Resource Augmentation and Production Using Advanced Techniques” (2012 – Present). - RLA 3/006 - 010 “Upgrading of Uranium Exploration, Exploitation and Yellowcake Production Techniques taking Environmental Problems into Account” (2007 - Present). - ARG 2/014 “Development and Strengthening of the Uranium Mining Cycle Human Resources” (2012 – Present). - ARG 3/012 - 014 "Geology favourability, production feasibility and environmental impact assessment of uranium deposits exploitable by the in situ leaching technology (ISL)'' (2007 - Present). - ARG 3/009 “Development and use of biological techniques for uranium production (ARG 3/009)” (2003 - 2006). - ARG 3/008 “Prospection of uranium and other elements using gamma-ray spectrometry surveys” (2001 – 2005). - ARG 3/007 “Uranium Favorability and Exploration in Argentina” (1993 - 1997). It can be considered that the role of the technological transfer by the IAEA has been highly relevant for increasing the capability of strategically plan and more efficiently carry out the uranium production cycle projects in Argentina. (author)

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

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

Life cycle planning: An evolving concept

International Nuclear Information System (INIS)

Moore, P.J.R.; Gorman, I.G.

1994-01-01

Life-cycle planning is an evolving concept in the management of oil and gas projects. BHP Petroleum now interprets this idea to include all development planning from discovery and field appraisal to final abandonment and includes safety, environmental, technical, plant, regulatory, and staffing issues. This article describes in the context of the Timor Sea, how despite initial successes and continuing facilities upgrades, BHPP came to perceive that current operations could be the victim of early development successes, particularly in the areas of corrosion and maintenance. The search for analogies elsewhere lead to the UK North Sea, including the experiences of Britoil and BP, both of which performed detailed Life of Field studies in the later eighties. These materials have been used to construct a format and content for total Life-cycle plans in general and the social changes required to ensure their successful application in Timor Sea operations and deployment throughout Australia

Catalogue and classification of technical safety standards, rules and regulations for nuclear power reactors and nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Fichtner, N.; Becker, K.; Bashir, M.

1977-01-01

The present report is an up-dated version of the report 'Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants' edited under code No EUR 5362e, August 1975. Like the first version of the report, it constitutes a catalogue and classification of standards, rules and regulations on land-based nuclear power reactors and fuel cycle facilities. The reasons for the classification system used are given and discussed

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.

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

Science.gov (United States)

2001-06-25

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

Analysis of possible fuel cycles

International Nuclear Information System (INIS)

Boehm, H.; Kessler, G.; Engelmann, P.; Maerkl, H.; Stoll, W.

1978-01-01

A brief survey is presented of the most important fuel cycles. A rough analysis of fuel cycles is attempted under the aspects of proliferation, status of technical feasibility, resource conservation and waste management and the most important criteria for such an analysis are discussed. Among the multitude of potential combinations of fuel cycles and types of reactors only a few have reached a level of technical feasibility which would make them eligible for commercial implementation within the next decade. However, if, for instance, the higher proliferation resistance of a specific fuel cycle is to be utilized to diminish the worldwide proliferation hazard, that cycle would first of all have to be introduced on an industrial scale as quickly as possible. The analysis shows that the reduction of the bazard of worldwide proliferation will continue to be the objective primarily of international agreements and measures taken in the political realm. (orig.) [de

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.

Description Fuel Cycle Spanish. Technical Visits

International Nuclear Information System (INIS)

Ochoa Valero, R.; Vinuesa Carretero, A.

2014-01-01

The nuclear fuel cycle includes all processes and operations from the mining of uranium to the management of radioactive waste generated. These processes include the manufacture of nuclear fuel, the operation of the plants and the storage of radioactive waste in the corresponding temporary stores. (Author)

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).

Imagining Technicities

DEFF Research Database (Denmark)

Liboriussen, Bjarke; Plesner, Ursula

2011-01-01

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

Development of TRU transmuters for optimization of the global fuel cycle. Final Report for the NERI Project

International Nuclear Information System (INIS)

Lee, John C.

2009-01-01

This final report summarizes the research activities during the entire performance period of the NERI grant, including the extra 9 months granted under a no-cost time extension. Building up on the 14 quarterly reports submitted through October 2008, we present here an overview of the research accomplishments under the five tasks originally proposed in July 2004, together with citations for publications resulting from the project. The AFCI-NERI project provided excellent support for two undergraduate and 10 graduates students at the University of Michigan during a period of three years and nine months. Significant developments were achieved in three areas: (1) Efficient deterministic fuel cycle optimization algorithms both for PWR and SFR configurations, (2) Efficient search algorithm for PWR equilibrium cycles, and (3) Simplified Excel-based script for dynamic fuel cycle analysis of diverse cycles. The project resulted in a total of 8 conference papers and three journal papers, including two that will be submitted shortly. Three pending publications are attached to the report

Thorium cycles and proliferation

International Nuclear Information System (INIS)

Lovins, A.B.

1979-01-01

This paper analyzes several prevalent misconceptions about nuclear fuel cycles that breed fissile uranium-233 from thorium. Its main conclusions are: U-233, despite the gamma radioactivity of associated isotopes, is a rather attractive material for making fission bombs, and is a credible material for subnational as well as national groups to use for this purpose; (2) pure thorium cycles, which in effect merely substitute U-233 for Pu, would take many decades and much U to establish, and offer no significant safeguards advantage over Pu, cycles; (3) denatured Th-U cycles, which dilute the U-233 with inert U-238 to a level not directly usable in bombs, are not an effective safeguard even against subnational bomb-making; (4) several other features of mixed Th-U cycles are rather unattractive from a safeguards point of view; (5) thus, Th cycles of any kind are not a technical fix for proliferation (national or subnational) and, though probably more safeguardable than Pu cycles, are less so than once-through U cycles that entail no reprocessing; (6) while thorium cycles have some potential technical advantages, including flexibility, they cannot provide major savings in nuclear fuel resources compared to simpler ways of saving neutrons and U; and (7) while advocates of nuclear power may find Th cycles worth exploring, such cycles do not differ fundamentally from U cycles in any of the respects--including safeguards and fuel resources--that are relevant to the broader nuclear debate, and should not be euphorically embraced as if they did

DUPIC fuel cycle economics assessment (1)

International Nuclear Information System (INIS)

Choi, H. B.; Roh, G. H.; Kim, D. H.

1999-04-01

This is a state-of-art report that describes the current status of the DUPIC fuel cycle economics analysis conducted by the DUPIC fuel compatibility assessment group of the DUPIC fuel development project. For the DUPIC fuel cycle economics analysis, the DUPIC fuel compatibility assessment group has organized the 1st technical meeting composed of 8 domestic specialists from government, academy, industry, etc. and a foreign specialist of hot-cell design from TRI on July 16, 1998. This report contains the presentation material of the 1st technical meeting, published date used for the economics analysis and opinions of participants, which could be utilized for further DUPIC fuel cycle and back-end fuel cycle economics analyses. (author). 11 refs., 7 charts

Fast breeder fuel cycle

International Nuclear Information System (INIS)

1978-09-01

Basic elements of the ex-reactor part of the fuel cycle (reprocessing, fabrication, waste handling and transportation) are described. Possible technical and proliferation measures are evaluated, including current methods of accountability, surveillance and protection. The reference oxide based cycle and advanced cycles based on carbide and metallic fuels are considered utilizing conventional processes; advanced nonaqueous reprocessing is also considered. This contribution provides a comprehensive data base for evaluation of proliferation risks

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

International Nuclear Information System (INIS)

Vierow, Karen; Aldemir, Tunc

2009-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Vierow, Karen; Aldemir, Tunc

2009-09-10

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

Life cycle assessment of geological repositories for the final disposal of spent fuel in Finland and Sweden

International Nuclear Information System (INIS)

Puhrer, A.; Bauer, C.

2014-01-01

This paper presents a Life Cycle Assessment (LCA) of the geological repositories for the final disposal of spent nuclear fuel in Finland and Sweden. A separate LCA has been performed for the geological spent fuel repository in each country and the results have been compared. A further benchmark comparison has been made with the LCA of the Swiss geological repository for high-level waste and spent fuel. The life cycle inventory (LCI) product system boundaries include the spent fuel repository and encapsulation facility in each country. All materials, processes, consumed utilities and transport associated with the construction, operation and closure of the repositories for spent fuel are included in the LCI. The life cycle impact assessment (LCIA) is performed using two methods: IPCC 2007 Climate Change and ReCiPe. These assessment methods return results pertaining to global warming potential (GWP) as well as a number of environmental impact categories such as human toxicity and natural land transformation. Results indicate that the use of copper for disposal canister fabrication and bentonite for repository backfilling are the causes for most of the environmental impact of the spent fuel repositories in Finland and Sweden. Alternate, less bentonite-intensive backfilling scenarios may mitigate this impact. While the Swiss bentonite consumption is lower and no copper is used for canister fabrication, the Swiss electricity and fuel consumption associated with final disposal of high-level waste and spent fuel is significantly higher than in Finland or Sweden. Approximately 1 g CO 2 -eq is emitted due to the final disposal of spent fuel and HLW per kWh of nuclear generated electricity. This represents some 10% of the emissions due to the entire nuclear energy chain and is practically negligible in the context of GHG emissions of other energy technologies. (authors)

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…

Final Technical Report - Kotzebue Wind Power Project - Volume II

Energy Technology Data Exchange (ETDEWEB)

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

2007-10-31

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

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

1993-01-01

The nuclear fuel cycle covers the procurement and preparation of fuel for nuclear power reactors, its recovery and recycling after use and the safe storage of all wastes generated through these operations. The facilities associated with these activities have an extensive and well documented safety record accumulated over the past 40 years by technical experts and safety authorities. This report constitutes an up-to-date analysis of the safety of the nuclear fuel cycle, based on the available experience in OECD countries. It addresses the technical aspects of fuel cycle operations, provides information on operating practices and looks ahead to future activities

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Resasco, Daniel [Univ. of Oklahoma, Norman, OK (United States). School of Chemical, Biological and Materials Engineering; Lobban, Lance [Univ. of Oklahoma, Norman, OK (United States); Crossley, Steven [Univ. of Oklahoma, Norman, OK (United States); Khanna, Vikas [Univ. of Pittsburgh, PA (United States); Maravelias, Christos [Univ. of Wisconsin, Madison, WI (United States); Petkovic, Lucia [Idaho National Lab. (INL), Idaho Falls, ID (United States); Duong, Nhung [Univ. of Oklahoma, Norman, OK (United States)

2018-01-24

The goal was to develop a biomass conversion process that optimizes fractionation and conversion to maximize Carbon efficiency and Hydrogen consumption to obtain drop-in fuels. Selective fractionation of raw biomass was obtained via multi-stage thermal fractionation to produce different streams that are enriched in a particular chemical family (acids, furanics or phenolics). These streams were later catalytically upgraded in both liquid and vapor phase to perform C-C bond formation and hydrodeoxygenation. Among various upgrading strategies investigated we have identified an effective path in which cyclopentanone is a crucial intermediate that can be derived from furfural and other furanics obtained in high concentrations from this thermal staged process. Cyclopentanone is a very versatile molecule, which can couple with itself to product high quality jet-fuel, or couple with phenolic or furanics to create long chain molecules. These (mono-oxygenated) compounds in the correct molecular weight fuel range can be hydrotreated to direct drop-in fuels. Interestingly, we have found that the conversion of furfural to cyclopentanone is not affected by the presence of acetic acid, and, more interestingly, it is enhanced by the presence of water. These are very significant findings, since water and acetic acid are always present in all streams from the primary conversion stage. These results have allowed to complete detailed life-cycle assessment and techno-economic analysis that have been back-fed to the experimentalists to refine the catalyst selection and process operations with the objective of maximizing C efficiency at minimum H utilization. These combined investigations have opened the possibility of an economically and technologically effective process that could result in commercial fuels produced from renewable sources at a cost that might be competitive with fossil fuels.

The nuclear fuel cycle is complete

International Nuclear Information System (INIS)

Hildenbrand, G.

1984-01-01

The nuclear fuel cycle in the Federal Republic of Germany has a firm base. Its entry stages, natural uranium, conversion, enrichment, and fuel fabrication, have not only been put on solid grounds in terms of supplies, but have also attained a high degree of technical maturity and a high quality level. Further efforts are being devoted to cost reductions. Especially higher burnups and the recycling of plutonium in the form of MOX fuel assemblies in light water reactors must be mentioned under this heading. In the field of back end fuel cycle steps, the important sector of interim storage has now found a practical solution, which is also fully sufficient with respect to capacity. The project of a German reprocessing plant has now entered its decisive stage with the filling of the licensing applications and the awarding of the planning contracts. The study on alternative waste management techniques entitled ''Direct Final Storage'' is about to be concluded, and a work on the exploration and development of a repository proceeds on schedule. (orig.) [de

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

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.

Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

Pakrasi, Himadri B. [Washington Univ., St. Louis, MO (United States)

2015-01-29

The potential for developing commercially viable microbial H₂-production systems as a renewable source of biofuel has been limited by the need for an anaerobic environment to enable photobiological H₂-production in capable bacterial and algal species. In this project, we have shown that the cyanobacterium Cyanothece sp. ATCC 51142 has the capacity for highly efficient H₂-production under natural aerobic conditions. The marine cyanobacterium Cyanothece sp. ATCC 51142 has a diurnal metabolic cycle; photosynthesis and carbon fixation occur during daylight hours and then at night, high rates of respiration create a suboxic intracellular environment that enables O₂-sensitive processes to occur, including N2-fixation and H₂-production. We developed a two-stage approach to monitor H₂-production by Cyanothece 51142. In the first stage, we grew the bacteria aerobically in an alternating 12 hour light/dark cycle. A second ‘incubation’ stage was then carried out in which we took cells from the end of a 12 hour light growth period and incubated them in air-tight vials for a further 12 hours under continuous illumination. Analysis of the headspace in the vial revealed high specific rates of H₂-production (>150 μmol of H₂ per mg chlorophyll per hour) during this incubation period. Furthermore, the rate of H₂-production could be enhanced by growing the cells in the presence of high levels of CO₂ or glycerol. We also confirmed that H₂-production was mediated by the nitrogenase system found in these Cyanothece cells. Interestingly, in the absence of molecular N₂, nitrogenase systems channel all available electrons towards H₂-production. Accordingly, when we incubated glycerol-supplemented Cyanothece 51142 cells in the absence of N₂, the rate of H₂-production increased up to 467 μmol of H₂ per mg

Final Technical Report for Award # ER64999

Energy Technology Data Exchange (ETDEWEB)

Metcalf, William W. [University of Illinois

2014-10-08

This report provides a summary of activities for Award # ER64999, a Genomes to Life Project funded by the Office of Science, Basic Energy Research. The project was entitled "Methanogenic archaea and the global carbon cycle: a systems biology approach to the study of Methanosarcina species". The long-term goal of this multi-investigator project was the creation of integrated, multiscale models that accurately and quantitatively predict the role of Methanosarcina species in the global carbon cycle under dynamic environmental conditions. To achieve these goals we pursed four specific aims: (1) genome sequencing of numerous members of the Order Methanosarcinales, (2) identification of genomic sources of phenotypic variation through in silico comparative genomics, (3) elucidation of the transcriptional networks of two Methanosarcina species, and (4) development of comprehensive metabolic network models for characterized strains to address the question of how metabolic models scale with genetic distance.

UK: Technical data for waste incineration background for modelling of product-specific emissions in a life cycle assessment context

DEFF Research Database (Denmark)

Hauschild, Michael Zwicky

and possible recycling hereof. The assessment is based on an inventory of inputs and outputs (resource/material consumption and generation of energy and emissions) for all the processes that occur as part of the product life-cycle. A model is developed to estimate the inputs and outputs associated...... and output of emissions to the environment caused by the incineration. The work has been performed as part of the EUREKA project EUROENVIRON 1296: LCAGAPS, sponsored by the Danish Agency for Industry and Trade. This report presents a compilation of technical data on waste incineration that serve...

Case study of an organic Rankine cycle applied for excess heat recovery: Technical, economic and policy matters

International Nuclear Information System (INIS)

Lemmens, Sanne; Lecompte, Steven

2017-01-01

Highlights: • Case study of an organic Rankine cycle for heat recovery from an industrial kiln. • The costs and financial feasibility of the system are discussed in detail. • The cost structure is most defined by the capital costs, annual costs are limited. • The system is financially feasible, but subsidies remain important. • The results are most sensitive to changes in load hours and electricity price. - Abstract: Many industrial processes inevitably produce excess heat as by-product. Recovering this heat is a matter of waste management and provides opportunities to improve the energy use efficiency. The excess heat can be used for heating purposes (e.g., in processes, or delivered to district heating systems or buildings) or to generate electricity. An increasingly applied technology for industrial excess heat recovery is the organic Rankine cycle (ORC), suitable to recover low-grade heat from 90 °C onwards. Although ORCs are studied intensively, few studies have examined the economics of commissioned ORC systems. This paper investigates a 375 kW_g_r_o_s_s ORC system employed for flue gas heat recovery from an industrial kiln in Flanders, Belgium. The purpose of the study is twofold: providing insight into a practical ORC case; and evaluating the financial feasibility while taking the specific policy circumstances into account. The financial appraisal takes account of the specific technical setup, the diverse costs of the system, the external economic parameters, and the policy circumstances in Europe, Belgium and Flanders. A sensitivity analysis illustrates the influence of each parameter on the results. The analysis demonstrates the dominance of the investment costs (4217 €_2_0_1_3/kW_g_r_o_s_s) in the expenses. Under the valid conditions the investment has a positive financial return, but the financial support from the government is indispensable. Finally, the sensitivity analysis reveals the importance of attaining sufficient load hours and the

Fuel cycle problems in fusion reactors

International Nuclear Information System (INIS)

Hickman, R.G.

1976-01-01

Fuel cycle problems of fusion reactors evolve around the breeding, recovery, containment, and recycling of tritium. These processes are described, and their implications and alternatives are discussed. Technically, fuel cycle problems are solvable; economically, their feasibility is not yet known

Report of Nuclear Fuel Cycle Subcommittee

International Nuclear Information System (INIS)

1982-01-01

In order to secure stable energy supply over a long period of time, the development and utilization of atomic energy have been actively promoted as the substitute energy for petroleum. Accordingly, the establishment of nuclear fuel cycle is indispensable to support this policy, and efforts have been exerted to promote the technical development and to put it in practical use. The Tokai reprocessing plant has been in operation since the beginning of 1981, and the pilot plant for uranium enrichment is about to start the full scale operation. Considering the progress in the refining and conversion techniques, plutonium fuel fabrication and son on, the prospect to technically establish the nuclear fuel cycle in Japan has been bright. The important problem for the future is to put these techniques in practical use economically. The main point of technical development hereafter is the enlargement and rationalization of the techniques, and the cooperation of the government and the people, and the smooth transfer of the technical development results in public corporations to private organization are necessary. The important problems for establishing the nuclear fuel cycle, the securing of enriched uranium, the reprocessing of spent fuel, unused resources, and the problems related to industrialization, location and fuel storing are reported. (Kako, I.)

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.

Part 6. Internationalization and collocation of FBR fuel cycle facilities

International Nuclear Information System (INIS)

Stevenson, M.G.; Abramson, P.B.; LeSage, L.G.

1980-01-01

This report examines some of the non-proliferation, technical, and institutional aspects of internationalization and/or collocation of major facilities of the Fast Breeder Reactor (FBR) fuel cycle. The national incentives and disincentives for establishment of FBR Fuel Cycle Centers are enumerated. The technical, legal, and administrative considerations in determining the feasibility of FBR Fuel Cycle Centers are addressed by making comparisons with Light Water Reactor (LWR) centers which have been studied in detail by the IAEA and UNSRC

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

International Nuclear Information System (INIS)

Till, C.E.; Chang, Y.I.

1993-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

Energy Technology Data Exchange (ETDEWEB)

Till, C.E.; Chang, Y.I.

1993-03-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions.

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

Energy Technology Data Exchange (ETDEWEB)

Till, C.E.; Chang, Y.I.

1993-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions.

Nuclear fuel cycle, nuclear fuel makes the rounds: choosing a closed fuel cycle, nuclear fuel cycle processes, front-end of the fuel cycle: from crude ore to enriched uranium, back-end of the fuel cycle: the second life of nuclear fuel, and tomorrow: multiple recycling while generating increasingly less waste

International Nuclear Information System (INIS)

Philippon, Patrick

2016-01-01

France has opted for a policy of processing and recycling spent fuel. This option has already been deployed commercially since the 1990's, but will reach its full potential with the fourth generation. The CEA developed the processes in use today, and is pursuing research to improve, extend, and adapt these technologies to tomorrow's challenges. France has opted for a 'closed cycle' to recycle the reusable materials in spent fuel (uranium and plutonium) and optimise ultimate waste management. France has opted for a 'closed' nuclear fuel cycle. Spent fuel is processed to recover the reusable materials: uranium and plutonium. The remaining components (fission products and minor actinides) are the ultimate waste. This info-graphic shows the main steps in the fuel cycle currently implemented commercially in France. From the mine to the reactor, a vast industrial system ensures the conversion of uranium contained in the ore to obtain uranium oxide (UOX) fuel pellets. Selective extraction, purification, enrichment - key scientific and technical challenges for the teams in the Nuclear Energy Division (DEN). The back-end stages of the fuel cycle for recycling the reusable materials in spent fuel and conditioning the final waste-forms have reached maturity. CEA teams are pursuing their research in support of industry to optimise these processes. Multi-recycle plutonium, make even better use of uranium resources and, over the longer term, explore the possibility of transmuting the most highly radioactive waste: these are the challenges facing future nuclear systems. (authors)

Proposal of a nuclear cycle research and development plan in Tokai works. The roadmap from LWR cycle to FBR cycle

International Nuclear Information System (INIS)

Nakamura, Hirofumi; Abe, Tomoyuki; Kashimura, Takuo; Nagai, Toshihisa; Maeda, Seichiro; Yamaguchi, Toshiya; Kuroki, Ryoichiro

2003-07-01

The Generation-II Project Task Force Team has investigated a research and development plan of a future nuclear fuel cycle in Tokai works for about three months from December 19, 2002. First we have discussed about the present condition of Japanese nuclear fuel cycle and have recognized it as the following. The relation of the technology between the LWR-cycle and the FBR-cycle is not clear. MOX Fuel Use in Light Water Reactors is important to establish technology of the FBR fuel cycle. Radioactive waste disposal issue is urgent. Next we have proposed the three basic policies on R and D plan of nuclear fuel cycle in consideration of the F.S. on FBR-cycle. Establishment and advancement of 'the tough nuclear fuel cycle'. Early establishment of the FBR cycle technology to be able to supply energy stably for long-term. Establishment of the radioactive waste treatment and disposal technology, and optimization of nuclear fuel cycle technology from the viewpoint of radioactive waste. And we have proposed the Japanese technical holder system to integrate all LWR and FBR cycle technology. (author)

Educational Focuses in Organisational Life Cycles.

Science.gov (United States)

Miller, Harry G.

1985-01-01

Presents four stages frequently associated with the stages of an organization's life cycle: experimentation, growth, maturity, and decline or stability. The author also demonstrates that the impact of employment and thus training related to organizational life cycles suggests a need for understanding the technical preparation required for…

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)

Head Start Impact Study. Technical Report

Science.gov (United States)

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

2010-01-01

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

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

International Nuclear Information System (INIS)

Till, C.E.; Chang, Y.I.

1991-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions. 10 refs

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

Energy Technology Data Exchange (ETDEWEB)

Till, C.E.; Chang, Y.I.

1991-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions. 10 refs.

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

International Nuclear Information System (INIS)

Till, C.E.; Chang, Y.I.

1991-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions. (author)

Alternative nuclear fuel cycles

International Nuclear Information System (INIS)

Till, C.E.

1979-01-01

This diffuse subject involves value judgments that are political as well as technical, and is best understood in that context. The four questions raised here, however, are mostly from the technical viewpoints: (1) what are alternative nuclear fuel cycles; (2) what generalizations are possible about their characteristics; (3) what are the major practical considerations; and (4) what is the present situation and what can be said about the outlook for the future

International Real Business Cycles

OpenAIRE

Mario J. Crucini

2006-01-01

This paper is a non-technical review of research developments in the international real business cycle literature. International business cycle facts are summarize with particular attention to the sources of output variance from the expenditure side of the NIPA and the production side, using a familiar neoclassical production function. Theoretical developments focus on the how consumption smoothing and investment dynamics shape the current account; the search for sources and propagation mecha...

Future fuel cycle and reactor strategies

International Nuclear Information System (INIS)

Meneley, D.A.

1999-01-01

Within the framework of the 1997 IAEA Symposium 'Future Fuel Cycle and Reactor Strategies Adjusting to New Realities', Working Group No.3 produced a Key Issues paper addressing the title of the symposium. The scope of the Key Issues paper included those factors that are expected to remain or become important in the time period from 2015 to 2050, considering all facets of nuclear energy utilization from ore extraction to final disposal of waste products. The paper addressed the factors influencing the choice of reactor and fuel cycle. It then addressed the quantitatively largest category of reactor types expected to be important during the period; that is, thermal reactors burning uranium and plutonium fuel. The fast reactor then was discussed both as a stand-alone technology and as might be used in combination with thermal reactors. Thorium fuel use was discussed briefly. The present paper includes of a digest of the Key Issues Paper. Some comparisons arc made between the directions suggested in that paper and those indicated by the Abstracts of this Technical Committee Meeting- Recommendations are made for work which might be undertaken in the short and medium time frames, to ensure that fuel cycle technologies and processes established by the year 2050 will support the continuation of nuclear energy applications in the long term. (author)

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

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

Strategy on energy saving reconstruction of distribution networks based on life cycle cost

Science.gov (United States)

Chen, Xiaofei; Qiu, Zejing; Xu, Zhaoyang; Xiao, Chupeng

2017-08-01

Because the actual distribution network reconstruction project funds are often limited, the cost-benefit model and the decision-making method are crucial for distribution network energy saving reconstruction project. From the perspective of life cycle cost (LCC), firstly the research life cycle is determined for the energy saving reconstruction of distribution networks with multi-devices. Then, a new life cycle cost-benefit model for energy-saving reconstruction of distribution network is developed, in which the modification schemes include distribution transformers replacement, lines replacement and reactive power compensation. In the operation loss cost and maintenance cost area, the operation cost model considering the influence of load season characteristics and the maintenance cost segmental model of transformers are proposed. Finally, aiming at the highest energy saving profit per LCC, a decision-making method is developed while considering financial and technical constraints as well. The model and method are applied to a real distribution network reconstruction, and the results prove that the model and method are effective.

Analysis of factors affecting the implementation of back-end nuclear fuel cycle policy in Korea

International Nuclear Information System (INIS)

Choi, Yung Myung; Yang, Maeng Ho; Kim, Hyun Joon; Chung, Hwan Sam; Oh, Keun Bae; Lee, Byung OoK; Ko, Han Suk; Song, Ki Dong; Lee, Man Ki; Moon, Ki Hwan; Lee, Han Myung

1994-01-01

In this study, the back-end nuclear fuel cycle acceptability is surveyed and analyzed in the following three aspects. To begin with, the future political situation and energy-environmental issues are analyzed as part of the socio-economic aspect. Secondly, the domestic situation of nuclear industries and the fuel cycle policy of foreign countries are surveyed as the technical aspect. Finally, NPT, IAEA safeguards and nuclear export control regimes are analyzed as the institutional aspect. The unification period of South and North Korea also will greatly affect the implementation of back-end fuel cycle policy, and public attitudes will affect the acquisition of site, construction, and operation of nuclear facilities. An effort to release international restrictions on the back-end fuel cycle is also required to accelerate the implementation of the policy. In this regard, the back-end fuel cycle policy should be clear-cut to avoid misunderstanding with respect to nuclear proliferation. Importantly, agreements with foreign countries should be amended at a mutual equivalent level. (Author) 30 refs., 5 figs., 25 tabs

Analysis of factors affecting the implementation of back-end nuclear fuel cycle policy in Korea

Energy Technology Data Exchange (ETDEWEB)

Choi, Yung Myung; Yang, Maeng Ho; Kim, Hyun Joon; Chung, Hwan Sam; Oh, Keun Bae; Lee, Byung OoK; Ko, Han Suk; Song, Ki Dong; Lee, Man Ki; Moon, Ki Hwan; Lee, Han Myung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-01-01

In this study, the back-end nuclear fuel cycle acceptability is surveyed and analyzed in the following three aspects. To begin with, the future political situation and energy-environmental issues are analyzed as part of the socio-economic aspect. Secondly, the domestic situation of nuclear industries and the fuel cycle policy of foreign countries are surveyed as the technical aspect. Finally, NPT, IAEA safeguards and nuclear export control regimes are analyzed as the institutional aspect. The unification period of South and North Korea also will greatly affect the implementation of back-end fuel cycle policy, and public attitudes will affect the acquisition of site, construction, and operation of nuclear facilities. An effort to release international restrictions on the back-end fuel cycle is also required to accelerate the implementation of the policy. In this regard, the back-end fuel cycle policy should be clear-cut to avoid misunderstanding with respect to nuclear proliferation. Importantly, agreements with foreign countries should be amended at a mutual equivalent level. (Author) 30 refs., 5 figs., 25 tabs.

A parametric study, based on physical and economic aspects, of the in-pile fuel cycle of pressurized light water reactor cores

International Nuclear Information System (INIS)

Guillet, J.-L.

1978-01-01

A method of determining the first core of a P.W.R. reactor was developed. This method is simple, inexpensive and takes the form of general laws expressing the effect of an enrichment variation from one batch to an other on the cycle characteristics (cycle length, end-of-cycle burn-up). These considerations are based upon an economic study which gives an idea of the financial consequences on the technical solution finally adopted. The parameters considered are the fuel cycle cost and the fuel investment cost. The computing methods used are based on a notion of purely theoretical core reactivity control which keeps stationary the power distributions during the cycle. A poisoned configuration involving burnable poisons, worked out on a particular case on the basis of this optimum control approach, has led to power distributions more uniform during the cycle and an appreciable limitation of the respective power peaks [fr

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

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.

Role of radiologists in CAD life-cycle

Energy Technology Data Exchange (ETDEWEB)

Pietka, Ewa, E-mail: ewa.pietka@polsl.pl [Silesian University of Technology, Faculty of Automatic Control, Electronics and Computer Science, ul. Akademicka 16, 44-100 Gliwice (Poland); Kawa, Jacek, E-mail: jacek.kawa@polsl.pl [Silesian University of Technology, Faculty of Automatic Control, Electronics and Computer Science, ul. Akademicka 16, 44-100 Gliwice (Poland); Spinczyk, Dominik, E-mail: dominik.spinczyk@polsl.pl [Silesian University of Technology, Faculty of Automatic Control, Electronics and Computer Science, ul. Akademicka 16, 44-100 Gliwice (Poland); Badura, Pawel, E-mail: pawel.badura@polsl.pl [Silesian University of Technology, Faculty of Automatic Control, Electronics and Computer Science, ul. Akademicka 16, 44-100 Gliwice (Poland); Wieclawek, Wojciech, E-mail: wojciech.wieclawek@polsl.pl [Silesian University of Technology, Faculty of Automatic Control, Electronics and Computer Science, ul. Akademicka 16, 44-100 Gliwice (Poland); Czajkowska, Joanna, E-mail: joanna.czajkowska@polsl.pl [Silesian University of Technology, Faculty of Automatic Control, Electronics and Computer Science, ul. Akademicka 16, 44-100 Gliwice (Poland); Rudzki, Marcin, E-mail: marcin.rudzki@polsl.pl [Silesian University of Technology, Faculty of Automatic Control, Electronics and Computer Science, ul. Akademicka 16, 44-100 Gliwice (Poland)

2011-05-15

A modern CAD (computer-aided diagnosis) system development involves a multidisciplinary team whose members are experts in medical and technical fields. This study indicates the activities of medical experts at various stages of the CAD design, testing, and implementation. Those stages include a medical analysis of the diagnostic problem, data collection, image analysis, evaluation, and clinical verification. At each stage the physicians knowledge and experience are indispensable. The final implementation involves integration with the existing Picture Archiving and Communication System. The term CAD life-cycle describes an overall process of the design, testing, and implementation of a system that in its final form assists the radiologists in their daily clinical routine. Four CAD systems (applied to the bone age assessment, Multiple Sclerosis detection, lung nodule detection, and pneumothorax measurement) developed in our laboratory are given as examples of how consecutive stages are developed by the multidisciplinary team. Specific advantages of the CAD implementation that include the daily clinical routine as well as research and education activities are discussed.

Role of radiologists in CAD life-cycle

International Nuclear Information System (INIS)

Pietka, Ewa; Kawa, Jacek; Spinczyk, Dominik; Badura, Pawel; Wieclawek, Wojciech; Czajkowska, Joanna; Rudzki, Marcin

2011-01-01

A modern CAD (computer-aided diagnosis) system development involves a multidisciplinary team whose members are experts in medical and technical fields. This study indicates the activities of medical experts at various stages of the CAD design, testing, and implementation. Those stages include a medical analysis of the diagnostic problem, data collection, image analysis, evaluation, and clinical verification. At each stage the physicians knowledge and experience are indispensable. The final implementation involves integration with the existing Picture Archiving and Communication System. The term CAD life-cycle describes an overall process of the design, testing, and implementation of a system that in its final form assists the radiologists in their daily clinical routine. Four CAD systems (applied to the bone age assessment, Multiple Sclerosis detection, lung nodule detection, and pneumothorax measurement) developed in our laboratory are given as examples of how consecutive stages are developed by the multidisciplinary team. Specific advantages of the CAD implementation that include the daily clinical routine as well as research and education activities are discussed.

Aspects of the fast reactors fuel cycle

International Nuclear Information System (INIS)

Zouain, D.M.

1982-06-01

The fuel cycle for fast reactors, is analysed, regarding the technical aspects of the developing of the reprocessing stages and the fuel fabrication. The environmental impact of LMFBRs and the waste management of this cycle are studied. The economic aspects of the fuel cycle, are studied too. Some coments about the Brazilian fast reactors programs are done. (E.G.) [pt

GPHS-RTGs in support of the Cassini RTG Program. Addendum to the final technical report, May 1--December 31, 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

This Addendum to the Cassini GPHS-RTG Program Final Technical Progress Report describes activities performed during the period 1 May 1998 through 31 December 1998, including effort reflecting contract modification M058. These activities include Earth Gravity Assist (EGA) reentry and related analyses which are detailed in Part A, and effort related to the installation of CAGO equipment within Lockheed Martin`s Building 100 facility in Valley Forge, PA, which is detailed in Part B.

GPHS-RTGs in support of the Cassini RTG Program. Addendum to the final technical report, May 1-December 31, 1998

International Nuclear Information System (INIS)

1998-12-01

This Addendum to the Cassini GPHS-RTG Program Final Technical Progress Report describes activities performed during the period 1 May 1998 through 31 December 1998, including effort reflecting contract modification M058. These activities include Earth Gravity Assist (EGA) reentry and related analyses which are detailed in Part A, and effort related to the installation of CAGO equipment within Lockheed Martin's Building 100 facility in Valley Forge, PA, which is detailed in Part B

Driving and engine cycles

CERN Document Server

Giakoumis, Evangelos G

2017-01-01

This book presents in detail the most important driving and engine cycles used for the certification and testing of new vehicles and engines around the world. It covers chassis and engine-dynamometer cycles for passenger cars, light-duty vans, heavy-duty engines, non-road engines and motorcycles, offering detailed historical information and critical review. The book also provides detailed examples from SI and diesel engines and vehicles operating during various cycles, with a focus on how the engine behaves during transients and how this is reflected in emitted pollutants, CO2 and after-treatment systems operation. It describes the measurement methods for the testing of new vehicles and essential information on the procedure for creating a driving cycle. Lastly, it presents detailed technical specifications on the most important chassis-dynamometer cycles around the world, together with a direct comparison of those cycles.

Alternative ORC bottoming cycles FOR combined cycle power plants

International Nuclear Information System (INIS)

Chacartegui, R.; Sanchez, D.; Munoz, J.M.; Sanchez, T.

2009-01-01

In this work, low temperature Organic Rankine Cycles are studied as bottoming cycle in medium and large scale combined cycle power plants. The analysis aims to show the interest of using these alternative cycles with high efficiency heavy duty gas turbines, for example recuperative gas turbines with lower gas turbine exhaust temperatures than in conventional combined cycle gas turbines. The following organic fluids have been considered: R113, R245, isobutene, toluene, cyclohexane and isopentane. Competitive results have been obtained for toluene and cyclohexane ORC combined cycles, with reasonably high global efficiencies. The paper is structured in four main parts. A review of combined cycle and ORC cycle technologies is presented, followed by a thermodynamic analysis of combined cycles with commercial gas turbines and ORC low temperature bottoming cycles. Then, a parametric optimization of an ORC combined cycle plant is performed in order to achieve a better integration between these two technologies. Finally, some economic considerations related to the use of ORC in combined cycles are discussed.

Gasification and combined cycles: Present situation and future prospects

International Nuclear Information System (INIS)

Brustia, G.F.; Bressan, L.; Domenichini, R.

1992-01-01

The gasification of coal and/or residual fuels from refineries together with the use of combined cycle power generation systems represents a technically and economically feasible method for the conversion of poor quality fossil fuels into electric power. The conversion is accomplished with maximum respect for the severest environmental normatives. In addition, foreseen technical improvements for components and plant systems are expected to heighten the marketing potential of gasification/combined cycle power plants. After Italy's moratorium on nuclear energy, the passing eras of conventional fossil fuel and then combined cycle power plants, the need for highly competitive industrial production technologies and the urgency of nation-wide energy conservation appear to be ushering in the new era of gasification with combined cycles

Optimization analysis of the nuclear fuel cycle transition to the last core

International Nuclear Information System (INIS)

Rebollo, L.; Blanco, J.

2001-01-01

The Zorita NPP was the first Spanish commercial nuclear reactor connected to the grid. It is a 160 MW one loop PWR, Westinghouse design, owned by UFG, in operation since 1968. The configuration of the reactor core is based on 69 fuel elements type 14 x 14, the standard reload of the present equilibrium cycle being based on 16 fuel elements with 3.6% enrichment in 235 U. In order to properly plan the nuclear fuel management of the transition cycles to its end of life, presently foreseen by 2008, an based on the non-reprocessing option required by the policy of the Spanish Administration, a technical-economical optimization analysis has been performed. As a result, a fuel management strategy has been defined looking for getting simultaneously the minimum integral fuel cost of the transition from the present equilibrium cycle to the last core, as well as the minimum residual worth of the fuel remaining in the core after the final outage. Based on the ''lessons learned'' derived from the study, the time margin for the decision making has been determined, and a planning of the nuclear fuel supply for the transition reloads, specifying both the number of fuel elements and their enrichment in 235 U, as been prepared. Finally, based on the calculated economical worth of the partially burned fuel of the last core, after the end of its operation cycle, a financial cover for yearly compensation from now on of the foreseen final lost has been elaborated. Most of the conceptual conclusions obtained are applicable to the other commercial nuclear reactors in operation owned by UFG, so that they are understood to be of general interest and broad application to commercial PWR. (author)

Environmental implications of thorium use in selected nuclear fuel cycles. Final

International Nuclear Information System (INIS)

Buckley, D.W.; Simmons, G.L.; Ziskind, R.A.

1978-01-01

The objective of this study was to assess the environmental implications of the nuclear fuel cycle associated with the highly enriched uranium concept of the High Temperature Gas Cooled Reactor. Model fuel cycles were constructed for the HTGR and a reference light water reactor (LWR) cycle. Mass flows were developed, control technology cases proposed and costed, effluents determined, and population doses calculated. Emphasis was given to the intercomparison of the fuel cycles to delineate areas which show pronounced departure. The dose commitment received by the population both within and outside a radius of 50 miles of each facility was determined. The 100 year population dose commitments due to a single year's plant operation was selected to facilitate intercomparison among fuel cycle components. No account was taken for long term waste sources associated with the fuel cycle such as mill tailing piles or terminal waste storage (study groundrule). The resource utilization and radionuclide activity of various fuel cycle options for using thorium in a Pressurized Water Reactor were studied. These data were contrasted with similar results obtained for a uranium fuel PWR

Dependence of cycle optimal configuration for closed gas turbines on thermodynamic properties of working fluids

International Nuclear Information System (INIS)

Andryushchenko, A.I.; Dubinin, A.B.; Krylov, E.E.

1988-01-01

The problem of choice of working fluids for NPP closed gas turbines (CGT) is discussed. Thermostable in the working temperature range, chemically inert relatively to structural materials, fire- and explosion - proof substances, radiation-resistant and having satisfactory neutron-physical characteristics are used as the working fluids. Final choice of a gas as a working fluid is exercised based on technical and economic comparison of different variants at optimum thermodynamic cycle and parameters for each gas. The character and degree of the effect of thermodynamic properties of gases on configuration of reference cycles of regenerative CGT are determined. It is established that efficiency and optimum parameters in nodal points of the reference cycle are specified by the degree of removing the compression processes from the critical point. Practical importance of the obtained results presupposes the possibility of rapid estimation of the efficiency of using a gas without multiparametric optimization

Computer-simulation movie of ionospheric electric fields and currents for a magnetospheric substorm life cycle. Technical note

International Nuclear Information System (INIS)

Kamide, Y.; Matsushita, S.

1980-07-01

Numerical solution of the current conservation equation gives the distributions of electric fields and currents in the global ionosphere produced by the field-aligned currents. By altering ionospheric conductivity distributions as well as the field-aligned current densities and configurations to simulate a magnetospheric substorm life cycle, which is assumed to last for five hours, various patterns of electric fields and currents are computed for every 30-second interval in the life cycle. The simulated results are compiled in the form of a color movie, where variations of electric equi-potential curves are the first sequence, electric current-vector changes are the second, and fluctuations of the electric current system are the third. The movie compresses real time by a factor of 1/180, taking 1.7 minutes of running time for one sequence. One of the most striking features of this simulation is the clear demonstration of rapid and large scale interactions between the auroral zone and middle-low latitudes during the substorm sequences. This technical note provides an outline of the numerical scheme and world-wide contour maps of the electric potential, ionospheric current vectors, and the equivalent ionospheric current system at 5-minute intervals as an aid in viewing the movie and to further detailed study of the 'model' substorms

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.

Final report on a study of coherence in acceptability criteria for the technical aspects of risks associated with potentially hazardous installations

International Nuclear Information System (INIS)

Chicken, J.C.

1988-01-01

This report describes the results of the study that was made, under Contract No ECI-1390-B7221-85D, for the European Atomic Energy Community. The aim of the study was to examine and assess the feasibility of developing coherent and uniform criteria for judging the acceptability of the technical aspects of the risks associated with potentially hazardous installations. The report is arranged in five main parts. First the nature of hazardous installations is considered and this provides the basis for examination of the currently-used technical risk acceptability criteria. Next, the possible forms of criteria are explored and then universally consistent partial and overall technical risk acceptability criteria are proposed. Following this the implications of using the criteria proposed at the design, regulatory and operating levels are examined. Then, by testing the criteria against some real decisions, the practical problems of using the proposed criteria are explored. This leads to consideration of possible alternatives to the proposed criteria. Finally the conclusions that appear to be justified are summarized and the need for further work is identified

Technical Publications as Indicators for Nuclear Fuel Cycle Declarable Activities

International Nuclear Information System (INIS)

Schuler, R.; El Gebaly, A.; Feldman, Y.; Gagne, D.; Schot, P.-M.; Ferguson, M.

2015-01-01

The Department of Safeguards aims to provide credible assurances to the international community that States are fulfiling their safeguards obligations in that all nuclear material remains in peaceful use. It does so in part by developing and implementing methodologies for early detection of undeclared activities or misuse of nuclear material or technology, based on large and diverse sources of information. Analyzing scientific, technical and patent information allows analysts in the Department to understand the technology available to a State, to forecast possible technical developments, to map collaborative research activities within and across States, and compare that information with declarations received by the State for completeness and correctness. Furthermore, with regard to patent information, scientists or companies want to make sure their intellectual property is protected; accordingly, patents are frequently filed before the information is published elsewhere, making patent information also an early indicator of relevant activities. Dealing with such large information sources requires the use of an innovative methodology conducting analysis. The Department has recently begun to examine the efficacy of link analysis tools to help carry out its mission. Using the link analysis platform Palantir, the authors conducted several case studies with the aim of deriving sound analytical results from large amounts of technical information within a reasonable time frame. The authors used data sets of bibliographic references from the IAEA International Nuclear Information System (INIS),Web of Science, Science Direct and data on worldwide patents from the European Patent Office (EPO). Based on these case studies, the authors are developing methodologies for the efficient application of link analysis to scientific and technical information, thus strengthening the Department's information collection and analysis capabilities and the overall process of State

NetView technical research

Science.gov (United States)

1993-01-01

This is the Final Technical Report for the NetView Technical Research task. This report is prepared in accordance with Contract Data Requirements List (CDRL) item A002. NetView assistance was provided and details are presented under the following headings: NetView Management Systems (NMS) project tasks; WBAFB IBM 3090; WPAFB AMDAHL; WPAFB IBM 3084; Hill AFB; McClellan AFB AMDAHL; McClellan AFB IBM 3090; and Warner-Robins AFB.

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.

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).

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

Final technical report. A sodium-cycle based organism with improved membrane resistance aimed at increasing the efficiency of energy biotransformations

International Nuclear Information System (INIS)

Lewis, Kim

2001-01-01

The aim of the project was to express in E. coli components that would allow a formation of oxidative phosphorylation based on a sodium cycle. This would improve the resistance of cells to organic solvents, detergents and other toxins. The author cloned and expressed the nqr operon FR-om H. influenzae in E. coli. Experiments with membrane vesicles indicated the presence of the functional recombinant sodium pumping NADH dehydrogenase. A gene for a hybrid E. coli/P.modestum ATPase was constructed which will enable one to co-express a sodium ATPsynthase together with a sodium NADH dehydrogenase

The importance of independent research and evaluation in assessing nuclear fuel cycle and waste management facility safety

International Nuclear Information System (INIS)

Downing, Walter D.; Patrick, Wesley C.; Sagar, Budhi

2009-01-01

In 1987, the United States Nuclear Regulatory Commission (NRC) established at Southwest Research Institute (SwRI) a federally funded research and development center. Known as the Center for Nuclear Waste Regulatory Analyses (CNWRA), its overall mission is to provide NRC with an independent assessment capability on technical and regulatory issues related to a potential geologic repository for spent nuclear fuel and high-level radioactive waste, as well as interim storage and other nuclear fuel-cycle facilities. For more than 20 years, the CNWRA has supported NRC through an extensive pre-licensing period of establishing the framework of regulations and guidance documents, developing computer codes and other review tools, and conducting independent laboratory, field, and numerical analyses. In June 2008, the United States Department of Energy (DOE) submitted a license application and final environmental impact statement to NRC seeking authorization to construct the nation's first geologic repository at Yucca Mountain, Nevada. The CNWRA will assist NRC in conducting a detailed technical review to critically evaluate the DOE license application to assess whether the potential repository has been designed and can be constructed and operated to safely dispose spent nuclear fuel and high-level radioactive waste. NRC access to independent, unbiased, technical advice from the CNWRA is an important aspect of the evaluation process. This paper discusses why an independent perspective is important when dealing with nuclear fuel cycle and waste management issues. It addresses practical considerations such as avoiding conflicts of interest while at the same time maintaining a world-class research program in technical areas related to the nuclear fuel cycle. It also describes an innovative approach for providing CNWRA scientists and engineers a creative outlet for professional development through an internally funded research program that is focused on future nuclear waste

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

Technical study report on reprocessing systems. The report of the feasibility study on commercialized FR cycle systems (phase I)

International Nuclear Information System (INIS)

Tanaka, Hiroshi; Kawamura, Fumio; Kakehi, Isao

2001-04-01

As a part of the feasibility study (FS) on commercialized fast reactor (FR) cycle systems started on July 1999, the design studies and the technical assessments for various advanced reprocessing systems have been carried out. In this study, plant design for the advanced aqueous system and the three non-aqueous systems (oxide electrowinning method, metal electrorefining method, and fluoride volatility method) has been carried out, and each system has been evaluated mainly from the viewpoint of economics. The future R and D issues on the processes and systems have been also clarified. This report describes the results of the study for two years as final report of FS phase I. (1) The advanced aqueous system, based on the simplified PUREX process, has been shown to be much more economical than the conventional PUREX. The 200 tHM/y plant achieves the target of economics, but the 50 tHM/y plant can not achieve the target. (2) The promising alternative systems replaced for advanced aqueous are the supercritical fluid direct extraction method and amine extraction method from the economical viewpoint. The ion exchange method is promising as the process for minor actinide recovery. (3) For reprocessing MOX fuel, all non-aqueous plants with a capacity of 200 tHM/y achieve the economical target. For such a small capacity as 50 tHM/y, further rationalization of the process is required for the oxide electrowinning method and metal electrorefining method to attain the target, though they are more economical than the advanced aqueous system. (4) For metallic and nitride fuel reprocessing, a metal electrorefining system has been shown to be advantageous. (author)

Performance assessment of simple and modified cycle turboshaft gas turbines

Directory of Open Access Journals (Sweden)

Barinyima Nkoi

2013-06-01

Full Text Available This paper focuses on investigations encompassing comparative assessment of gas turbine cycle options. More specifically, investigation was carried out of technical performance of turboshaft engine cycles based on existing simple cycle (SC and its projected modified cycles for civil helicopter application. Technically, thermal efficiency, specific fuel consumption, and power output are of paramount importance to the overall performance of gas turbine engines. In course of carrying out this research, turbomatch software established at Cranfield University based on gas turbine theory was applied to conduct simulation of a simple cycle (baseline two-spool helicopter turboshaft engine model with free power turbine. Similarly, some modified gas turbine cycle configurations incorporating unconventional components, such as engine cycle with low pressure compressor (LPC zero-staged, recuperated engine cycle, and intercooled/recuperated (ICR engine cycle, were also simulated. In doing so, design point (DP and off-design point (OD performances of the engine models were established. The percentage changes in performance parameters of the modified cycle engines over the simple cycle were evaluated and it was found that to a large extent, the modified engine cycles with unconventional components exhibit better performances in terms of thermal efficiency and specific fuel consumption than the traditional simple cycle engine. This research made use of public domain open source references.

Final Report on Two-Stage Fast Spectrum Fuel Cycle Options

International Nuclear Information System (INIS)

Yang, Won Sik; Lin, C. S.; Hader, J. S.; Park, T. K.; Deng, P.; Yang, G.; Jung, Y. S.; Kim, T. K.; Stauff, N. E.

2016-01-01

This report presents the performance characteristics of two ''two-stage'' fast spectrum fuel cycle options proposed to enhance uranium resource utilization and to reduce nuclear waste generation. One is a two-stage fast spectrum fuel cycle option of continuous recycle of plutonium (Pu) in a fast reactor (FR) and subsequent burning of minor actinides (MAs) in an accelerator-driven system (ADS). The first stage is a sodium-cooled FR fuel cycle starting with low-enriched uranium (LEU) fuel; at the equilibrium cycle, the FR is operated using the recovered Pu and natural uranium without supporting LEU. Pu and uranium (U) are co-extracted from the discharged fuel and recycled in the first stage, and the recovered MAs are sent to the second stage. The second stage is a sodium-cooled ADS in which MAs are burned in an inert matrix fuel form. The discharged fuel of ADS is reprocessed, and all the recovered heavy metals (HMs) are recycled into the ADS. The other is a two-stage FR/ADS fuel cycle option with MA targets loaded in the FR. The recovered MAs are not directly sent to ADS, but partially incinerated in the FR in order to reduce the amount of MAs to be sent to the ADS. This is a heterogeneous recycling option of transuranic (TRU) elements

Final Report on Two-Stage Fast Spectrum Fuel Cycle Options

Energy Technology Data Exchange (ETDEWEB)

Yang, Won Sik [Purdue Univ., West Lafayette, IN (United States); Lin, C. S. [Purdue Univ., West Lafayette, IN (United States); Hader, J. S. [Purdue Univ., West Lafayette, IN (United States); Park, T. K. [Purdue Univ., West Lafayette, IN (United States); Deng, P. [Purdue Univ., West Lafayette, IN (United States); Yang, G. [Purdue Univ., West Lafayette, IN (United States); Jung, Y. S. [Purdue Univ., West Lafayette, IN (United States); Kim, T. K. [Argonne National Lab. (ANL), Argonne, IL (United States); Stauff, N. E. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-01-30

This report presents the performance characteristics of two “two-stage” fast spectrum fuel cycle options proposed to enhance uranium resource utilization and to reduce nuclear waste generation. One is a two-stage fast spectrum fuel cycle option of continuous recycle of plutonium (Pu) in a fast reactor (FR) and subsequent burning of minor actinides (MAs) in an accelerator-driven system (ADS). The first stage is a sodium-cooled FR fuel cycle starting with low-enriched uranium (LEU) fuel; at the equilibrium cycle, the FR is operated using the recovered Pu and natural uranium without supporting LEU. Pu and uranium (U) are co-extracted from the discharged fuel and recycled in the first stage, and the recovered MAs are sent to the second stage. The second stage is a sodium-cooled ADS in which MAs are burned in an inert matrix fuel form. The discharged fuel of ADS is reprocessed, and all the recovered heavy metals (HMs) are recycled into the ADS. The other is a two-stage FR/ADS fuel cycle option with MA targets loaded in the FR. The recovered MAs are not directly sent to ADS, but partially incinerated in the FR in order to reduce the amount of MAs to be sent to the ADS. This is a heterogeneous recycling option of transuranic (TRU) elements

Yucca Mountain Climate Technical Support Representative

International Nuclear Information System (INIS)

Sharpe, Saxon E

2007-01-01

The primary objective of Project Activity ORD-FY04-012, 'Yucca Mountain Climate Technical Support Representative', was to provide the Office of Civilian Radioactive Waste Management (OCRWM) with expertise on past, present, and future climate scenarios and to support the technical elements of the Yucca Mountain Project (YMP) climate program. The Climate Technical Support Representative was to explain, defend, and interpret the YMP climate program to the various audiences during Site Recommendation and License Application. This technical support representative was to support DOE management in the preparation and review of documents, and to participate in comment response for the Final Environmental Impact Statement, the Site Recommendation Hearings, the NRC Sufficiency Comments, and other forums as designated by DOE management. Because the activity was terminated 12 months early and experience a 27% reduction in budget, it was not possible to complete all components of the tasks as originally envisioned. Activities not completed include the qualification of climate datasets and the production of a qualified technical report. The following final report is an unqualified summary of the activities that were completed given the reduced time and funding

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

Burnup effect on nuclear fuel cycle cost using an equilibrium model

International Nuclear Information System (INIS)

Youn, S. R.; Kim, S. K.; Ko, W. I.

2014-01-01

The degree of fuel burnup is an important technical parameter to the nuclear fuel cycle, being sensitive and progressive to reduce the total volume of process flow materials and eventually cut the nuclear fuel cycle costs. This paper performed the sensitivity analysis of the total nuclear fuel cycle costs to changes in the technical parameter by varying the degree of burnups in each of the three nuclear fuel cycles using an equilibrium model. Important as burnup does, burnup effect was used among the cost drivers of fuel cycle, as the technical parameter. The fuel cycle options analyzed in this paper are three different fuel cycle options as follows: PWR-Once Through Cycle(PWR-OT), PWR-MOX Recycle, Pyro-SFR Recycle. These fuel cycles are most likely to be adopted in the foreseeable future. As a result of the sensitivity analysis on burnup effect of each three different nuclear fuel cycle costs, PWR-MOX turned out to be the most influenced by burnup changes. Next to PWR-MOX cycle, in the order of Pyro-SFR and PWR-OT cycle turned out to be influenced by the degree of burnup. In conclusion, the degree of burnup in the three nuclear fuel cycles can act as the controlling driver of nuclear fuel cycle costs due to a reduction in the volume of spent fuel leading better availability and capacity factors. However, the equilibrium model used in this paper has a limit that time-dependent material flow and cost calculation is impossible. Hence, comparative analysis of the results calculated by dynamic model hereafter and the calculation results using an equilibrium model should be proceed. Moving forward to the foreseeable future with increasing burnups, further studies regarding alternative material of high corrosion resistance fuel cladding for the overall

Life Cycle Assessments Applied to First Generation Biofuels Used in France. Final report; Analyses de Cycle de Vie appliquees aux biocarburants de premiere generation consommes en France. Rapport final

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

construction of a national calculation method parallel to that defined by the Commission. This work presents here a global consistency with the Directive, namely in term of allocation principle based on energy pro-rata, but was also performed in a finer, step by step detail level. The objective of the study is to realize the life cycle assessment of the current biofuel pathways (also called 'first generation') by applying the principles retained in the 2008 methodological guide. This work was performed with the technical support of industrial actors, technical institutes, research centers, and environmental associations. Integrating the European context and wishing to put the results in perspective, this study performs, in a second step, an analysis of the results obtained with other methodologies, including those from the Directive. This critical and constructive aspect emphasizes points of vigilance to keep in mind in the European discussions with regards to quantify biofuel sustainability

Fuel cycle and waste newsletter, Vol. 5, No. 1, April 2009

International Nuclear Information System (INIS)

2009-04-01

sponsored SAPIERR Project (Strategic Action Plan for Implementation of European Regional Repositories which leads to a practical regional repository initiative; on waste management in Ukraine (mainly design and construction of a safe confinement shelter for the destroyed Chernobyl NPP Unit 4 and the safe management of radioactive waste in the Exclusion Zone, as well as the remediation of the area); on the cooperation with RADON to establish a network of Regional centres for training in waste management; on the meeting of the Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWGNFCO); on the International Symposium on Uranium raw Material for the Nuclear Fuel Cycle. Finally recent publications and upcoming Meetings are listed

Technical diagnostics functioning machines and mechanisms

Science.gov (United States)

Kiselev, M. I.; Pronyakin, V. I.; Tulekbaeva, A. K.

2018-02-01

Article discusses the machines and mechanisms technical state monitoring problem. Approaches for estimating mechanical systems current technical state, defects detection and evaluation of mechanical elements degradation levels are considered. The paper analyzes the traditional methods offered in international and national standards, especially vibrodiagnostics. An advanced phase method is presented which is based on registration the kinematic parameters of the mechanism running cycle. The result of coupling the phase method and mathematical modeling is shown, and simulation comparison with the experimental data is presented.

Heavy water reactors on the denatured thorium cycles

International Nuclear Information System (INIS)

1978-05-01

This paper presents preliminary technical and economic data to INFCE on the denatured U-233/Thorium fuel cycle for use in early comparisons of alternate nuclear systems. The once-through uranium fuel cycle is discussed in a companion paper. In presenting this preliminary information at this time, it is recognized that there are several other denatured thorium fuel cycles of potential interest, such as the U-235/thorium cycle which could be implemented at an earlier date. Information on these alternate cycles is currently being developed, and will be provided to INFCE when available

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.

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.

``Turbo-KWK `99``. Combined-cycle power stations with gas turbines. Technical meeting; Turbo-KWK `99. Kraft-Waerme-Kopplung mit Gasturbinen. Fachtagung

Energy Technology Data Exchange (ETDEWEB)

1999-09-01

This conference report comprises 18 contributions on the technological success of gas turbines in power generation, e.g.: Maximum power generation efficiency of combined cycle systems, flexibility of power generation, reduction of air pollution, hot gas production for drying processes and environment-friendly cold generation in the pharmaceutical and printing industries. The final contribution presents an outlook to the future.

Development of the biosphere code BIOMOD: final report

International Nuclear Information System (INIS)

Kane, P.

1983-05-01

Final report to DoE on the development of the biosphere code BIOMOD. The work carried out under the contract is itemised. Reference is made to the six documents issued along with the final report. These consist of two technical notes issued as interim consultative documents, a user's guide and a programmer's guide to BIOMOD, a database description, program test document and a technical note entitled ''BIOMOD - preliminary findings''. (author)

Alternative fuel cycles

International Nuclear Information System (INIS)

Penn, W.J.

1979-05-01

Uranium resource utilization and economic considerations provide incentives to study alternative fuel cycles as future options to the PHWR natural uranium cycle. Preliminary studies to define the most favourable alternatives and their possible introduction dates are discussed. The important and uncertain components which influence option selection are reviewed, including nuclear capacity growth, uranium availability and demand, economic potential, and required technological developments. Finally, a summary of Ontario Hydro's program to further assess cycle selection and define development needs is given. (auth)

Study of Incoloy 800HT alloy tested by heat-cycling

International Nuclear Information System (INIS)

Velciu, L.; Meleg, T.; Pantiru, M.; Petrescu, D.; Voicu, F.

2016-01-01

This paper investigated Incoloy 800HT (UNS N08811) alloy after some heat-cycling tests. The study continues prior tests realized in INR Pitesti concerning utilization of some nickel-based alloys in the heat exchangers and steam generators construction. The thermal-cycling consist in a successive series of heating and cooling with some rates in a range temperature. Technical parameters of thermal cycling: 50 & 200 cycles, 25 °C/minute heating-cooling rate, temperature range 450-1000°C, and argon working medium. The analysis consisted in metallographic examination (microstructure), Vickers microhardness, and traction tests. The average grain size was determined by linear interception method (ASTM E-112). The micro hardness was calculated by the relationship of the device technical book. On the Strength-Deformation diagrams were obtained: tensile strength and elongation. The tested samples were compared with the ''as received'' material. The results showed a good metallographic and mechanical behaviour of Incoloy 800HT at these thermal-cycling tests. (authors)

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

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

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

FOREX trading strategy formation using technical analysis

OpenAIRE

Klimavičius, Domas

2010-01-01

FOREX technical analysis indicators, their characteristics and capabilities are researched in this final master thesis. The main goal of this thesis is to determine if technical analysis indicators can recognise patterns in price movements and if they can predict future price movement. The first part of the thesis presents with FOREX theoretical aspects, its characteristics and participants. In the second part of the thesis FOREX analysis tools are overviewed, focusing on technical analysis. ...

Final Technical Report for Year 5 Early Career Research Project "Viscosity and equation of state of hot and dense QCD matter"

Energy Technology Data Exchange (ETDEWEB)

Molnar, Denes [Purdue Univ., West Lafayette, IN (United States)

2016-05-25

The Section below summarizes research activities and achievements during the fifth (last) year of the PI’s Early Career Research Project (ECRP). Unlike the first four years of the project, the last year was not funded under the American Recovery and Reinvestment Act (ARRA). The ECRP advanced two main areas: i) radiative 3 ↔ 2 radiative transport, via development of a new computer code MPC/Grid that solves the Boltzmann transport equation in full 6+1D (3X+3V+time); and ii) application of relativistic hydrodynamics, via development of a self-consistent framework to convert viscous fluids to particles. In Year 5 we finalized thermalization studies with radiative gg ↔ ggg transport (Sec. 1.1.1) and used nonlinear covariant transport to assess the accuracy of fluid-to-particle conversion models (Sec. 1.1.2), calculated observables with self-consistent fluid-to-particle conversion from realistic viscous hydrodynamic evolution (Secs. 1.2.1 and 1.2.2), extended the covariant energy loss formulation to heavy quarks (Sec. 1.4.1) and studied energy loss in small systems (Sec. 1.4.2), and also investigated how much of the elliptic flow could have non-hydrodynamic origin (Sec 1.3). Years 1-4 of the ECRP were ARRA-funded and, therefore, they have their own report document ’Final Technical Report for Years 1-4 of the Early Career Research Project “Viscosity and equation of state of hot and dense QCD matter”’ (same award number DE-SC0004035). The PI’s group was also part of the DOE JET Topical Collaboration, a multi-institution project that overlapped in time significantly with the ECRP. Purdue achievements as part of the JET Top- ical Collaboration are in a separate report “Final Technical Report summarizing Purdue research activities as part of the DOE JET Topical Collaboration” (award DE-SC0004077).

Rankine bottoming cycle safety analysis. Final report

Energy Technology Data Exchange (ETDEWEB)

Lewandowski, G.A.

1980-02-01

Vector Engineering Inc. conducted a safety and hazards analysis of three Rankine Bottoming Cycle Systems in public utility applications: a Thermo Electron system using Fluorinal-85 (a mixture of 85 mole % trifluoroethanol and 15 mole % water) as the working fluid; a Sundstrand system using toluene as the working fluid; and a Mechanical Technology system using steam and Freon-II as the working fluids. The properties of the working fluids considered are flammability, toxicity, and degradation, and the risks to both plant workers and the community at large are analyzed.

75 FR 33682 - Export Administration Regulations; Technical Amendments

Science.gov (United States)

2010-06-15

...-01] RIN 0694-AE93 Export Administration Regulations; Technical Amendments AGENCY: Bureau of Industry... Bureau of Industry and Security (BIS) makes a technical amendment to the Export Administration... review of final decisions and orders issued in BIS export control administrative enforcement proceedings...

Health care fraud and abuse data collection program: technical revisions to Healthcare Integrity and Protection Data Bank data collection activities. Final rule.

Science.gov (United States)

2004-09-21

The rule finalizes technical changes to the Healthcare Integrity and Protection Data Bank (HIPDB) data collection reporting requirements by clarifying the types of personal numeric identifiers that may be reported to the data bank in connection with adverse actions. The rule clarifies that in lieu of a Social Security Number (SSN), an individual taxpayer identification number (ITIN) may be reported to the data bank when, in those limited situations, an individual does not have an SSN.

Strategies of operation cycles in BWR type reactors

International Nuclear Information System (INIS)

Molina, D.; Sendino, F.

1996-01-01

The article analyzes the operation cycles in BWR type reactors. The cycle size of operation is the consequence on the optimization process of the costs with the technical characteristics of nuclear fuel and the characteristics of demand and production. The authors analyze the cases of Garona NP and Cofrentes NP, both with BWR reactors. (Author)

Method and Result of Experiment for Support of Technical Solutions in the Field of Perfection of a Nuclear Fuel Cycle for Future PWR Reactors

International Nuclear Information System (INIS)

Ostrovskiy, V.; Kudryavtsev, E.; Tutnov, I.

2011-01-01

The paper presents the basics of approach of planning and carrying out of experiments to validate safety PWR reactors of the future when accepting technical solutions concerning using of improved fuel rods in fuel assembly. Basic principles and criteria used for the validation of technical solutions and developments in improving of nuclear fuel cycle of PWR reactors of the future are presented from the point of safety of future operation of modified fuel rods. We explore the questions of safety operation of PWR reactors with fuel assemblies, containing fuel rods with different length of fuel. The paper discusses the ways of solving of important tasks of critical facility experiments conducting for verification of new technical solutions in the sphere of PWR nuclear fuel cycle improvement on the base of international standards ISO 2000:9000 and functional safety recommendations of IEC (International Electromechanical Commission). New Federal laws of Russian Federation define the main principle for demands to NPP and any supplier of nuclear techniques. The principle is 'quantity indicators of risk should not exceed comprehensible social size of the established indicators of safety for any moment of operation of NPP'. On the other hand the second principle should be applied to extraction of the greatest benefit from operation of the equipment, systems or the NPP as whole: 'The long operation and full commercial use of resource and service properties of the equipment, systems and the NPP as a whole'. Realization of this principle assumes development and introduction of new technical solutions for a validation of guarantees of safety of the future operation of NPP or it separate components. Solving the practical problems of a validation of safety use of fuel rods with the increased length of a fuel column in fuel assembly in nuclear reactors of the future, we should choose new strategies and programs of verification experiments on the base of the analysis of guarantees

The back end of the nuclear fuel cycle: Technical and economic analysis-Part 2

International Nuclear Information System (INIS)

Roglans-Ribas, J.; Spinrad, B.I.

1990-01-01

The back end of the nuclear fuel cycle has been analyzed under current conditions in the United States, including the constraints imposed by the Nuclear Waste Policy Act of 1982 and its amendments. The scenarios for two closed cycles, a regular reprocessing cycle and a reprocessing scheme with cesium and strontium fractionation, are described. The storage of spent fuel discharged from the reactors and the disposal of reprocessed waste are studied for both reprocessing cycles. The economics of waste storage and disposal for the two closed cycles are compared with each other and with the reference once-through cycle. The results show that a standard reprocessing cycle results in the minimum cost for storage and disposal. When reporcessing costs are considered, the closed cycles can compete economically with the once-through cycle only if net reprocessing costs are very low

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

International Nuclear Information System (INIS)

O'TOOLE, S.M.

1999-01-01

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

Triggering of final oocyte maturation with gonadotropin-releasing hormone agonist or human chorionic gonadotropin. Live birth after frozen-thawed embryo replacement cycles

DEFF Research Database (Denmark)

Griesinger, Georg; Kolibianakis, E M; Papanikolaou, E G

2007-01-01

OBJECTIVE: To report the outcome of frozen-thawed embryo replacement cycles after GnRH-agonist triggering of final oocyte maturation in the collecting cycle with GnRH-antagonist. DESIGN: Prospective, observational, multicentric clinical study. SETTING: Tertiary university-affiliated IVF centers...... a total of 228 participants. Surplus embryos or oocytes at the pronuclear stage were cryopreserved in 53 patients after hCG administration and 32 patients after GnRH-agonist administration on the basis of patient choice, pronuclear/embryo availability, and local laws. INTERVENTION(S): Transfer of frozen......-thawed embryos. MAIN OUTCOME MEASURE(S): Live birth rate. RESULT(S): Thirty-one and 23 patients after administration of hCG and GnRH-agonist, respectively, started a frozen-embryo replacement cycle by September 2005, with 25 and 16 patients eventually undergoing at least one frozen-thawed ET. Live birth rate per...

Fuel cycle management

International Nuclear Information System (INIS)

Herbin, H.C.

1977-01-01

The fuel cycle management is more and more dependent on the management of the generation means among the power plants tied to the grid. This is due mainly because of the importance taken by the nuclear power plants within the power system. The main task of the fuel cycle management is to define the refuelling pattern of the new and irradiated fuel assemblies to load in the core as a function of: 1) the differences which exist between the actual conditions of the core and what was expected for the present cycle, 2) the operating constraints and the reactor availability, 3) the technical requirements in safety and the technological limits of the fuel, 4) the economics. Three levels of fuel cycle management can be considered: 1) a long term management: determination of enrichments and expected cycle lengths, 2) a mid term management whose aim corresponds to the evaluation of the batch to load within the core as a function of both: the next cycle length to achieve and the integrated power history of all the cycles up to the present one, 3) a short term management which deals with the updating of the loaded fuel utilisations to take into account the operation perturbations, or with the alteration of the loading pattern of the next batch to respect unexpected conditions. (orig.) [de

Development of nuclear fuel cycle technologies

International Nuclear Information System (INIS)

Suzuoki, Akira; Matsumoto, Takashi; Suzuki, Kazumichi; Kawamura, Fumio

1995-01-01

In the long term plan for atomic energy that the Atomic Energy Commission decided the other day, the necessity of the technical development for establishing full scale fuel cycle for future was emphasized. Hitachi Ltd. has engaged in technical development and facility construction in the fields of uranium enrichment, MOX fuel fabrication, spent fuel reprocessing and so on. In uranium enrichment, it took part in the development of centrifuge process centering around Power Reactor and Nuclear Fuel Development Corporation (PNC), and took its share in the construction of the Rokkasho uranium enrichment plant of Japan Nuclear Fuel Service Co., Ltd. Also it cooperates with Laser Enrichment Technology Research Association. In Mox fuel fabrication, it took part in the construction of the facilities for Monju plutonium fuel production of PNC, for pellet production, fabrication and assembling processes. In spent fuel reprocessing, it cooperated with the technical development of maintenance and repair of Tokai reprocessing plant of PNC, and the construction of spent fuel stores in Rokkasho reprocessing plant is advanced. The centrifuge process and the atomic laser process of uranium enrichment are explained. The high reliability of spent fuel reprocessing plants and the advancement of spent fuel reprocessing process are reported. Hitachi Ltd. Intends to exert efforts for the technical development to establish nuclear fuel cycle which increases the importance hereafter. (K.I.)

The evaluation of a framework for measuring the non-technical ward round skills of final year nursing students: An observational study.

Science.gov (United States)

Murray, Kara; McKenzie, Karen; Kelleher, Michael

2016-10-01

The importance of non-technical skills (NTS) to patient outcomes is increasingly being recognised, however, there is limited research into how such skills can be taught and evaluated in student nurses in relation toward rounds. This pilot study describes an evaluation of a NTS framework that could potentially be used to measure ward round skills of student nurses. The study used an observational design. Potential key NTS were identified from existing literature and NTS taxonomies. The proposed framework was then used to evaluate whether the identified NTS were evident in a series of ward round simulations that final year general nursing students undertook as part of their training. Finally, the views of a small group of qualified nurse educators, qualified nurses and general nursing students were sought about whether the identified NTS were important and relevant to practice. The proposed NTS framework included seven categories: Communication, Decision Making, Situational Awareness, Teamwork and Task Management, Student Initiative and Responsiveness to Patient. All were rated as important and relevant to practice. The pilot study suggests that the proposed NTS framework could be used as a means of evaluating student nurse competencies in respect of many non-technical skills required for a successful ward round. Further work is required to establish the validity of the framework in educational settings and to determine the extent to which it is of use in a non-simulated ward round setting. Copyright © 2016 Elsevier Ltd. All rights reserved.

GLOBAL 2009: Closing speech - the bulk of technical sessions

International Nuclear Information System (INIS)

Greneche, D.

2009-01-01

The author proposes an overview of the content of the hundred technical sessions of the GLOBAL 2009 conference. Thus, he addresses the twelve main issues: the upstream part of the fuel cycle, the present status of used fuel recycling, the waste management strategies and technologies, the transportation and storage of used fuels and radioactive materials, the definitive storage of nuclear wastes, the new technologies for fuel recycling, advanced designs of reactor cores and fuel management, long life radionuclide transmutation systems, the non proliferation issue, material management and options for sustainable fuel cycles, dismantling, decommissioning and resulting material management, transverse topics (technical-economic studies, nuclear energy applications other than electricity production, challenges of sustainable development of nuclear energy, advanced researches)

Life cycle assessment of biomass-to-liquid fuels - Final report

Energy Technology Data Exchange (ETDEWEB)

Jungbluth, N.; Buesser, S.; Frischknecht, R.; Tuchschmid, M.

2008-02-15

This study elaborates a life cycle assessment of using of BTL-fuels (biomass-to-liquid). This type of fuel is produced in synthesis process from e.g. wood, straw or other biomass. The life cycle inventory data of the fuel provision with different types of conversion concepts are based on the detailed life cycle assessment compiled and published within a European research project. The inventory of the fuel use emissions is based on information published by automobile manufacturers on reductions due to the use of BTL-fuels. Passenger cars fulfilling the EURO3 emission standards are the basis for the comparison. The life cycle inventories of the use of BTL-fuels for driving in passenger cars are investigated from cradle to grave. The full life cycle is investigated with the transportation of one person over one kilometre (pkm) as a functional unit. This includes all stages of the life cycle of a fuel (biomass and fuel production, distribution, combustion) and the necessary infrastructure (e.g. tractors, conversion plant, cars and streets). The use of biofuels is mainly promoted for the reason of reducing the climate change impact and the use of scarce non-renewable resources e.g. crude oil. The possible implementation of BTL-fuel production processes would potentially help to achieve this goal. The emissions of greenhouse gases due to transport services could be reduced by 28% to 69% with the BTL-processes using straw, forest wood or short-rotation wood as a biomass input. The reduction potential concerning non-renewable energy resources varies between 37% und 61%. A previous study showed that many biofuels cause higher environmental impacts than fossil fuels if several types of ecological problems are considered. The study uses two single score impact assessment methods for the evaluation of the overall environmental impacts, namely the Eco-indicator 99 (H,A) and the Swiss ecological scarcity 2006 method. The transportation with the best BTL-fuel from short

Life Cycle Assessments Applied to First Generation Biofuels Used in France. Final report

International Nuclear Information System (INIS)

2010-01-01

a national calculation method parallel to that defined by the Commission. This work presents here a global consistency with the Directive, namely in term of allocation principle based on energy pro-rata, but was also performed in a finer, step by step detail level. The objective of the study is to realize the life cycle assessment of the current biofuel pathways (also called 'first generation') by applying the principles retained in the 2008 methodological guide. This work was performed with the technical support of industrial actors, technical institutes, research centers, and environmental associations. Integrating the European context and wishing to put the results in perspective, this study performs, in a second step, an analysis of the results obtained with other methodologies, including those from the Directive. This critical and constructive aspect emphasizes points of vigilance to keep in mind in the European discussions with regards to quantify biofuel sustainability

TECHNICAL COORDINATION

CERN Document Server

A. Ball and W. Zeuner

2013-01-01

For the reporting period, the CMS common systems and infrastructure worked well, without failures that caused significant data losses. One more disconnection of the magnet cold box occurred in the shadow of interruptions in data taking, caused by a series of technical faults. The recognition during 2012 that re-connection can only safely be done at around 2 T implies a minimum magnet recovery time of 12 hours and raises serious concerns about the number of ramping cycles of the magnet these incidents cause. This has triggered studies of how to make the cryo-system of the magnet more robust against failures. The proton-proton run ended just before the end-of-year CERN closure, during which CASTOR was installed on the negative end of CMS and both ZDC calorimeters were installed in TAN absorbers the LHC tunnel, in preparation for the heavy-ion run. The installation of CASTOR was an excellent “engineering test” of procedures for working in an activated environment. Despite some technical pr...

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

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

Sizing models and performance analysis of volumetric expansion machines for waste heat recovery through organic Rankine cycles on passenger cars

OpenAIRE

Guillaume, Ludovic; Legros, Arnaud; Quoilin, Sylvain; Declaye, Sébastien; Lemort, Vincent

2013-01-01

This paper aims at helping designers of waste heat recovery organic (or non-organic) Rankine cycles on internal combustion engines to best select the expander among the piston, scroll and screw machines, and the working fluids among R245fa, ethanol and water. The first part of the paper presents the technical constraints inherent to each machine through a state of the art of the three technologies. The second part of the paper deals with the modeling of such expanders. Finally, in the last pa...

Heavy water reactors on the once-through uranium cycle

International Nuclear Information System (INIS)

1978-05-01

This paper presents preliminary technical and economic data to INFCE on the once-through uranium fuel cycle for use in early comparisons of alternate nuclear systems. The denatured thorium fuel cycle is discussed in a companion paper. Information for this paper was developed under an ongoing program, and more complete reporting of the evaluation of the heavy water reactor and its fuel cycles is planned toward the end of the year

Guidelines for technical reviews of software products

Energy Technology Data Exchange (ETDEWEB)

Wilburn, N.P.

1982-03-01

A guideline is given for technical review of products developed during a software life cycle. Purposes and benefits of reviews are given. Varieties of reviews, when they should take place, roles of the reviewers and products of the review are described.

Guidelines for technical reviews of software products

International Nuclear Information System (INIS)

Wilburn, N.P.

1982-03-01

A guideline is given for technical review of products developed during a software life cycle. Purposes and benefits of reviews are given. Varieties of reviews, when they should take place, roles of the reviewers and products of the review are described

Effective technical service in the life cycle of heavy dumpers

Directory of Open Access Journals (Sweden)

Михайло Валерійович Помазков

2016-11-01

Full Text Available A comparative analysis of the known systems of technical reliability of heavy dumpers functionality has been made. It has been stated that the previously proposed methods to determine the optimal service life of heavy-duty dumpers are not effective enough and do not take into account the whole range of factors specific to the operation of heavy dumpers in the current economic realities of industrial enterprises. Based on the analysis results, a mechanism of determining the optimal service life of heavy-duty dumpers and their constituent technical systems ensuring the operational reliability of heavy-duty dumpers has been offered. The article takes into account the analysis of resource factors, general description of system logistic tasks, the main provisions of serviceability, the resource forming in route charts at ore mining and metallurgical enterprises, the use of theoretical developments in practice. Heavy dumpers generalized description modelling shown in the article, the principle of resource use by using interchangable work at different intensity routes has received confirmation in the dumpers’ work schedule

Polar source analysis : technical memorandum

Science.gov (United States)

2017-09-29

The following technical memorandum describes the development, testing and analysis of various polar source data sets. The memorandum also includes recommendation for potential inclusion in future releases of AEDT. This memorandum is the final deliver...

Zero-emission vehicle technology assessment. Final report

Energy Technology Data Exchange (ETDEWEB)

Woods, T.

1995-08-01

This is the final report in the Zero-Emission Vehicle (ZEV) Technology Assessment, performed for NYSERDA by Booz-Allen & Hamilton Inc. Booz-Allen wrote the final report, and performed the following tasks as part of the assessment: assembled a database of key ZEV organizations, their products or services, and plans; described the current state of ZEV technologies; identified barriers to widespread ZEV deployment and projected future ZEV technical capabilities; and estimated the cost of ZEVs from 1998 to 2004. Data for the ZEV Technology Assessment were obtained from several sources, including the following: existing ZEV industry publications and Booz-Allen files; major automotive original equipment manufacturers; independent electric vehicle manufacturers; battery developers and manufacturers; infrastructure and component developers and manufacturers; the U.S. Department of Energy, the California Air Resources Board, and other concerned government agencies; trade associations such as the Electric Power Research Institute and the Electric Transportation Coalition; and public and private consortia. These sources were contacted by phone, mail, or in person. Some site visits of manufacturers also were conducted. Where possible, raw data were analyzed by Booz-Allen staff and/or verified by independent sources. Performance data from standardized test cycles were used as much as possible.

Technical features to enhance proliferation resistance of nuclear energy systems

International Nuclear Information System (INIS)

2010-01-01

It is generally accepted that proliferation resistance is an essential issue for the continued development and sustainability of nuclear energy. Several comprehensive assessment activities on the proliferation resistance of the nuclear fuel cycle have previously been completed, notably the International Nuclear Fuel Cycle Evaluation (INFCE) carried out under the auspices of the IAEA, and the Non-proliferation Alternative Systems Assessment Program (NASAP) review carried out by the USA. There have been, however, relatively few comprehensive treatments of the issue following these efforts in the 1970s. However, interest in and concern about this issue have increased recently, particularly because of greater interest in innovative nuclear fuel cycles and systems. In 2000, the IAEA initiated the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) and the US Department of Energy initiated the Generation IV International Forum (GIF). These projects are aimed at the selection and development of concepts of innovative nuclear energy systems and fuel cycles. Proliferation resistance is one of the fundamental considerations for both projects. In this context, the IAEA in 2001 initiated a study entitled 'Technical Aspects of Increasing Proliferation Resistance of the Nuclear Fuel Cycle'. This task is not intended as an effort to assess the merits of a particular fuel cycle system for the future, but to describe a qualitative framework for an examination of the proliferation resistance provided by the intrinsic features of an innovative nuclear energy system and fuel cycle. This task also seeks to provide a high level survey of a variety of innovative nuclear energy systems and fuel cycles with respect to that framework. The concept of proliferation resistance is considered in terms of intrinsic features and extrinsic measures. The intrinsic features, sometimes referred to as the physical/technical aspects, are those features that result from the

Advanced Low Temperature Geothermal Power Cycles (The ENTIV Organic Project) Final Report

Energy Technology Data Exchange (ETDEWEB)

Mugerwa, Michael [Technip USA, Inc., Claremont, CA (United States)

2015-11-18

Feasibility study of advanced low temperature thermal power cycles for the Entiv Organic Project. Study evaluates amonia-water mixed working fluid energy conversion processes developed and licensed under Kalex in comparison with Kalina cycles. Both cycles are developed using low temperature thermal resource from the Lower Klamath Lake Geothermal Area. An economic feasibility evaluation was conducted for a pilot plant which was deemed unfeasible by the Project Sponsor (Entiv).

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...

Digital calculations of engine cycles

CERN Document Server

Starkman, E S; Taylor, C Fayette

1964-01-01

Digital Calculations of Engine Cycles is a collection of seven papers which were presented before technical meetings of the Society of Automotive Engineers during 1962 and 1963. The papers cover the spectrum of the subject of engine cycle events, ranging from an examination of composition and properties of the working fluid to simulation of the pressure-time events in the combustion chamber. The volume has been organized to present the material in a logical sequence. The first two chapters are concerned with the equilibrium states of the working fluid. These include the concentrations of var

Large-scale fuel cycle centres

International Nuclear Information System (INIS)

Smiley, S.H.; Black, K.M.

1977-01-01

The US Nuclear Regulatory Commission (NRC) has considered the nuclear energy centre concept for fuel cycle plants in the Nuclear Energy Centre Site Survey 1975 (NECSS-75) Rep. No. NUREG-0001, an important study mandated by the US Congress in the Energy Reorganization Act of 1974 which created the NRC. For this study, the NRC defined fuel cycle centres as consisting of fuel reprocessing and mixed-oxide fuel fabrication plants, and optional high-level waste and transuranic waste management facilities. A range of fuel cycle centre sizes corresponded to the fuel throughput of power plants with a total capacity of 50,000-300,000MW(e). The types of fuel cycle facilities located at the fuel cycle centre permit the assessment of the role of fuel cycle centres in enhancing the safeguard of strategic special nuclear materials - plutonium and mixed oxides. Siting fuel cycle centres presents a smaller problem than siting reactors. A single reprocessing plant of the scale projected for use in the USA (1500-2000t/a) can reprocess fuel from reactors producing 50,000-65,000MW(e). Only two or three fuel cycle centres of the upper limit size considered in the NECSS-75 would be required in the USA by the year 2000. The NECSS-75 fuel cycle centre evaluation showed that large-scale fuel cycle centres present no real technical siting difficulties from a radiological effluent and safety standpoint. Some construction economies may be achievable with fuel cycle centres, which offer opportunities to improve waste-management systems. Combined centres consisting of reactors and fuel reprocessing and mixed-oxide fuel fabrication plants were also studied in the NECSS. Such centres can eliminate shipment not only of Pu but also mixed-oxide fuel. Increased fuel cycle costs result from implementation of combined centres unless the fuel reprocessing plants are commercial-sized. Development of Pu-burning reactors could reduce any economic penalties of combined centres. The need for effective fissile

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

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.

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.

The technical and industrial evolutions in the nuclear fuel cycle

International Nuclear Information System (INIS)

Rougeau, J.P.; Guais, J.C.

1989-01-01

The fuel cycle industry is a vital part of nuclear energy generation. Producers in every step of this industry, from uranium to reprocessing are working to adapt their products and services both to the more and more competitive conditions of the market and to the utilities evoluting specific needs. For the next decade, the main trend is uranium economy and reduction of industrial costs. For the longer term, the difficult prevision of nuclear energy developments, in particular with new types of reactors necessitates a true capacity of adaptation both from the utilities and from the fuel cycle industry. Cogema has already demonstrated the ability to adapt its industrial capabilities and therefore can prepare confidently for the future challenges [fr

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 1. Summary: alternatives for the back of the LWR fuel cycle types and properties of LWR fuel cycle wastes projections of waste quantities; selected glossary

International Nuclear Information System (INIS)

1976-05-01

Volume I of the five-volume report contains executive and technical summaries of the entire report, background information of the LWR fuel cycle alternatives, descriptions of waste types, and projections of waste quantities. Overview characterizations of alternative LWR fuel cycle modes are also included

Life Cycle Engineering – from methodology to enterprise culture

DEFF Research Database (Denmark)

Hauschild, Michael Zwicky; Alting, Leo; Poll, Christian

2003-01-01

As part of a sustainable development, the environmental efficiency of industry must increase by a factor four to ten. This engenders attention to the environmental impact of products and technical systems over their entire life cycle. The last decade has seen the development of a number of method......As part of a sustainable development, the environmental efficiency of industry must increase by a factor four to ten. This engenders attention to the environmental impact of products and technical systems over their entire life cycle. The last decade has seen the development of a number...... of methodologies and tools for life cycle assessment and development of more eco-efficient products, from complex to simplified, catering to the needs of especially small and medium-sized enterprizes. The tools and data are in place, but dissemination lacks behind. Propagation of life cycle thinking and life cycle...... engineering to larger parts of industry is attempted by strengthening the market pull through integrated product policy measures, and at the same time pushing through information activities, training and dissemination of tools. Experience hitherto shows that these forces are insufficient and that stronger...

NUSC Technical Publications Guide.

Science.gov (United States)

1985-05-01

Facility personnel especially that of A. Castelluzzo, E. Deland, J. Gesel , and E. Szlosek (all of Code 4343). Reviewed and Approved: 14 July 1980 D...their technical content and format. Review and approve the manual outline, the review manuscript, and the final camera - reproducible copy. Conduct in

Fuel cycle services

International Nuclear Information System (INIS)

Gruber, Gerhard J.

1990-01-01

TRIGA reactor operators are increasingly concerned about the back end of their Fuel Cycle due to a new environmental policy in the USA. The question how to close the Fuel Cycle will have to be answered by all operators sooner or later. Reprocessing of the TRIGA fuel elements is not available. Only long term storage and final disposal can be considered. But for such a storage or disposal a special treatment of the fuel elements and of course a final depository is necessary. NUKEM plans to undertake efforts to assist the TRIGA operators in this area. For that reason we need to know your special needs for today and tomorrow - so that potential processors can consider whether to offer these services on the market. (orig.)

Optimization of life cycle management costs

International Nuclear Information System (INIS)

Banerjee, A.K.

1994-01-01

As can be seen from the case studies, a LCM program needs to address and integrate, in the decision process, technical, political, licensing, remaining plant life, component replacement cycles, and financial issues. As part of the LCM evaluations, existing plant programs, ongoing replacement projects, short and long-term operation and maintenance issues, and life extension strategies must be considered. The development of the LCM evaluations and the cost benefit analysis identifies critical technical and life cycle cost parameters. These open-quotes discoveriesclose quotes result from the detailed and effective use of a consistent, quantifiable, and well documented methodology. The systematic development and implementation of a plant-wide LCM program provides for an integrated and structured process that leads to the most practical and effective recommendations. Through the implementation of these recommendations and cost effective decisions, the overall power production costs can be controlled and ultimately lowered

Medium energy measurements of N-N parameters. Final technical report, April 1, 1994--September 30, 1996

International Nuclear Information System (INIS)

Ambrose, D.; Betts, W.; Coffey, P.; Glass, G.; McDonough, J.; Riley, P.; Tang, J.L.

1998-08-01

This document is a final technical report describing the accomplishments of the medium/high energy nuclear physics research program at the University of Texas at Austin. The research program had four main thrusts, only one of which can be considered as measurements of N-N parameters: (1) finishing the data analyses associated with recent LAMPF and TRIUMPF N-N experiments, whose overall purpose has been the determination of the nucleon-nucleon amplitudes, both for isospin 0 and 1 at medium energies; (2) continuing work on BNL E871, a search for rare decay modes of the K L ; (3) work on the RHIC-STAR project, an experiment to create and study a quark gluon plasma and nuclear matter at high energy density; (4) beginning a new AGS experiment (E896) which will search for the lowest mass state of the predicted strange di-baryons, the Ho, and other exotic states of nuclear matter through nucleus-nucleus collisions

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

Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2006-05-04

. Platform teams organize faculty and students for cross-disciplinary, systems-oriented research and collaborative learning. To date, nine platforms have been developed, although these will most likely be reorganized into a smaller number of broader topics. In the spring of 2004, BRT faculty initiated a regional partnership and collaborative learning program with colleagues at the University of Minnesota, Kansas State University, and South Dakota State University to develop distance education courses in biorenewable resources and technology. As a fledgling graduate program, the BRT graduate program didn’t have the breadth of resources to offer a large number of courses in biorenewables. Other schools faced a similar problem. The academic consortium as first conceived would allow students from the member schools to enroll in biorenewables courses from any of the participating schools, which would assure the necessary enrollment numbers to offer specialized course work. Since its inception, the collaborative curriculum partnership has expanded to include Louisiana State University and the University of Wisconsin. A second international curriculum development campaign was also initiated in the spring of 2004. In particular, several BRT faculty teamed with colleagues at the University of Arkansas, University of Washington, University of Gent (Belgium), National Polytechnic Institute of Toulouse (France), and Technical University of Graz (Austria) to develop an EU-US exchange program in higher education and vocational education/training (entitled “Renewable Resources and Clean Technology”).

Document status for 1 and 2 Kozloduy NPP decommissioning activities -Phase 'Final Shutdown'

International Nuclear Information System (INIS)

Vangev, A.; Boyadjiev, Z.

1997-01-01

Decommissioning process (D and D) is the final phase of each nuclear reactor life cycle. The first nuclear reactor generation has reached his expiration life date. Decommissioning working documentation had not been taken into account at the project and construction stage. The decommissioning activities, planning and legislation has to develop along their operation. Most of developed nuclear energetic countries have gathered good experience and have create their own decommissioning strategy. This report represents in brief an overview of different country's approaches and the Kozloduy NPP decommissioning activity intention in near future and reviews the D and D working document status for 1 and 2 Kozloduy NPP Units decommissioning. Kozloduy NPP D and D task to the moment is to plan the first stage of the decommissioning process - 'The Final Shutdown' and to prepare the working documents for the phase execution. The Final Shutdown of Kozloduy NPP - 1 is the termination of operation of the Units 1 and 2 and the electricity production cessation after their useful life exhaust. In accordance with the legal legislation in Bulgaria only the normal planned termination of operation on units 1 and 2 should be prescribed. The project results concern the initial condition of the equipment and systems, their preparation and sequence for defueling, decontamination and dismantling. A plan for activities' organization for D and D and Complex Characterization of the Site under consideration will contain the following documents: 1. Time-schedule for the sequence of activities during the stages of the Final Shutdown and Safe Enclosure preparation. Technical project for organization of work related to Final Shutdown; 2. Complex Characterization Programme for a condition investigation of the Units 1 and 2 equipment and systems. 3. Technical project for design modifications and dismantling of equipment and systems which violate the radiation and nuclear safety during the Final Shutdown

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-11-03

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

Environmental analysis of natural gas life cycle

International Nuclear Information System (INIS)

Riva, A.; D'Angelosante, S.; Trebeschi, C.

2000-01-01

Life Cycle Assessment is a method aimed at identifying the environmental effects connected with a given product, process or activity during its whole life cycle. The evaluation of published studies and the application of the method to electricity production with fossil fuels, by using data from published databases and data collected by the gas industry, demonstrate the importance and difficulties to have reliable and updated data required for a significant life cycle assessment. The results show that the environmental advantages of natural gas over the other fossil fuels in the final use stage increase still further if the whole life cycle of the fuels, from production to final consumption, is taken into account [it

Using communication norms in socio-technical systems

NARCIS (Netherlands)

Weigand, H.; Whitworth, B.; de Moor, A.

2009-01-01

Often socio-technical systems are designed simply on the basis of what the user asks, and without considering explicitly whether the required process structure is right and wrong. However, poor communication may cause many problems. Therefore, a design cycle should always include diagnosis, and in

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.

Fundamental studies of the chemical vapor deposition of diamond. Final technical report, April 1, 1988--December 31, 1994

Energy Technology Data Exchange (ETDEWEB)

Nix, W.D.

1995-05-01

We submit here a final technical report for the research program entitled: Fundamental Studies of the Chemical Vapor Deposition of Diamond, DOE Grant No. DE-FG05-88ER45345-M006. This research program was initiated in 1988 under the direction of the late Professor David A. Stevenson and was renewed in 1992. Unfortunately, at the end of 1992, just as the last phase of this work was getting underway, Professor Stevenson learned that he had developed mesothelioma, a form of cancer based on asbestos. Professor Stevenson died from that disease in February of 1994. Professor William D. Nix, the Chairman of the Materials Science department at Stanford was named the Principal Investigator. Professor Nix has assembled this final technical report. Much of the work of this grant was conducted by Mr. Paul Dennig, a graduate student who will receive his Ph.D. degree from Stanford in a few months. His research findings are described in the chapters of this report and in the papers published over the past few years. The main discovery of this work was that surface topology plays a crucial role in the nucleation of diamond on silicon. Dennig and his collaborators demonstrated this by showing that diamond nucleates preferentially at the tips of asperities on a silicon surface rather than in the re-entrant comers at the base of such asperities. Some of the possible reasons for this effect are described in this report. The published papers listed on the next page of this report also describe this research. Interested persons can obtain copies of these papers from Professor Nix at Stanford. A full account of all of the research results obtained in this work is given in the regular chapters that follow this brief introduction. In addition, interested readers will want to consult Mr. Dennig`s Ph.D. dissertation when it is made available later this year.

Proliferation resistance fuel cycle technology

Energy Technology Data Exchange (ETDEWEB)

Lee, J. S.; Ko, W. I

1999-02-01

The issues of dual use in nuclear technology are analysed for nuclear fuel cycle with special focus on uranium enrichment and spent fuel reprocessing which are considered as the most sensitive components in terms of vulnerability to diversion. Technical alternatives to mitigrate the vulnerability, as has been analysed in depth during the NASAP and INFCE era in the late seventies, are reviewed to characterize the DUPIC fuel cycle alternative. On the other hand, the new realities in nuclear energy including the disposition of weapon materials as a legacy of cold war are recast in an angle of nuclear proliferation resistance and safeguards with a discussion on the concept of spent fuel standard concept and its compliance with the DUPIC fuel cycle technology. (author)

Minutes of the IFMIF technical meeting

International Nuclear Information System (INIS)

Nakamura, H.; Takeda, M.; Ida, M.; Maebara, S.; Yutani, T.; Sugimoto, M.

2004-03-01

The IFMIF Technical Meeting was held on December 4-5, 2003 at Shiran-kaikan, Kyoto University. The main objectives are 1) to finalize the Comprehensive Design Report (CDR), 2) to discuss IFMIF cost and organization, 3) to review technical status of major systems, transition phase activities and EVEDA plan. This report presents a brief summary of the results of the meeting. Agenda, participants list and presentation materials are attached as Appendix. (author)

Hispanic Vocational Exploration Project. Final Report.

Science.gov (United States)

Centro De La Comunidad, Inc., New London, CT.

During its second year, the Hispanic Vocational Exploration Project recruited eighth and ninth grade Hispanic youth for a four-week cycle, after-school, career exploratory program at Southeastern Regional Vocational Technical School, Groton, Connecticut. A series of career education workshops was the other major project activity. Supportive…

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.

Research in JAERI on the backend of nuclear fuel cycle

International Nuclear Information System (INIS)

Maeda, Mitsuru; Takeshita, Isao

1999-01-01

Japan's policy of the backend of nuclear fuel cycle is to reprocess spent fuels and recycle recovered plutonium and uranium, under the principle of no surplus plutonium. High-level radioactive waste separated during reprocessing will be disposed of after solidification in vitrified form, followed by the storage for 30 to 50 years and finally by ultimate disposal in a deep geological formation. The role of JAERI and the effective utilization of NUCEF would become more important. The current status of JAERI's research on backend cycle is reviewed together with the future research direction with emphases on NUCEF utilization. (1) Major objectives of safety research is to develop safety criteria and establish technical bases for licensing, to improve the safety of current or near future technology and to clarify the safety margin of licensed technology. (2) The present goal of fundamental research is to show or clarify the chemical or scientific feasibility of advanced system such as for recycling minor actinides or for incinerating long-lived nuclides. (3) Supporting research for nuclear material control is also conducted mainly for international contribution to strengthened safeguards by IAEA and to frame working of international monitoring system for CTBT. (J.P.N.)

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.

Life cycle greenhouse gas analysis of biojet fuels with a technical investigation into their impact on jet engine performance

International Nuclear Information System (INIS)

Lokesh, Kadambari; Sethi, Vishal; Nikolaidis, Theoklis; Goodger, Eric; Nalianda, Devaiah

2015-01-01

Biojet fuels have been claimed to be one of the most promising and strategic solutions to mitigate aviation emissions. This study examines the environmental competence of Bio-Synthetic Paraffinic Kerosene (Bio-SPKs) against conventional Jet-A, through development of a life cycle GHG model (ALCEmB – Assessment of Life Cycle Emissions of Biofuels) from “cradle-grave” perspective. This model precisely calculates the life cycle emissions of the advanced biofuels through a multi-disciplinary study entailing hydrocarbon chemistry, thermodynamic behaviour and fuel combustion from engine/aircraft performance, into the life cycle studies, unlike earlier studies. The aim of this study is predict the “cradle-grave” carbon intensity of Camelina SPK, Microalgae SPK and Jatropha SPK through careful estimation and inclusion of combustion based emissions, which contribute ≈70% of overall life cycle emissions (LCE). Numerical modelling and non-linear/dynamic simulation of a twin-shaft turbofan, with an appropriate airframe, was conducted to analyse the impact of alternative fuels on engine/aircraft performance. ALCEmB revealed that Camelina SPK, Microalgae SPK and Jatropha SPK delivered 70%, 58% and 64% LCE savings relative to the reference fuel, Jet-A1. The net energy ratio analysis indicates that current technology for the biofuel processing is energy efficient and technically feasible. An elaborate gas property analysis infers that the Bio-SPKs exhibit improved thermodynamic behaviour in an operational gas turbine engine. This thermodynamic effect has a positive impact on aircraft-level fuel consumption and emissions characteristics demonstrating fuel savings in the range of 3–3.8% and emission savings of 5.8–6.3% (CO 2 ) and 7.1–8.3% (LTO NOx), relative to that of Jet-A. - Highlights: • Bio-SPKs were determined to deliver “Cradle-Grave” GHG savings of 58–70%. • Bio-SPKs exhibited improved thermodynamic behaviour at integrated system level assessment

Expectation and task for constructing the volume reduction system of removed soils. In search of the technical integrity from the intermediate storage to final disposal

International Nuclear Information System (INIS)

Mori, Hisaki

2016-01-01

The intermediate storage volume of the removed soils and incineration ash in Fukushima is supposed about 22 million cubic meters. Within 30 years after starting the intermediate storage, the final disposal outside Fukushima prefecture to these removed soils and incineration ash is determined by the law. Because these removed soils are the very-very low radio activity, the volume reduction method is most effective to reduce the burden of the final disposal. As the volume reduction technology is the stage of research and development, the possibility of the introduction of the volume reduction technology that has the consistency of the final disposal technology is evaluated from the point of view of cost. Since this business is accompanied by economic and technical risk to implement private companies, this project is considered appropriate to be implemented as a national project. (author)

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.

Medicare and Medicaid programs; salary equivalency guidelines for physical therapy, respiratory therapy, speech language pathology, and occupational therapy services; revised effective date and technical correction--HCFA. Final rule; delay of effective date and correction.

Science.gov (United States)

1998-03-31

This document delays the effective date of the final rule on salary equivalency guidelines, published in the Federal Register (63 FR 5106) on January 30, 1998, from April 1, 1998 to April 10, 1998. In addition, we are making a technical correction in the preamble to the January 30, 1998 final rule.

Technical feasibility of the electrode ionization process for the makeup water treatment system of the thermal cycle of the CAREM-25 nuclear power plant

International Nuclear Information System (INIS)

Ramilo, Lucia B.; Chocron, Mauricio

2003-01-01

In thermal cycles of PWRs nuclear power plants with once-through steam generators as the CAREM-25, makeup water of very high purity is required to minimizing the induction of corrosion phenomena, fundamentally in the steam generators and other thermal cycle components. The makeup water treatment systems include several stages, of which the demineralization is the purification stage. The required makeup water purity is obtained in this stage. Historically, ultrapure water systems were based completely on ion exchange technology. Now, the electrode ionization process (EDI) has replaced the ion exchange technology used traditionally in the demineralization stage. Continuous demineralization in an EDI stack consists of three coupled processes: ion exchange, continuous ion removal by transport through the ion exchange resin and membranes into the concentrate stream, continuous regeneration by hydrogen and hydroxyl ions derived from the water splitting reaction and driven by the applied direct current. EDI process allows to obtain ultrapure water, with practically no use of chemical reagents and with technologies of continuous process. The objective of this work is the analysis of the electrode ionization process (EDI) for its implementation in the makeup water treatment system of the thermal cycle of the CAREM-25 nuclear power plant. The obtained results allow to assure the technical feasibility of implementation of the electrode ionization process, EDI, in the makeup water treatment system of the thermal cycle of this Argentinean nuclear power plant. (author)

Summary of the ITER final design report. July 2001

International Nuclear Information System (INIS)

2001-01-01

This document is a summary of the ITER final design report foreseen during the current, Engineering Design Activities (EDA), phase of the ITER project. The report presents the results of collaborative design and supporting technical work undertaken by the ITER Joint Central team (JCT) and the Home Teams (HT) of the parties to the agreement on co-operation in the Engineering Design Activities for ITER (the ITER EDA Agreement). This report marks the achievement of the full technical scope of activities indicated in the ITER EDA Agreement, with a final design which meets the programmatic objective defined in the Agreement and satisfies detailed scientific, technical and costing objectives set by ITER Council in 1998

New usable technical specifications

International Nuclear Information System (INIS)

Webster, S.A.; Tomasi, L.T.; Bernier, R.A.

1989-01-01

After 2 yr of preparation, 1988 finally saw the nuclear industry writing operator-oriented technical specifications. This effort is a continuation of previous efforts to develop improved and usable standard technical specifications (STSs), and is being conducted by the four nuclear steam supply system vendor owners' groups under the auspices of the Nuclear Management Resources Council. Each participant is currently preparing a set of improved STSs based on a writer's guide that was developed through a combined industry effort. In May of 1987, a Human Factors Improvements to Technical Specifications (HFITS) task group was formed to prepare a writer's guide for improved, industrywide STSs. This task group was composed of two representatives from each owners' group, one with a human factors background and one with some operations background. Two documents were prepared in 6 months, a human factors report laying the groundwork for the considerations to go into technical specifications and a writer's guide for their preparation. This paper reports on the application of this writer's guide to the writing of improved STS

Large-scale fuel cycle centers

International Nuclear Information System (INIS)

Smiley, S.H.; Black, K.M.

1977-01-01

The United States Nuclear Regulatory Commission (NRC) has considered the nuclear energy center concept for fuel cycle plants in the Nuclear Energy Center Site Survey - 1975 (NECSS-75) -- an important study mandated by the U.S. Congress in the Energy Reorganization Act of 1974 which created the NRC. For the study, NRC defined fuel cycle centers to consist of fuel reprocessing and mixed oxide fuel fabrication plants, and optional high-level waste and transuranic waste management facilities. A range of fuel cycle center sizes corresponded to the fuel throughput of power plants with a total capacity of 50,000 - 300,000 MWe. The types of fuel cycle facilities located at the fuel cycle center permit the assessment of the role of fuel cycle centers in enhancing safeguarding of strategic special nuclear materials -- plutonium and mixed oxides. Siting of fuel cycle centers presents a considerably smaller problem than the siting of reactors. A single reprocessing plant of the scale projected for use in the United States (1500-2000 MT/yr) can reprocess the fuel from reactors producing 50,000-65,000 MWe. Only two or three fuel cycle centers of the upper limit size considered in the NECSS-75 would be required in the United States by the year 2000 . The NECSS-75 fuel cycle center evaluations showed that large scale fuel cycle centers present no real technical difficulties in siting from a radiological effluent and safety standpoint. Some construction economies may be attainable with fuel cycle centers; such centers offer opportunities for improved waste management systems. Combined centers consisting of reactors and fuel reprocessing and mixed oxide fuel fabrication plants were also studied in the NECSS. Such centers can eliminate not only shipment of plutonium, but also mixed oxide fuel. Increased fuel cycle costs result from implementation of combined centers unless the fuel reprocessing plants are commercial-sized. Development of plutonium-burning reactors could reduce any

Modeling the Pan-Arctic terrestrial and atmospheric water cycle. Final report; FINAL

International Nuclear Information System (INIS)

Gutowski, W.J. Jr.

2001-01-01

This report describes results of DOE grant DE-FG02-96ER61473 to Iowa State University (ISU). Work on this grant was performed at Iowa State University and at the University of New Hampshire in collaboration with Dr. Charles Vorosmarty and fellow scientists at the University of New Hampshire's (UNH's) Institute for the Study of the Earth, Oceans, and Space, a subcontractor to the project. Research performed for the project included development, calibration and validation of a regional climate model for the pan-Arctic, modeling river networks, extensive hydrologic database development, and analyses of the water cycle, based in part on the assembled databases and models. Details appear in publications produced from the grant

TADS Final Evaluation Report, 1980-81. Appendix S.

Science.gov (United States)

Suarez, Tanya M.; And Others

The document contains the final report of the Technical Assistance Development System (TADS), a program which provided technical assistance (TA) services to 53 Handicapped Children's Early Education Program (HCEEP) demonstration projects and 13 State Implementation Grants (SIGs). The evaluation report is divided into five sections. Section 1…

Final report. Geothermal Energy Program: Information dissemination, public outreach, and technical analysis activities. April 1, 1999 to December 31, 2001. USDOE Grant No. DE-FG01-99-EE35098

Energy Technology Data Exchange (ETDEWEB)

Lund, John W.

2002-03-22

This is the final report of the accomplishments of the geothermal energy program: information dissemination, public outreach, and technical analysis activities by the project team consisting of the Geo-Heat Center, Geothermal Resources Council, Geothermal Education Office, Geothermal Energy Association, and the Washington State University Energy Program.

The technical-tactical preparation of the boxers from Sancti Spíritus

Directory of Open Access Journals (Sweden)

Juan Manuel García Hernández

2018-05-01

Full Text Available The investigative work presented is part of the daily work of the group of trainers that works in the Provincial Boxing Academy in the province of Sancti Spíritus. The problem investigated responds to the technological demands that exist at the provincial level, with the objective of applying a set of technical-tactical actions to raise the level of preparation of the boxers of Sancti Spiritus that allows to obtain satisfactory results in the competitive order. The diagnosis was developed based on the results of the technical tests of the participation of the boxers from Sancti Spiritus in the Playa Girón National Championships in the 2013-2016 cycle. The final results are compared with those issued by the specialists of the National Technical Commission in the present Playa Girón National Championship held in December 2017, in the Sala Yara of the Province of Sancti Spíritus. The population that used for this investigation is made up of 20 elite category boxers from the province of Sancti Spíritus. The achievements correspond to the work done collectively and individually from the shortcomings and potentials presented by the investigated boxers from Sancti Spiritus. Therefore, it was possible to demonstrate that taking into account the behavior of the main dimensions and indicators of the technical tests, good competitive results can be obtained and that it facilitated the differentiated work with each boxer taking into account the scientific and technical advances at our disposal. In order to comply with this research, theoretical, empirical and mathematical methods were used; among them we can mention: Historical-logical, synthesis analysis, inductive deductive, observation, interview, pre-experiment and descriptive statistics.

Fifth technical meeting on quality

International Nuclear Information System (INIS)

Girard, A.

1998-01-01

This article reports on the 5th Technical Meeting on Quality which was held in San Diego on 20-22 October 1997 and which was attended by representatives of the Home and Joint Central Team and of manufacturers currently involved in the Large R and D projects. The meeting made progress towards the finalization of the ITER Quality Manual document for inclusion in the Final Design Report and the definition of the quality necessary for ITER procurement and construction

Introduction of long term cycle of reactor operation

International Nuclear Information System (INIS)

Aoyati, M.; Tanaka, T.

2004-01-01

Introduction of long term cycle of LWR reactor operation at NPP in Japan is considered, and problems of technical, legislative and economical character, increase of power coefficient are discussed. More long term operation period provides decreasing frequency of periodic inspections and reduction of personnel radiation doses. Reliability of fuel, energetic equipment, mechanisms and devices must be taken into account for the decision of technical problems. Consumptions for electric power generation are studied [ru

Technical and economic limits to fuel burnup extension. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-07-01

For many years, the increase of efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase of fuel burnup leads to a reduction in the volume of spent fuel discharged to longer fuel cycles in the reactor, which means bigger availability and capacity factors. After having increased the authorized burnup in plants, developing new alloys capable of resisting high burnup, and having accumulated data on fuel evolution with burnup, it has become necessary to establish the limitations which could be imposed by the physical evolution of the fuel, influencing fuel management, neutron properties, reprocessing or, more generally, the management of waste and irradiated fuels. It is also necessary to verify whether the benefits of lower electricity costs would not be offset by an increase in fuel management costs. The main questions are: Are technical and economic limits to the increasing of fuel burnup in parallel? Can we envisage nowadays the hardest limitation in some of these areas? Which are the main points to be solved from the technical point of view? Is this effort worthwhile considering the economy of the cycle? To which extent? For these reasons, the IAEA, following a recommendation by the International Working Group on Fuel Performance and Technology, held a Technical Committee Meeting on Technical and Economic Limits to Fuel Burnup Extension. The purpose of this meeting was to provide an international forum to review the evolution of fuel properties at increased burnup in order to estimate the limitations both from a physical and an economic point of view. The meeting was therefore divided into two parts. The first part, focusing on technical limits, was devoted to the improvement of the fuel element, such as fission gas release (FGR), RIM effect, cladding, etc. and the fabrication, core management, spent fuel and reprocessing. Eighteen related papers were presented which

Investigations on the application of zeotropic fluid mixtures in the organic rankine cycle for the geothermal power generation; Untersuchung zum Einsatz von zeotropen Fluidgemischen im Organic Rankine Cycle fuer die geothermische Stromerzeugung

Energy Technology Data Exchange (ETDEWEB)

Heberle, Florian

2013-04-01

The organic rankine cycle is a thermodynamic cycle process which uses an organic fluid working fluid instead of water in comparison to the commercial rankine process. The organic rankine cycle facilitates sufficiently high pressures at moderate temperatures. The organic rankine cycle significantly expands the technically possible and economically feasible ranges of application of such heat and power processes. The geothermal power is a very attractive field of application. Thermal water with a temperature of nearly 100 Celsius can be used for the power generation by means of the organic rankine cycle. Especially zeotropic mixtures are interesting as a working fluid. This is due to a non-isothermal phase change to a temperature glide which adapts very well to the temperature progress of the heat source. The author of the book under consideration reports on the application of different mixtures in the organic rankine cycle. The evaluation is based on a thermodynamic analysis and considers also toxicological, ecologic, technical as well as economic aspects.

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

Environmental macroeconomics : Environmental policy, business cycles, and directed technical change

NARCIS (Netherlands)

Fischer, Carolyn; Heutel, Garth

Environmental economics has traditionally fallen in the domain of microeconomics, but approaches from macroeconomics have recently been applied to studying environmental policy. We focus on two macroeconomic tools and their application to environmental economics. First, real-business-cycle models

Life cycle management and assessment: approaches and visions towards sustainable manufacturing

DEFF Research Database (Denmark)

Westkämper, Engelbert; Alting, Leo; Arndt, Günther

2000-01-01

. The goal of this approach is to protect resources and maximize effectiveness by means of life cycle assessment, product data management, technical support and, last but not least, life cycle costing. This paper shows the existing approaches of LCM and discusses their prospects and further development....... concepts are required, new regulations have been passed or consumer values are changing, the differences between business areas are disappearing. Life cycle management (LCM) considers the product life cycle as a whole and optimizes the interaction of product design, manufacturing and life cycle activities...

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-01-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the ''front end'' and ''back end'' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of the Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-10-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the 'front end' and 'back end' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of The Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

Suggested non-proliferation criteria for commercial nuclear fuel cycles

International Nuclear Information System (INIS)

Laney, R.V.; Heubotter, P.R.

1978-01-01

Based on the Administration's policy to prevent nuclear weapons proliferation through diversion of fuel from commercial reactor fuel cycles, a ''benchmark'' set of nonproliferation criteria was prepared for the commercial nuclear fuel cycle. These criteria should eliminate incremental risks of proliferation beyond those inherent in the present generation of low-enriched-uranium-fueled reactors operating in a once-through mode, with internationally safeguarded storage of spent fuel. They focus on the balanced application of technical constraints consistent with the state of the technology, with minimal requirements for institutional constraints, to provide a basis for assessing the proliferation resistance of proposed fission power systems. The paper contains: (1) our perception of the nuclear energy policy and of the baseline proliferation risk accepted under this policy; (2) objectives for a reactor and fuel cycle strategy which address the technical, political, and institutional aspects of diversion and proliferation and, at the same time, satisfy the Nation's needs for efficient, timely, and economical utilization of nuclear fuel resources; (3) criteria which are responsive to these objectives and can therefore be used to screen proposed reactor and fuel cycle strategies; and (4) a rationale for these criteria

Final Technical Report for Award DESC0011912, "Trimodal Tapping Mode Atomic Force Microscopy: Simultaneous 4D Mapping of Conservative and Dissipative Probe-Sample Interactions of Energy-Relevant Materials”

Energy Technology Data Exchange (ETDEWEB)

Solares, Santiago D. [George Washington Univ., Washington, DC (United States)

2017-09-22

The final project report covering the period 7/1/14-6/30/17 provides an overview of the technical accomplishments in the areas of (i) fundamental viscoelasticity, (ii) multifrequency atomic force microscopy, and (iii) characterization of energy-relevant materials with atomic force microscopy. A list of publications supported by the project is also provided.

Technical, hygiene, economic, and life cycle assessment of full-scale moving bed biofilm reactors for wastewater treatment in India.

Science.gov (United States)

Singh, Anju; Kamble, Sheetal Jaisingh; Sawant, Megha; Chakravarthy, Yogita; Kazmi, Absar; Aymerich, Enrique; Starkl, Markus; Ghangrekar, Makarand; Philip, Ligy

2018-01-01

Moving bed biofilm reactor (MBBR) is a highly effective biological treatment process applied to treat both urban and industrial wastewaters in developing countries. The present study investigated the technical performance of ten full-scale MBBR systems located across India. The biochemical oxygen demand, chemical oxygen demand, total suspended solid, pathogens, and nutrient removal efficiencies were low as compared to the values claimed in literature. Plant 1 was considered for evaluation of environmental impacts using life cycle assessment approach. CML 2 baseline 2000 methodology was adopted, in which 11 impact categories were considered. The life cycle impact assessment results revealed that the main environmental hot spot of this system was energy consumption. Additionally, two scenarios were compared: scenario 1 (direct discharge of treated effluent, i.e., no reuse) and scenario 2 (effluent reuse and tap water replacement). The results showed that scenario 2 significantly reduce the environmental impact in all the categories ultimately decreasing the environmental burden. Moreover, significant economic and environmental benefits can be obtained in scenario 2 by replacing the freshwater demand for non-potable uses. To enhance the performance of wastewater treatment plant (WWTP), there is a need to optimize energy consumption and increase wastewater collection efficiency to maximize the operating capacity of plant and minimize overall environmental footprint. It was concluded that MBBR can be a good alternative for upgrading and optimizing existing municipal wastewater treatment plants with appropriate tertiary treatment. Graphical abstract ᅟ.

The role of non-technical skills in surgery.

Science.gov (United States)

Agha, Riaz A; Fowler, Alexander J; Sevdalis, Nick

2015-12-01

Non-technical skills are of increasing importance in surgery and surgical training. A traditional focus on technical skills acquisition and competence is no longer enough for the delivery of a modern, safe surgical practice. This review discusses the importance of non-technical skills and the values that underpin successful modern surgical practice. This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care.

The role of non-technical skills in surgery

Science.gov (United States)

Agha, Riaz A.; Fowler, Alexander J.; Sevdalis, Nick

2015-01-01

Non-technical skills are of increasing importance in surgery and surgical training. A traditional focus on technical skills acquisition and competence is no longer enough for the delivery of a modern, safe surgical practice. This review discusses the importance of non-technical skills and the values that underpin successful modern surgical practice. This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care. PMID:26904193

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.

AIPM Final Report

Energy Technology Data Exchange (ETDEWEB)

John Mookken

2006-06-30

The final AIPM project report consists of six sections. Each section includes information on the original AIPM project and extension work on the high temperature design. The first section (1) provides an overview of the program and highlights the significant targets to meet at the end of the program. The next section (2) summarizes the significant technical accomplishments by the SEMIKRON AIPM team during the course of the project. Greater technical details are provided in a collection of all the quarterly reports which can be found in the appendix. Section three (3) presents some the more significant technical data collected from technology demonstrators. Section four (4) analyzes the manufacturing cost or economic aspects of producing 100,000 units/yr. Section five (5) describes the commercialization efforts of the AIPM technology into the automotive market. The last section (6) recommends follow on work that will build on the efforts and achievements of the AIPM program.

ITER technical advisory committee meeting

International Nuclear Information System (INIS)

Fujiwara, M.

2001-01-01

The 17th Meeting of the ITER Technical Advisory Committee (TAC-17) was held on February 19-22, the ITER Garching Work Site in Germany. The objective of the meeting was to review the Draft Final Design Report of ITER-FEAT and assess the ability of the self-consistent overall design both to satisfy the technical objectives previously defined and to meet the cost limitations. TAC-17 was also organized to confirm that the design and critical elements, with emphasis on the key recommendations made at previous TAC meetings, are such as to extend the confidence in starting ITER construction. It was also intended to provide the ITER Council, scheduled to meet on 27 and 28 February in Toronto, with a technical assessment and key recommendations of the above mentioned report

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

ITER EDA technical activities

International Nuclear Information System (INIS)

Aymar, R.

1998-01-01

Six years of technical work under the ITER EDA Agreement have resulted in a design which constitutes a complete description of the ITER device and of its auxiliary systems and facilities. The ITER Council commented that the Final Design Report provides the first comprehensive design of a fusion reactor based on well established physics and technology

Measuring business cycles in The Netherlands, 1815-1913: a comparison of business cycle dating methods

OpenAIRE

Bonenkamp, Jan; Jacobs, Jan; Kuper, Gerard H.

2001-01-01

This paper compares different business cycle dating methods both on theoretical and practical grounds. Weighing the pros and cons of these methods, and based on a new data set for The Netherlands in the nineteenth century, we finally recommend two preferred methods for doing further business cycle research on the economy of the Netherlands. With respect to the methods for finding turning points in the level of economic activity, the classical cycle definition, we prefer the Bry-Boschan algori...

The future of integrated coal gasification combined cycle power plants

International Nuclear Information System (INIS)

Mueller, R.; Termuehlen, H.

1991-01-01

This paper examines the future of integrated coal gasification combined cycle (IGCC) power plants as affected by various technical, economical and environmental trends in power generation. The topics of the paper include a description of natural gas-fired combined cycle power plants, IGCC plants, coal gasifier concepts, integration of gasifiers into combined cycle power plants, efficiency, environmental impacts, co-products of IGCC power plants, economics of IGCC power plants, and a review of IGCC power plant projects

Nuclear Fuel Cycle Analysis by Integrated AHP and TOPSIS Method Using an Equilibrium Model

Energy Technology Data Exchange (ETDEWEB)

Yoon, S. R. [University of Science and Technology, Daejeon (Korea, Republic of); Choi, S. Y. [UNIST, Ulju (Korea, Republic of); Koc, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Determining whether to break away from domestic conflict surrounding nuclear power and step forward for public consensus can be identified by transparent policy making considering public acceptability. In this context, deriving the best suitable nuclear fuel cycle for Korea is the key task in current situation. Assessing nuclear fuel cycle is a multicriteria decision making problem dealing with multiple interconnected issues on efficiently using natural uranium resources, securing an environment friendliness to deal with waste, obtaining the public acceptance, ensuring peaceful uses of nuclear energy, maintaining economic competitiveness compared to other electricity sources, and assessing technical feasibility of advanced nuclear energy systems. This paper performed the integrated AHP and TOPSIS analysis on three nuclear fuel cycle options against 5 different criteria including U utilization, waste management, material attractiveness, economics, and technical feasibility. The fuel cycle options analyzed in this paper are three different fuel cycle options as follows: PWR-Once through cycle(PWR-OT), PWR-MOX cycle, Pyro- SFR cycle. These fuel cycles are most likely to be adopted in the foreseeable future. Analytic Hierarchy Process (AHP) and TOPSIS (Technique for Order of Preference by Similarity to Ideal Solution). The analyzed nuclear fuel cycle options include the once-through cycle, the PWR-MOX recycle, and the Pyro-SFR recycle.

Nuclear Fuel Cycle Analysis by Integrated AHP and TOPSIS Method Using an Equilibrium Model

International Nuclear Information System (INIS)

Yoon, S. R.; Choi, S. Y.; Koc, W. I.

2015-01-01

Determining whether to break away from domestic conflict surrounding nuclear power and step forward for public consensus can be identified by transparent policy making considering public acceptability. In this context, deriving the best suitable nuclear fuel cycle for Korea is the key task in current situation. Assessing nuclear fuel cycle is a multicriteria decision making problem dealing with multiple interconnected issues on efficiently using natural uranium resources, securing an environment friendliness to deal with waste, obtaining the public acceptance, ensuring peaceful uses of nuclear energy, maintaining economic competitiveness compared to other electricity sources, and assessing technical feasibility of advanced nuclear energy systems. This paper performed the integrated AHP and TOPSIS analysis on three nuclear fuel cycle options against 5 different criteria including U utilization, waste management, material attractiveness, economics, and technical feasibility. The fuel cycle options analyzed in this paper are three different fuel cycle options as follows: PWR-Once through cycle(PWR-OT), PWR-MOX cycle, Pyro- SFR cycle. These fuel cycles are most likely to be adopted in the foreseeable future. Analytic Hierarchy Process (AHP) and TOPSIS (Technique for Order of Preference by Similarity to Ideal Solution). The analyzed nuclear fuel cycle options include the once-through cycle, the PWR-MOX recycle, and the Pyro-SFR recycle

Electric vehicle life cycle cost analysis : final research project report.

Science.gov (United States)

2017-02-01

This project compared total life cycle costs of battery electric vehicles (BEV), plug-in hybrid electric vehicles (PHEV), hybrid electric vehicles (HEV), and vehicles with internal combustion engines (ICE). The analysis considered capital and operati...

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

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.

MODELLING OF NON-ROAD TRANSIENT CYCLE

Directory of Open Access Journals (Sweden)

Martin Kotus

2013-12-01

Full Text Available The paper describes the modeling of NRTC (Non-Road Transient Cycle test procedure based on previously measured characteristics of fuel consumption, carbon monoxide (CO, carbon dioxide (CO2, hydrocarbons (HC, nitrogen oxides (NOx and particulates (PM production. It makes possible to compare the current technical condition of an internal combustion engine of an agricultural tractor with its previous state or other tractor’s engine. Based on measured characteristics, it is also possible to model any other cycle without further measurements (NRSC test procedure, cycle for specific conditions – mountain tractor, etc.. The result may thus contribute to improving the environment by reducing the production of harmful substances emitted into the air and save money due to reduced fuel consumption.

Forecasting Resource as a Method of Increasing the Security of Technical Devices

Science.gov (United States)

Cherepanov, Anatoly P.; Lyapustin, Pavel K.

2017-10-01

The article shows a method of increasing the safe operation of technical devices at various stages of the life cycle according to the proposed classification parameters of the resource by applying the model of resource prediction. The model takes into account the presence of defects, the rate of corrosion and corrosion resistance of the material, the volume of technical diagnosis, the degree of risk in case of failure or damage of technical devices. The article shows the application of the model resource of the technical device from the manufacture to the end of its service life.

INTEGRATED PYROLYSIS COMBINED CYCLE BIOMASS POWER SYSTEM CONCEPT DEFINITION

International Nuclear Information System (INIS)

Sandvig, Eric; Walling, Gary; Brown, Robert C.; Pletka, Ryan; Radlein, Desmond; Johnson, Warren

2003-01-01

Advanced power systems based on integrated gasification/combined cycles (IGCC) are often presented as a solution to the present shortcomings of biomass as fuel. Although IGCC has been technically demonstrated at full scale, it has not been adopted for commercial power generation. Part of the reason for this situation is the continuing low price for coal. However, another significant barrier to IGCC is the high level of integration of this technology: the gas output from the gasifier must be perfectly matched to the energy demand of the gas turbine cycle. We are developing an alternative to IGCC for biomass power: the integrated (fast) pyrolysis/ combined cycle (IPCC). In this system solid biomass is converted into liquid rather than gaseous fuel. This liquid fuel, called bio-oil, is a mixture of oxygenated organic compounds and water that serves as fuel for a gas turbine topping cycle. Waste heat from the gas turbine provides thermal energy to the steam turbine bottoming cycle. Advantages of the biomass-fueled IPCC system include: combined cycle efficiency exceeding 37 percent efficiency for a system as small as 7.6 MW e ; absence of high pressure thermal reactors; decoupling of fuel processing and power generation; and opportunities for recovering value-added products from the bio-oil. This report provides a technical overview of the system including pyrolyzer design, fuel clean-up strategies, pyrolysate condenser design, opportunities for recovering pyrolysis byproducts, gas turbine cycle design, and Rankine steam cycle. The report also reviews the potential biomass fuel supply in Iowa, provide and economic analysis, and present a summery of benefits from the proposed system

INTEGRATED PYROLYSIS COMBINED CYCLE BIOMASS POWER SYSTEM CONCEPT DEFINITION

Energy Technology Data Exchange (ETDEWEB)

Eric Sandvig; Gary Walling; Robert C. Brown; Ryan Pletka; Desmond Radlein; Warren Johnson

2003-03-01

Advanced power systems based on integrated gasification/combined cycles (IGCC) are often presented as a solution to the present shortcomings of biomass as fuel. Although IGCC has been technically demonstrated at full scale, it has not been adopted for commercial power generation. Part of the reason for this situation is the continuing low price for coal. However, another significant barrier to IGCC is the high level of integration of this technology: the gas output from the gasifier must be perfectly matched to the energy demand of the gas turbine cycle. We are developing an alternative to IGCC for biomass power: the integrated (fast) pyrolysis/ combined cycle (IPCC). In this system solid biomass is converted into liquid rather than gaseous fuel. This liquid fuel, called bio-oil, is a mixture of oxygenated organic compounds and water that serves as fuel for a gas turbine topping cycle. Waste heat from the gas turbine provides thermal energy to the steam turbine bottoming cycle. Advantages of the biomass-fueled IPCC system include: combined cycle efficiency exceeding 37 percent efficiency for a system as small as 7.6 MW{sub e}; absence of high pressure thermal reactors; decoupling of fuel processing and power generation; and opportunities for recovering value-added products from the bio-oil. This report provides a technical overview of the system including pyrolyzer design, fuel clean-up strategies, pyrolysate condenser design, opportunities for recovering pyrolysis byproducts, gas turbine cycle design, and Rankine steam cycle. The report also reviews the potential biomass fuel supply in Iowa, provide and economic analysis, and present a summery of benefits from the proposed system.

Technical-tactical analysis of youth olympic taekwondo combat.

Science.gov (United States)

Tornello, Francesco; Capranica, Laura; Minganti, Carlo; Chiodo, Salvatore; Condello, Giancarlo; Tessitore, Antonio

2014-04-01

The purpose of this study was to define the technical and tactical profiles of official youth taekwondo competitions played under the most recent rules of the International Taekwondo Federation. Tactical actions (i.e., attack, defense, and block), technical executions (from 1- to 4-point scores), kicking legs (i.e., front/rear and right/left), and overall technical effectiveness were investigated in relation to match outcome of semifinal and final competitions (n = 50) of youth (aged 13-14 years) black belt athletes during the Italian Taekwondo Cadet Championship. Differences (p technical exchanges showed differences (p technical executions. Winners resulted more efficient (p technical and tactical variables. In general, these findings showed that Cadets tend to adopt an offensive strategy. In considering that the adoption of the new electronic system requires athletes to execute correct technical actions to have a score assigned, coaches should emphasize the effectiveness of scoring techniques and help athletes to effectively improve their defense and counterattack capabilities.

[Indicators, variables and obstacles to the life cycle of scientific and technical information in health. Experiences of the Centro Nacional de Información y Documentación en Salud in Mexico].

Science.gov (United States)

Macías-Chapula, C A

1987-01-01

Indicators, variables and barriers to scientific and technical health information have been detected and described by CENIDS in Mexico within the life cycle of the information production model, covering the phases of: a) generation; b) institutionalization; c) maintenance/development; and d) distribution/dissemination. Emphasis is placed on the important role that play social, economic, demographic, and political factors of each developing country to conform their ideal information life cycle. After an analysis of the existing Mexican situation, and a short description of CENIDS' structure, organization, functions and services, CENIDS' short-term and mid-term projects, and suggestions for further research lines to improve the current situation in Mexico are also given.

Astrobee Periodic Technical Review (PTR) Delta 3

Science.gov (United States)

Provencher, Christopher; Smith, Marion F.; Smith, Ernest Everett; Bualat, Maria Gabriele; Barlow, Jonathan Spencer

2017-01-01

Astrobee is a free flying robot for the inside of the International Space Station (ISS). The Periodic Technical Review (PTR) delta 3 is the final design review of the system presented to stakeholders.

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.

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.

Life cycle management and assessment: approaches and visions towards sustainable manufacturing

DEFF Research Database (Denmark)

Westkämper, Engelbert; Alting, Leo; Arndt, Günther

2001-01-01

and optimizes the interaction of product design, manufacturing and life cycle activities. The goal of this approach is to protect resources and maximize effectiveness by means of life cycle assessment, product data management, technical support and, last but not least, life cycle costing. This paper shows....... Economically successful business areas can also be explored. Whether new service concepts are required, new regulations have been passed or consumer values are changing, the differences between business areas are disappearing. Life cycle management (LCM) considers the product life cycle as a whole...... the existing approaches of LCM and discusses their prospects and further development....

Technical support for open-cycle MHD program. Progress report, July--December 1978

Energy Technology Data Exchange (ETDEWEB)

Doss, E D [ed.

1979-06-01

The support program for open-cycle MHD at Argonne National Laboratory is developing the analytical tools needed to investigate the performance of the major components in the combined cycle MHD/steam power system. The analytical effort is centered on the primary components of the system that are unique to MHD and also on the integration of these analytical representations into a model of the entire power producing system. The present project activities include modeling of the combustor, MHD channel, slag separator, and high-temperature air heater. In addition, these models are combined into a complete system model, which is at present capable of carrying out optimizations of the entire system relative to either thermodynamic efficiency or cost of electrical power. Also, in support of other aspects of the open-cycle program, test plans are developed and facility and program reviews are provided upon request in support of the needs and requirements of the DOE/MHD Division.

Reprocessing in the thorium fuel cycle

International Nuclear Information System (INIS)

Merz, E.

1984-01-01

An overview of the authors personal view is presented on open questions in regard to still required research and development work for the thorium fuel cycle before its application in a technical-industrial scale may be tackled. For a better understanding, all stations of the back-end of the thorium fuel cycle are briefly illustrated and their special features discussed. They include storage and transportation measures, all steps of reprocessing, as well as the entire radioactive waste treatment. Knowledge gaps are, as far as they are obvious, identified and proposals put forward for additional worthwile investigations. (orig.) [de

Basic concepts for crew resource management and non-technical skills.

Science.gov (United States)

Flin, Rhona; Maran, Nikki

2015-03-01

In this paper, we explain the conceptual background to non-technical skills and show how they can influence job performance in anaesthesia. We then describe the taxonomy of anaesthetists' non-technical skills (ANTS) and related systems, such as ANTS-AP for anaesthetic practitioners. We discuss the training courses that have been designed to teach these non-technical skills, which are called crew resource management (CRM), crisis resource management (CRM) or crisis avoidance resource management (CARMA). Finally, we discuss the application of non-technical skills assessment systems. Copyright © 2015 Elsevier Ltd. All rights reserved.

Developing Students' Understanding of Industrially Relevant Economic and Life Cycle Assessments

Science.gov (United States)

Bode, Claudia J.; Chapman, Clint; Pennybaker, Atherly; Subramaniam, Bala

2017-01-01

Training future leaders to understand life cycle assessment data is critical for effective research, business, and sociopolitical decision-making. However, the technical nature of these life cycle reports often makes them challenging for students and other nonexperts to comprehend. Therefore, we outline here the key takeaways from recent economic…

Fuel cycle management in Finland

International Nuclear Information System (INIS)

Vaeyrynen, H.; Mikkola, I.

1987-01-01

Both Finnish utilities producing nuclear power - Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (Industrial Power Co. Ltd, TVO) - have created efficient fuel cycle management systems. The systems however differ in almost all respects. The reason is that the principal supplier for IVO is the Soviet Union and for TVO is Sweden. A common feature of both systems at the front end of the cycle is the building of stockpiles in order to provide for interruptions in fuel deliveries. Quality assurance supervision at the fuel factory for IVO is regulated by the Soviet Chamber of Commerce and Industry and a final control is made in Finland. The in-core fuel management is done by IVO using codes developed in Finland. The whole IVO fuel cycle is basically a leasing arrangement. The spent fuel is returned to the USSR after five years cooling. TVO carries out the in-core fuel management using a computer code system supplied by Asea-Atom. TVO is responsable for the back end of the cycle and makes preparations for the final disposal of the spent fuel in Finland. 6 refs., 2 figs

A new data architecture for advancing life cycle assessment

Science.gov (United States)

IntroductionLife cycle assessment (LCA) has a technical architecture that limits data interoperability, transparency, and automated integration of external data. More advanced information technologies offer promise for increasing the ease with which information can be synthesized...

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.

Comparative analysis of concentrating solar power and photovoltaic technologies: Technical and environmental evaluations

International Nuclear Information System (INIS)

Desideri, U.; Zepparelli, F.; Morettini, V.; Garroni, E.

2013-01-01

Highlights: ► Life cycle was assessed for both concentrated solar power and photovoltaic systems. ► The PV plant has a higher environmental impact than the CSP plant. ► The Global Warming Potential is lower for the CSP than for the PV plant. ► The energy payback time is lower for the CSP than for the PV plant. -- Abstract: Solar energy is an important alternative energy source to fossil fuels and theoretically the most available energy source on the earth. Solar energy can be converted into electric energy by using two different processes: by means of thermodynamic cycles and the photovoltaic conversion. Solar thermal technologies, sometimes called thermodynamic solar technologies, operating at medium (about 500 °C) and high temperatures (about 1000 °C), have recently attracted a renewed interest and have become one of the most promising alternatives in the field of solar energy utilization. Photovoltaic conversion is very interesting, although still quite expensive, because of the absence of moving components and the reduced operating and management costs. The main objectives of the present work are: •to carry out comparative technical evaluations on the amount of electricity produced by two hypothetical plants, located on the same site, for which a preliminary design was made: a solar thermal power plant with parabolic trough collectors and a photovoltaic plant with a single-axis tracking system; •to carry out a comparative analysis of the environmental impact derived from the processes of electricity generation during the whole life cycle of the two hypothetical power plants. First a technical comparison between the two plants was made assuming that they have the same nominal electric power and then the same total covered surface. The methodology chosen to evaluate the environmental impact associated with the power plants is the Life Cycle Assessment (LCA). It allows to analyze all the phases of the life cycle of the plants, from the extraction of

Performance Estimation of Organic Rankine Cycle by Using Soft Computing Technics

Directory of Open Access Journals (Sweden)

Tuğba Kovacı

2017-10-01

Full Text Available In this study, the thermal efficiency values of Organic Rankine cycle system were estimated depending on the condenser temperature and the evaporator temperatures values by adaptive network fuzzy interference system (ANFIS and artificial neural networks system (ANN. Organic Rankine cycle (ORC fluids of R365-mfc and SES32 were chosen to evaluate as the system fluid. The performance values of ANN and ANFIS models are compared with actual values. The R2 values are determined between 0.97 and 0.99 for SES36 and R365-mfc, and this is satisfactory. Although it was observed that both ANN and ANFIS models obtained a good statistical prediction performance through coefficient of determination variance, the accuracies of ANN predictions were usually imperceptible better than those of ANFIS predictions.

Sustainable Building Life Cycle Design

Directory of Open Access Journals (Sweden)

Ginzburg Alexander

2016-01-01

Full Text Available The current building life cycle management system in the Russian Federation is a family of discrete subsystems that exist independently for different building life cycle stages. In this situation building reliability and sustainable functioning are out of the question. The implementation of a united information model (BIM-model intended to describe building entire life cycle will allow to raise the sustainability, but this will happen only if goals and concerns of all participants of the project process are properly coordinated. An important figure of process sustainability is the organizational and technological reliability (OTR that describes the possibility of a system to reach a goal. In case of building life cycle design, the economical efficiency of a building can be considered as the goal. The required technical, ecological, organizational, and other parameters form a complex of constraints that determine the area of allowable values for building functioning. In its broad meaning, OTR may be understood as the probability of receiving an economical effect based on the value of organizational and economical reliability (OER.

Contemporaneous assembly of Western Gondwana and final Rodinia break-up: Implications for the supercontinent cycle

Directory of Open Access Journals (Sweden)

Sebastián Oriolo

2017-11-01

Full Text Available Geological, geochronological and isotopic data are integrated in order to present a revised model for the Neoproterozoic evolution of Western Gondwana. Although the classical geodynamic scenario assumed for the period 800–700 Ma is related to Rodinia break-up and the consequent opening of major oceanic basins, a significantly different tectonic evolution can be inferred for most Western Gondwana cratons. These cratons occupied a marginal position in the southern hemisphere with respect to Rodinia and recorded subduction with back-arc extension, island arc development and limited formation of oceanic crust in internal oceans. This period was thus characterized by increased crustal growth in Western Gondwana, resulting from addition of juvenile continental crust along convergent margins. In contrast, crustal reworking and metacratonization were dominant during the subsequent assembly of Gondwana. The Río de la Plata, Congo-São Francisco, West African and Amazonian cratons collided at ca. 630–600 Ma along the West Gondwana Orogen. These events overlap in time with the onset of the opening of the Iapetus Ocean at ca. 610–600 Ma, which gave rise to the separation of Baltica, Laurentia and Amazonia and resulted from the final Rodinia break-up. The East African/Antarctic Orogen recorded the subsequent amalgamation of Western and Eastern Gondwana after ca. 580 Ma, contemporaneously with the beginning of subduction in the Terra Australis Orogen along the southern Gondwana margin. However, the Kalahari Craton was lately incorporated during the Late Ediacaran–Early Cambrian. The proposed Gondwana evolution rules out the existence of Pannotia, as the final Gondwana amalgamation postdates latest connections between Laurentia and Amazonia. Additionally, a combination of introversion and extroversion is proposed for the assembly of Gondwana. The contemporaneous record of final Rodinia break-up and Gondwana assembly has major implications for the

ITER technical basis

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-01-01

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

ITER technical basis

International Nuclear Information System (INIS)

2002-01-01

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

Nuclear fuel cycle: international market, international constraints and international cooperation

International Nuclear Information System (INIS)

Imai, R.

1977-01-01

Some of the constraints on the nuclear fuel cycle are ones arising from economic and financial reasons, those caused by uranium resources and their distribution, those arising from technical reasons, issues of public acceptance, and those quite independent of normal industrial considerations, but caused by elements of international politics. The nuclear fuel cycle and the international market, matters of nuclear non-proliferation, and international cooperation are discussed

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.

Exergy Losses in the Szewalski Binary Vapor Cycle

Directory of Open Access Journals (Sweden)

Tomasz Kowalczyk

2015-10-01

Full Text Available In this publication, we present an energy and exergy analysis of the Szewalski binary vapor cycle based on a model of a supercritical steam power plant. We used energy analysis to conduct a preliminary optimization of the cycle. Exergy loss analysis was employed to perform a comparison of heat-transfer processes, which are essential for hierarchical cycles. The Szewalski binary vapor cycle consists of a steam cycle bottomed with an organic Rankine cycle installation. This coupling has a negative influence on the thermal efficiency of the cycle. However, the primary aim of this modification is to reduce the size of the power unit by decreasing the low-pressure steam turbine cylinder and the steam condenser. The reduction of the “cold end” of the turbine is desirable from economic and technical standpoints. We present the Szewalski binary vapor cycle in addition to a mathematical model of the chosen power plant’s thermodynamic cycle. We elaborate on the procedure of the Szewalski cycle design and its optimization in order to attain an optimal size reduction of the power unit and limit exergy loss.

Technical considerations in decisions on plutonium use

International Nuclear Information System (INIS)

Till, C.E.

1980-01-01

Present-day reactors use uranium inefficiently. Really substantial increases in efficiency of uranium utilization require reprocessing. Reprocessing activities give rise to concern about their possible use in fission weapons acquisition. The basic properties of nuclides severely limit both the number of alternative ways that fuel utilization can be improved and the amount of the improvement that is possible from any of the alternatives. By far the greatest improvement comes from plutonium use in a fast reactor. The properties that allow this are peculiar to plutonium. There are basically only two fuel cycles that can be considered as alternatives to the plutonium-238/uranium fuel cycle. One is a uranium-233/thorium fuel cycle, a cycle that is very similar in requirements, including reprocessing, to the plutonium-238/uranium cycle. The other is continuation and refinement of the current once-through cycle. A small number of technical measures to increase proliferation-resistance have been proposed. Improvements of an institutional nature are of two types. The first are improvements in international safeguards - most importantly, nuclear materials accountancy - essentially strengthening or augmenting current IAEA procedures. The second involves agreements between nations to limit distribution of sensitive technologies and to multinationalize or internationalize sensitive elements of the fuel cycle

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 ...

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.

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.

System study of alternative waste management techniques: Final report

International Nuclear Information System (INIS)

1986-01-01

This report summarizes the important results achieved in conjunction with the Research and Development Priority ''Alternative Waste Management Techniques'' sponsored by the Federal Ministry of Research and Technology from 1981 to 1984. The subject of these studies was solely ''direct disposal'' of spent fuel elements. For this purpose a reference concept was selected from a variety of possible processes and engineered in detailed form by firms in the nuclear industry. Those who worked on the engineering concepts consider this waste management method technically feasible. Several disposal casks have been fabricated. The basic licensability of direct disposal can be evaluated on the basis of the documentation developed by the companies. The direct disposal method was compared with the ''integrated waste management concept'' using reference fuel cycles with respect to the following criteria: radiological safety and nuclear material safeguards and, in addition, economic and energy-policy aspects. It was found that with respect to radiological safety, including the long-term safety of the final repository, there are no significant differences between the two fuel cycles with and without reprocessing. With respect to the nuclear material safeguards of a final repository containing spent fuel elements, there are still a number of unanswered questions. From an economic standpoint, direct disposal will be more economical in the foreseeable future than integrated waste management. Quantification of the effects of one or the other waste management method on the national economy is not necessarily possible. Reprocessing is supported primarily by technological and energy-policy considerations. On the basis of the results, the conclusion is reached that reprocessing should be pursued further, but that at the same time direct disposal should be developed to the point of practical maturity

76 FR 4645 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

Science.gov (United States)

2011-01-26

... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Department...: This notice announces a meeting of the Hydrogen and Fuel Cell Technical Advisory Committee (HTAC). HTAC... Agenda: (Subject to change; updates will be posted on http://hydrogen.energy.gov and copies of the final...

76 FR 60478 - Hydrogen and Fuel Cell Technical Advisory Committee (HTAC)

Science.gov (United States)

2011-09-29

... DEPARTMENT OF ENERGY Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) AGENCY: Department...: The Hydrogen and Fuel Cell Technical Advisory Committee (HTAC) was established under section 807 of... website at: http://hydrogen.energy.gov and copies of the final agenda will available the date of the...

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

A resource guide to nuclear plant life-cycle management

International Nuclear Information System (INIS)

Negin, C.A.; Klein, D.J.

1993-11-01

Forecasting the useful economic life of a nuclear unit and addressing the complementary issue of license renewal, both key elements of life cycle management, are complex undertakings. This guide is a resource document emphasizing the technical elements of life cycle management (LCM) with focus on the determination of adequate maintenance programs and the identification of data and records necessary to support them. Information on other life cycle management issues, such as license renewal regulation, is also provided. Because of the volume of information required for LCM evaluations and the need for periodic updating, this Guide is presented as an updatable ''electronic book.''

Technical specifications and performance of CANDU fuel

International Nuclear Information System (INIS)

Sejnoha, R.

1997-01-01

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

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

Theory of Technical Systems--Educational Tool for Engineering

Science.gov (United States)

Eder, Wolfgang Ernst

2016-01-01

Hubka's theory of technical systems (TTS) is briefly outlined. It describes commonalities in all engineering devices, whatever their physical principles of action. This theory is based on a general transformation system (TrfS), which can be used to show engineering in the contexts of society, economics and historic developments. The life cycle of…

Review of the IAEA nuclear fuel cycle and material section activities connected with nuclear fuel including WWER fuel

International Nuclear Information System (INIS)

Sokolov, F.

2001-01-01

Program activities on Nuclear Fuel Cycle and Materials cover the areas of: 1) raw materials (B.1.01); 2) fuel performance and technology (B.1.02); 3) pent fuel (B.1.03); 4) fuel cycle issues and information system (B.1.04); 5) support to technical cooperation activities (B.1.05). The IAEA activities in fuel performance and technology in 2001 include organization of the fuel experts meetings and completion of the Co-ordinate Research Projects (CRP). The special attention is given to the advanced post-irradiation examination techniques for water reactor fuel and fuel behavior under transients and LOCA conditions. An international research program on modeling of activity transfer in primary circuit of NPP is finalized in 2001. A new CRP on fuel modeling at extended burnup (FUMEX II) has planed to be carried out during the period 2002-2006. In the area of spent fuel management the implementation of burnup credit (BUC) in spent fuel management systems has motivated to be used in criticality safety applications, based on economic consideration. An overview of spent fuel storage policy accounting new fuel features as higher enrichment and final burnup, usage of MOX fuel and prolongation of the term of spent fuel storage is also given

Comments on fuel cycle concepts and impacts on nonproliferation and safeguards concerns

International Nuclear Information System (INIS)

Persiani, P.J.

1997-01-01

Fuel cycle technologies have inherently differing levels of proliferation risk profiles. Institutional and/or multi-national arrangements have been effective in reducing the proliferation risk concerns. The implementation of international safeguards further reduces the proliferation risk concerns by the timely detection of a possible physical diversion of SNM from fuel cycle facilities. Fuel cycles are safeguardable, but the proliferation risk characteristics of fuel cycles concepts differ significantly with consequent impacts on the international level of technical safeguards measures. The paper comments on proliferation characteristics of some of the fuel cycle concepts for the purpose of exploring development of advanced nonproliferation and safeguards measures

The role of non-technical skills in surgery

Directory of Open Access Journals (Sweden)

Riaz A. Agha

2015-12-01

This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care.

Non-proliferation and safeguards aspects of alternative fuel cycle concepts

International Nuclear Information System (INIS)

Persiani, P.J.

1997-01-01

Timely visibility on the development, evaluation and optimization of fuel cycle concepts with respect to nonproliferation characteristics should be emphasized in the early stage of planning a civilian nuclear power program, by fuel cycle developers, reviewers and decision makers. Fuel cycle technologies have inherently differing levels of nonproliferation characteristic profiles. Institutional and/or multi-national arrangements have been effective in reducing the nonproliferation concerns. The implementation of international safeguards further reduces these concerns by the timely detection of a possible physical diversion of SNM from fuel cycle facilities. Fuel cycles are safeguardable, but the nonproliferation characteristics of fuel cycle concepts differ significantly with consequent impacts on the international level of technical safeguards measures. The paper comments on characteristics of some of the fuel cycle concepts for the purpose of exploring the need to develop advanced nonproliferation and safeguards measures. (author)

Performance of PZT stacks under high-field electric cycling at various temperatures in heavy-duty diesel engine fuel injectors

Science.gov (United States)

Wang, Hong; Lee, Sung-Min; Lin, Hua-Tay; Stafford, Randy

2016-04-01

Testing and characterization of large prototype lead zirconate titanate (PZT) stacks present substantial technical challenges to electronic systems. The work in this study shows that an alternative approach can be pursued by using subunits extracted from prototype stacks. Piezoelectric and dielectric integrity was maintained even though the PZT plate specimens experienced an additional loading process involved with the extraction after factory poling. Extracted 10-layer plate specimens were studied by an electric cycle test under an electric field of 3.0/0.0 kV/mm, 100 Hz to 108 cycles, both at room temperature (22°C) and at 50°C. The elevated temperature had a defined impact on the fatigue of PZT stacks. About 48 and 28% reductions were observed in the piezoelectric and dielectric coefficients, respectively, after 108 cycles at 50°C, compared with reductions of 25 and 15% in the respective coefficients at 22°C. At the same time, the loss tangent varied to a limited extent. The evolution of PZT-electrode interfacial layers or nearby dielectric layers should account for the difference in the fatigue rates of piezoelectric and dielectric coefficients. But the basic contribution to observed fatigue may result from the buildup of a bias field that finally suppressed the motion of the domain walls. Finally, monitoring of dielectric coefficients can be an effective tool for on-line lifetime prediction of PZT stacks in service if a failure criterion is defined properly.

Criteria for proliferation resistance of nuclear fuel cycle options

International Nuclear Information System (INIS)

Kiriyama, Eriko; Pickett, Susan; Suzuki, Tatsujiro

2000-01-01

In order to understand the concept of nuclear proliferation resistance, this paper examines the technical definitions of proliferation resistance. Although nuclear proliferation resistance is often included as one of the major goals of advanced reactor research and development, the criteria for nuclear proliferation resistance of nuclear fuel cycles is not defined clearly. The implied meaning of proliferation resistance was compared in proposals regarding the nuclear fuel cycle. Discrepancies amongst the proposals regarding the technical definition of proliferation resistance is found. While all these proposals indicate proliferation resistance, few clearly spell out exactly what criteria they are measuring themselves against. However we found there are also common feature in many proposals. They are; (1) Reduction of Pu, (2) Less separated Weapon Usable Materials, (3) Fewer steps, (4) Barrier for Weapon Usable Materials. Recognizing that there are numerous political and infrastructure measures that may also be taken to guard against proliferation risks, we have focused here on the definition of proliferation resistance in terms of technical characteristics. Another important conclusion is that in many proposals proliferation resistance is only one of the important criteria such as energy security, economical efficiency, and safety. (author)

ECONOMICS AND FEASIBILITY OF RANKINE CYCLE IMPROVEMENTS FOR COAL FIRED POWER PLANTS

Energy Technology Data Exchange (ETDEWEB)

Richard E. Waryasz; Gregory N. Liljedahl

2004-09-08

ALSTOM Power Inc.'s Power Plant Laboratories (ALSTOM) has teamed with the U.S. Department of Energy National Energy Technology Laboratory (DOE NETL), American Electric Company (AEP) and Parsons Energy and Chemical Group to conduct a comprehensive study evaluating coal fired steam power plants, known as Rankine Cycles, equipped with three different combustion systems: Pulverized Coal (PC), Circulating Fluidized Bed (CFB), and Circulating Moving Bed (CMB{trademark}). Five steam cycles utilizing a wide range of steam conditions were used with these combustion systems. The motivation for this study was to establish through engineering analysis, the most cost-effective performance potential available through improvement in the Rankine Cycle steam conditions and combustion systems while at the same time ensuring that the most stringent emission performance based on CURC (Coal Utilization Research Council) 2010 targets are met: > 98% sulfur removal; < 0.05 lbm/MM-Btu NO{sub x}; < 0.01 lbm/MM-Btu Particulate Matter; and > 90% Hg removal. The final report discusses the results of a coal fired steam power plant project, which is comprised of two parts. The main part of the study is the analysis of ten (10) Greenfield steam power plants employing three different coal combustion technologies: Pulverized Coal (PC), Circulating Fluidized Bed (CFB), and Circulating Moving Bed (CMB{trademark}) integrated with five different steam cycles. The study explores the technical feasibility, thermal performance, environmental performance, and economic viability of ten power plants that could be deployed currently, in the near, intermediate, and long-term time frame. For the five steam cycles, main steam temperatures vary from 1,000 F to 1,292 F and pressures from 2,400 psi to 5,075 psi. Reheat steam temperatures vary from 1,000 F to 1,328 F. The number of feedwater heaters varies from 7 to 9 and the associated feedwater temperature varies from 500 F to 626 F. The main part of the

Potential health and environmental impacts attributable to the nuclear and coal fuel cycles: Final report

International Nuclear Information System (INIS)

Gotchy, R.L.

1987-06-01

Estimates of mortality and morbidity are presented based on present-day knowledge of health effects resulting from current component designs and operations of the nuclear and coal fuel cycles, and anticipated emission rates and occupational exposure for the various fuel cycle facilities expected to go into operation during the next decade. The author concluded that, although there are large uncertainties in the estimates of potential health effects, the coal fuel cycle alternative has a greater health impact on man than the uranium fuel fycle. However, the increased risk of health effects for either fuel cycle represents a very small incremental risk to the average individual in the public for the balance of this century. The potential for large impacts exists in both fuel cycles, but the potential impacts associated with a runaway Greenhouse Effect from combustion of fossil fuels, such as coal, cannot yet be reasonably quantified. Some of the potential environmental impacts of the coal fuel cycle cannot currently be realistically estimated, but those that can appear greater than those from the nuclear fuel cycle. 103 refs., 1 fig., 18 tabs

Technical evaluation of biomass gasification technology integrated with combined cycle using bagasse as fuel; Avaliacao tecnica da tecnologia de gaseificacao de biomassa integrada a ciclos combinados utilizando bagaco como combustivel

Energy Technology Data Exchange (ETDEWEB)

Ortiz, Pablo Silva; Venturini, Osvaldo Jose; Lora, Electo Silva [Universidade Federal de Itajuba (NEST/UNIFEI), MG (Brazil). Nucleo de Excelencia em Geracao Termeletrica e Distribuida], email: pablo.silvaortiz@gmail.com; Campo, Andres Perez [Universidade Automona de Bucaramanga (UNAB) (Colombia). Fac. de Engenharia Fisico- Mecanica, Engenharia em Energia

2010-07-01

Biomass Integrated Gasification Combined Cycle (BIGCC) was identified as an advanced technology with potential to be competitive for electricity generation. The BIGCC technology uses biomass and the sub products of some industrial sectors processing, like sugar cane, as feedstock. The current Brazilian energy matrix is mainly based on renewable generation sources, making it important to assess these gasification technologies in the production of sugar, ethanol and electricity. In this work, a technical evaluation of the technologies incorporated in BIGCC power plants is done: the gasification process and the combined cycle power plant. On the other hand, the generated costs of these systems are analyzed, and the potential for implementation in Brazil plants from sugar cane bagasse is studied, in which a 10% increase in efficiency is obtained. (author)

Scientific and Technical Report, 1997

International Nuclear Information System (INIS)

Metivier, Henri; Mur, Emmanuelle

1998-01-01

This report highlights the most significant scientific and technical achievements of the Institute of Nuclear Protection and Safety in 1997. In all 23 reports are grouped in the following 7 sections: 1.Reactor safety; 2.Safety of nuclear facility; 3.Safeguards for radioactive materials and transports; 4.Public protection; 5.Environment protection; 6.Radioactive waste safety; 7.Crisis management. Special attention is paid to the pressurized water and fast neutron reactors and, accordingly, the program PHEBUS PF and the first results obtained with it concerning nuclear safety are reported. The safety of nuclear fuel cycle and spent fuel storage is addressed in a couple of reports, as well as the problem of inspection, measurement and containers for nuclear materials. Concerning the public and environment protection, studies are reported on medical surveillance of people working with CEA Group, and clinical dosimetric follow-up of radiological events as well as the strategy of contaminated site rehabilitation. In the field of radioactive waste management, the IPSN project of Tournemire tunnel and the project of deep disposal are presented. Finally, the issue of major nuclear accidents is approached through the exercise Becquerel, the SESAME system of predicting the radioactive products release in PWR reactors and ASTRAL, the evaluation system of aftermath of an accidental environmental contamination by radioactive release. Each section of this IPSN report is opened by a review paper

Evaluation of effects of different fuel cycles in environment

International Nuclear Information System (INIS)

1979-03-01

The paper discusses the risks for personnel and environment caused by different steps of FBR-Fuel cycle. For FBRS the most important factor of exposure is the fabrication of fuel elements but technical development is capable to reduce this factor

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.

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

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

Technical writing versus technical writing

Science.gov (United States)

Dillingham, J. W.

1981-01-01

Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

Technical procedures for utilities and solid waste: Environmental Field Program, Deaf Smith County site, Texas: Final draft

International Nuclear Information System (INIS)

1987-08-01

The evaluation of environmental issues and concerns and the addressing of statutory requirements are fundamental parts in the characterization of the site in Deaf Smith County, Texas for the US Department of Energy's Salt Repository Project (SRP). To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Utilities and Solid Waste considerations. This technical procedure (TP) has been developed to implement the field program described in the Utilities and Solid Waste Site Study Plan. The purpose and scope of the Utilities and Solid Waste Technical Procedure is to develop and implement a data collection procedure to fulfill the data base needs of the Utilities and Solid Waste SSP. The procedure describes a method of obtaining, assessing and verifying the capabilities of the regional service utilities and disposal contractors. This data base can be used to identify a preferred service source for the engineering contractor. The technical procedure was produced under the guidelines established in Technical Administrative Procedure No. 1.0, Preparation, Review and Approval of Technical Procedures

Technical study report on fuel fabrication system

International Nuclear Information System (INIS)

Kono, Shusaku; Tanaka, Kenya; Ono, Kiyoshi; Iwasa, Katsuyoshi; Hoshino, Yasushi; Shinkai, Yasuo

2000-07-01

The feasibility study of FBR and related fuel cycle is performed for developing the FBR recycle system which ensures safety, economic competitiveness, efficient utilization of resources, reduction of environmental burden and enhancement of nuclear non-proliferation under consistency of FBR reactor and fuel cycle systems. In this study, a conceptual design study and system characteristics evaluation are conducted for fuel fabrication systems of pellet process, vibropack process for oxide and nitride fuel and casting process for metal fuel. Technical issues in each process are also extracted. In 1999 fiscal year, a conceptual design study were conducted for the fuel fabrication plants adopting (1) the short pellet process which simplifies the conventional MOX pellet fabrication processes, (2) vibropack processes of aqueous gelation process, improved RIAR process, improved ANL process and fluoride volatility process, (3) casting processes of injection process, centrifuging process. As a result, attainable perspective was obtained for each fuel fabrication system through the evaluation of apparatuses, layout and facility volume, etc. In each fuel fabrication system, technical issues for practical use were made clear. Hereafter, more detailed study will be performed for each system, and research programs for phase II study will be planned. (author)

KBS Technical report 1-120 (1977-1978). Summaries

International Nuclear Information System (INIS)

1979-05-01

The Swedish nuclear utilities started early in 1977 the KBS (nuclear fuel safety) project to study the high level waste problem and report on how and where a safe final storage could be arranged in Sweden. The docummentation produced by the project during 1977 and 1978 has been collected in a series of technical reports numbered from 1 to 120. The English summaries of the technical reports have been collected in this separate volume, No. 121. (G.B.)

Specified radioactive waste final disposal act

International Nuclear Information System (INIS)

Yasui, Masaya

2001-01-01

Radioactive wastes must be finally and safely disposed far from human activities. Disposal act is a long-range task and needs to be understood and accepted by public for site selection. This paper explains basic policy of Japanese Government for final disposal act of specified radioactive wastes, examination for site selection guidelines to promote residential understanding, general concept of multi-barrier system for isolating the specific radioactive wastes, and research and technical development for radioactive waste management. (S. Ohno)

LEU and thorium fuel cycles for the high temperature reactor (once-through and recycle)

International Nuclear Information System (INIS)

1978-09-01

Sets of performance parameters, optimised for minimum costs within the bounds of current technical confidence, are presented for each of the four fuel cycle variants mentioned in the title. The overall cost of the HEU once-through system is found to be significantly more expensive than the other three which are similar. Data are presented on fissile material utilisation, on the isotopic composition of discharged fuel, and on fuel cycle costs. Comments are made on technical status, development needs, safety, environmental concerns including the storage and disposal of irradiated fuel, and on characteristics relevant to proliferation control

Fuel cycles of WWER-1000 based on assemblies with increased fuel mass

International Nuclear Information System (INIS)

Kosourov, E.; Pavlovichev, A.; Shcherenko, A.

2011-01-01

Modern WWER-1000 fuel cycles are based on FAs with the fuel column height of 3680 mm, diameters of the fuel pellet and its central hole of 7.6 and 1.2 mm respectively. The highest possible fuel enrichment has reached its license limit that is 4.95 %. Research in the field of modernization, safety justification and licensing of equipment for fuel manufacture, storage and transportation are required for further fuel enrichment increase (above 5 %). So in the nearest future an improvement of technical and economic characteristics of fuel cycles is possible if assembly fuel mass is increased. The available technology of the cladding thinning makes it possible. If the fuel rod outer diameter is constant and the clad inner diameter is increased to 7.93 mm, the diameter of the fuel pellet can be increased to 7.8 mm. So the suppression of the pellet central hole allows increasing assembly fuel weight by about 8 %. In this paper we analyze how technical and economic characteristics of WWER-1000 fuel cycle change when an advanced FA is applied instead of standard one. Comparison is made between FAs with equal time interval between refueling. This method of comparison makes it possible to eliminate the parameters that constitute the operation component of electricity generation cost, taking into account only the following technical and economic characteristics: 1)cycle length; 2) average burnup of spent FAs; 3) specific natural uranium consumption; 4)specific quantity of separative work units; 5) specific enriched uranium consumption; 6) specific assembly consumption. Collected data allow estimating the efficiency of assembly fuel weight increase and verifying fuel cycle characteristics that may be obtained in the advanced FAs. (authors)

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

ORIGEN-based Nuclear Fuel Inventory Module for Fuel Cycle Assessment: Final Project Report

Energy Technology Data Exchange (ETDEWEB)

Skutnik, Steven E. [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Nuclear Engineering

2017-06-19

The goal of this project, “ORIGEN-based Nuclear Fuel Depletion Module for Fuel Cycle Assessment" is to create a physics-based reactor depletion and decay module for the Cyclus nuclear fuel cycle simulator in order to assess nuclear fuel inventories over a broad space of reactor operating conditions. The overall goal of this approach is to facilitate evaluations of nuclear fuel inventories for a broad space of scenarios, including extended used nuclear fuel storage and cascading impacts on fuel cycle options such as actinide recovery in used nuclear fuel, particularly for multiple recycle scenarios. The advantages of a physics-based approach (compared to a recipe-based approach which has been typically employed for fuel cycle simulators) is in its inherent flexibility; such an approach can more readily accommodate the broad space of potential isotopic vectors that may be encountered under advanced fuel cycle options. In order to develop this flexible reactor analysis capability, we are leveraging the Origen nuclear fuel depletion and decay module from SCALE to produce a standalone “depletion engine” which will serve as the kernel of a Cyclus-based reactor analysis module. The ORIGEN depletion module is a rigorously benchmarked and extensively validated tool for nuclear fuel analysis and thus its incorporation into the Cyclus framework can bring these capabilities to bear on the problem of evaluating long-term impacts of fuel cycle option choices on relevant metrics of interest, including materials inventories and availability (for multiple recycle scenarios), long-term waste management and repository impacts, etc. Developing this Origen-based analysis capability for Cyclus requires the refinement of the Origen analysis sequence to the point where it can reasonably be compiled as a standalone sequence outside of SCALE; i.e., wherein all of the computational aspects of Origen (including reactor cross-section library processing and interpolation, input and output

Raft River binary-cycle geothermal pilot power plant final report

Energy Technology Data Exchange (ETDEWEB)

Bliem, C.J.; Walrath, L.F.

1983-04-01

The design and performance of a 5-MW(e) binary-cycle pilot power plant that used a moderate-temperature hydrothermal resource, with isobutane as a working fluid, are examined. Operating problems experienced and solutions found are discussed and recommendations are made for improvements to future power plant designs. The plant and individual systems are analyzed for design specification versus actual performance figures.

Final Report: Modifications and Optimization of the Organic Rankine Cycle to Improve the Recovery of Waste Heat

Energy Technology Data Exchange (ETDEWEB)

Guillen, Donna Post [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zia, Jalal [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2013-09-01

This research and development (R&D) project exemplifies a shared public private commitment to advance the development of energy efficient industrial technologies that will reduce the U.S. dependence upon foreign oil, provide energy savings and reduce greenhouse gas emissions. The purpose of this project was to develop and demonstrate a Direct Evaporator for the Organic Rankine Cycle (ORC) for the conversion of waste heat from gas turbine exhaust to electricity. In conventional ORCs, the heat from the exhaust stream is transferred indirectly to a hydrocarbon based working fluid by means of an intermediate thermal oil loop. The Direct Evaporator accomplishes preheating, evaporation and superheating of the working fluid by a heat exchanger placed within the exhaust gas stream. Direct Evaporation is simpler and up to 15% less expensive than conventional ORCs, since the secondary oil loop and associated equipment can be eliminated. However, in the past, Direct Evaporation has been avoided due to technical challenges imposed by decomposition and flammability of the working fluid. The purpose of this project was to retire key risks and overcome the technical barriers to implementing an ORC with Direct Evaporation. R&D was conducted through a partnership between the Idaho National Laboratory (INL) and General Electric (GE) Global Research Center (GRC). The project consisted of four research tasks: (1) Detailed Design & Modeling of the ORC Direct Evaporator, (2) Design and Construction of Partial Prototype Direct Evaporator Test Facility, (3) Working Fluid Decomposition Chemical Analyses, and (4) Prototype Evaluation. Issues pertinent to the selection of an ORC working fluid, along with thermodynamic and design considerations of the direct evaporator, were identified. The FMEA (Failure modes and effects analysis) and HAZOP (Hazards and operability analysis) safety studies performed to mitigate risks are described, followed by a discussion of the flammability analysis of the

Engine cycle design considerations for nuclear thermal propulsion systems

International Nuclear Information System (INIS)

Pelaccio, D.G.; Scheil, C.M.; Collins, J.T.

1993-01-01

A top-level study was performed which addresses nuclear thermal propulsion system engine cycle options and their applicability to support future Space Exploration Initiative manned lunar and Mars missions. Technical and development issues associated with expander, gas generator, and bleed cycle near-term, solid core nuclear thermal propulsion engines are identified and examined. In addition to performance and weight the influence of the engine cycle type on key design selection parameters such as design complexity, reliability, development time, and cost are discussed. Representative engine designs are presented and compared. Their applicability and performance impact on typical near-term lunar and Mars missions are shown

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…

Nuclear Fuel Cycle Evaluation and Real Options

Directory of Open Access Journals (Sweden)

L. Havlíček

2008-01-01

Full Text Available The first part of this paper describes the nuclear fuel cycle. It is divided into three parts. The first part, called Front-End, covers all activities connected with fuel procurement and fabrication. The middle part of the cycle includes fuel reload design activities and the operation of the fuel in the reactor. Back-End comprises all activities ensuring safe separation of spent fuel and radioactive waste from the environment. The individual stages of the fuel cycle are strongly interrelated. Overall economic optimization is very difficult. Generally, NPV is used for an economic evaluation in the nuclear fuel cycle. However the high volatility of uranium prices in the Front-End, and the large uncertainty of both economic and technical parameters in the Back-End, make the use of NPV difficult. The real option method is able to evaluate the value added by flexibility of decision making by a company under conditions of uncertainty. The possibility of applying this method to the nuclear fuel cycle evaluation is studied. 

Technic and economic viability study on exploitation of lunar 3He resource

International Nuclear Information System (INIS)

Deng Baiquan

1995-01-01

From the energetics point of view, the technic and economic viability study on exploitation of lunar 3 He for fuelling the fusion reactor burning D- 3 He has been carried out. This study is divided into the following sections: analysis of solar wind parameters and estimation of potential quantity 3 He in the lunar regolith, the cost evaluation of mining He of lunar soil; the energy cost calculation of He extraction by vacuum heating degassing during lunar day, the cost calculation of cryogenic isotopic separation 3 He/ 4 He during the lunar night, the energy cost for earth/moon transportation of liquid 3 He, the energy payback calculation of fusion power burning 3 He based lunar source, and finally the comparison of the energy multiplication with that for 235 U production of nuclear fuel and for coal mining. The comparisons of cost of electricity between D- 3 He and D-T fuel cycle for different reactor types have been discussed

Influence of admission marks on the academic performance of technical architecture students

OpenAIRE

Gaspar Fàbregas, Kàtia; Núñez Andrés, María Amparo; Rodríguez Jordana, Juan; Jordana Riba, Francisco de Paula

2016-01-01

Traditionally, students from higher training cycle and upper secondary school education access higher technical education with a wide range of access marks in each group. The purpose of this article is to analyse how students’ backgrounds and access marks really influence their success in the first academic year and further evolution to obtain the degree of Technical Architecture. To achieve this aim, the progress of students from different backgrounds was analysed for three acade...

Temporal discounting in life cycle assessment: A critical review and theoretical framework

International Nuclear Information System (INIS)

Yuan, Chris; Wang, Endong; Zhai, Qiang; Yang, Fan

2015-01-01

Temporal homogeneity of inventory data is one of the major problems in life cycle assessment (LCA). Addressing temporal homogeneity of life cycle inventory data is important in reducing the uncertainties and improving the reliability of LCA results. This paper attempts to present a critical review and discussion on the fundamental issues of temporal homogeneity in conventional LCA and propose a theoretical framework for temporal discounting in LCA. Theoretical perspectives for temporal discounting in life cycle inventory analysis are discussed first based on the key elements of a scientific mechanism for temporal discounting. Then generic procedures for performing temporal discounting in LCA is derived and proposed based on the nature of the LCA method and the identified key elements of a scientific temporal discounting method. A five-step framework is proposed and reported in details based on the technical methods and procedures needed to perform a temporal discounting in life cycle inventory analysis. Challenges and possible solutions are also identified and discussed for the technical procedure and scientific accomplishment of each step within the framework. - Highlights: • A critical review for temporal homogeneity problem of life cycle inventory data • A theoretical framework for performing temporal discounting on inventory data • Methods provided to accomplish each step of the temporal discounting framework

Present condition of survey research on actualization strategy of fast breeding reactor (FBR) cycling. General outlines on the research

International Nuclear Information System (INIS)

Hara, Hideaki

2001-01-01

The Japan Nuclear Cycle Development Institute (JNC) started the survey research on actualization strategy of FBR cycling under cooperation of related organizations such as electric business company and so on, on July, 1999. The research aims at preparation of technical system to establish the FBR cycling for a future main energy supply source by extracting an actualization picture maximum activated advantages originally haven by the FBR cycling and by proposing a developmental strategy flexibly responsible to diverse needs in future society. Here was reported on effort state of its phase 1 (two years between 1999 and 2000 fiscal years). In the phase 1, it was planned to perform research and development shown as follows: 1) Extraction of actualization candidate concept on the FBR cycling under a premise of safety security and a viewpoint of evaluation on economics, resource effective usage, environmental loading reduction, and nuclear dispersion resistance by conducting investigation and evaluation of wide technical choices adopting innovative techniques, and 2) Embodiment of a research and development program of phase 2 (from 2001 to 2005 fiscal years) by investigating some technical subjects important for selection of research and development program aiming at actualization and its candidate concept on the FBR cycling. (G.K.)

Human Resource Development for Uranium Production Cycle

International Nuclear Information System (INIS)

Ganguly, C.

2014-01-01

Concluding Remarks & Suggestions: • HRD will be one of the major challenges in the expanding nuclear power program in countries like China and India. • China and India get uranium raw material from domestic mines and international market. In addition, China has overseas uranium property. India is also exploring the possibility of overseas Joint Venture and uranium properties. For uranium production cycle there is a need for trained geologist, mining engineers, chemical and mechanical engineers. • There is a need for introducing specialization course on “uranium production cycle” at post graduate levels in government and private universities. Overseas Utilities and private firms in India engaged in nuclear power and fuel cycle activities may like to sponsor MTech students with assurance of employment after the successful completion of the course. • The IAEA may consider to extend Technical Assistance to universities in HRD in nuclear power and fuel cycle in general and uranium production cycle in particular - IAEA workshops, with participation of international experts, on uranium geology, mining, milling and safety and best practices in uranium production cycle will be of great help. • The IAEA – UPSAT could play an important role in HRD in uranium production cycle

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

Chapter 10. Multinational and international controls. Paper 17. A preliminary evaluation of the technical aspects of INFCE

International Nuclear Information System (INIS)

Farinelli, U.

1979-01-01

The International Nuclear Fuel Cycle Evaluation (INFCE) has not generated any very new idea in terms of reactors or fuel cycles. Its very subdivision into working groups, which for the most part represent the traditional subdivisions of the fuel cycle, and the absence of a full-time international working team for the evaluation, have been obstacles in this direction. Moreover, evaluation based on studies and extrapolations has very little ultimate value; a realistic assessment requires such a detailed analysis that it can only be performed on small variations of present systems. Proliferation characteristics of various fuel cycles have proven more difficult to evaluate than was previously thought. First, proliferation is mainly a short-term issue, and not many solutions are applicable within this time horizon (20 or 25 years); second, traditional criteria to classify proliferation resistance have become less rigid at closer scrutiny; and finally, it is difficult to assess the effectiveness of technical antiproliferation measures without considering the political actions attached to them. The result is that the two basic strategies of the USA (based on the once-through fuel cycle in light water reactors and postponing decisions on more advanced solutions) and of Western Europe and Japan (based on fuel reprocessing and early deployment of fast breeders) have remained the only realistic options under discussion. However, changes are taking place in each strategy to make the one less wasteful of fuel and the other more protected for proliferation, and it is reasonable to suppose that they will be able to co-exist in the future. (author)

International nuclear fuel cycle fact book

International Nuclear Information System (INIS)

1992-09-01

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R ampersand D programs and key personnel on 23 countries, including the US, four multi-national agencies, and 21 nuclear societies. The Fact Book is organized as follows: National summaries-a section for each country which summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies-a section for each of the international agencies which has significant fuel cycle involvement and a listing of nuclear societies. Glossary-a list of abbreviations/acronyms of organizations, facilities, technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter presented from the perspective of the Fact Book user in the United States

Mechanical design and first experimental results of an upgraded technical PERMCAT reactor for tritium recovery in the fuel cycle of a fusion machine

Energy Technology Data Exchange (ETDEWEB)

Welte, S., E-mail: stefan.welte@kit.edu [Karlsruhe Institute of Technology (KIT), Forschungszentrum Karlsruhe, Institute for Technical Physics, Tritium Laboratory Karlsruhe, Hermann v. Helmholtz Platz 1, 76344 Eggenstein Leopoldshafen (Germany); Demange, D.; Wagner, R. [Karlsruhe Institute of Technology (KIT), Forschungszentrum Karlsruhe, Institute for Technical Physics, Tritium Laboratory Karlsruhe, Hermann v. Helmholtz Platz 1, 76344 Eggenstein Leopoldshafen (Germany)

2010-12-15

The PERMCAT process developed for the final clean-up stage of the Tokamak Exhaust Processing systems of the ITER tritium plant combines a catalytic reactor and a Pd/Ag permeator in a single component. A first generation technical PERMCAT has been successfully operated as part of the CAPER experiment at the Tritium Laboratory Karlsruhe for several years. Various alternative PERMCAT mechanical designs were proposed and studied on small-scale prototypes. An upgraded technical PERMCAT reactor was designed, manufactured and commissioned with deuterium. A parallel arrangement of finger-type membranes inserted in a single catalyst bed design was chosen to simplify the geometry and the manufacturing while improving the robustness of the reactor. The component has been designed and manufactured to be fully tritium compatible and also fully compatible with both process and electrical connections of the previous PERMCAT to be replaced. The new PERMCAT mechanical design is more compact and easy to manufacture. This PERMCAT reactor was submitted to functional tests and experiments based on isotopic exchanges between H{sub 2}O and D{sub 2} to measure the processing performances. The first experimental results show decontamination factors versus flow rates better than all previously measured.

Mechanical design and first experimental results of an upgraded technical PERMCAT reactor for tritium recovery in the fuel cycle of a fusion machine

International Nuclear Information System (INIS)

Welte, S.; Demange, D.; Wagner, R.

2010-01-01

The PERMCAT process developed for the final clean-up stage of the Tokamak Exhaust Processing systems of the ITER tritium plant combines a catalytic reactor and a Pd/Ag permeator in a single component. A first generation technical PERMCAT has been successfully operated as part of the CAPER experiment at the Tritium Laboratory Karlsruhe for several years. Various alternative PERMCAT mechanical designs were proposed and studied on small-scale prototypes. An upgraded technical PERMCAT reactor was designed, manufactured and commissioned with deuterium. A parallel arrangement of finger-type membranes inserted in a single catalyst bed design was chosen to simplify the geometry and the manufacturing while improving the robustness of the reactor. The component has been designed and manufactured to be fully tritium compatible and also fully compatible with both process and electrical connections of the previous PERMCAT to be replaced. The new PERMCAT mechanical design is more compact and easy to manufacture. This PERMCAT reactor was submitted to functional tests and experiments based on isotopic exchanges between H 2 O and D 2 to measure the processing performances. The first experimental results show decontamination factors versus flow rates better than all previously measured.

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)

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

State variable participation in the limit cycle of induction motor

Indian Academy of Sciences (India)

State variable participation in the limit cycle of induction ... 2National Institute of Technical Teachers' Training and Research, Kolkata 700 106, India ..... the phase plot shown in figure 10 would be very useful as it shows infinite loops, meaning.

77 FR 42637 - Navigation and Navigable Waters; Technical, Organizational, and Conforming Amendments; Corrections

Science.gov (United States)

2012-07-20

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Parts 84 and 115 [Docket No. USCG-2012-0306] RIN 1625-AB86 Navigation and Navigable Waters; Technical, Organizational, and Conforming Amendments...), the Coast Guard published a final rule entitled ``Navigation and Navigable Waters; Technical...

Nuclear fuel cycle assessment of India: A technical study for U.S.-India cooperation

Science.gov (United States)

Krishna, Taraknath Woddi Venkat

The recent civil nuclear cooperation proposed by the Bush Administration and the Government of India has heightened the necessity of assessing India's nuclear fuel cycle inclusive of nuclear materials and facilities. This agreement proposes to change the long-standing U.S. policy of preventing the spread of nuclear weapons by denying nuclear technology transfer to non-NPT signatory states. The nuclear tests in 1998 have convinced the world community that India would never relinquish its nuclear arsenal. This has driven the desire to engage India through civilian nuclear cooperation. The cornerstone of any civilian nuclear technological support necessitates the separation of military and civilian facilities. A complete nuclear fuel cycle assessment of India emphasizes the entwinment of the military and civilian facilities and would aid in moving forward with the separation plan. To estimate the existing uranium reserves in India, a complete historical assessment of ore production, conversion, and processing capabilities was performed using open source information and compared to independent reports. Nuclear energy and plutonium production (reactor- and weapons-grade) was simulated using declared capacity factors and modern simulation tools. The three-stage nuclear power program entities and all the components of civilian and military significance were assembled into a flowsheet to allow for a macroscopic vision of the Indian fuel cycle. A detailed view of the nuclear fuel cycle opens avenues for technological collaboration. The fuel cycle that grows from this study exploits domestic thorium reserves with advanced international technology and optimized for the existing system. To utilize any appreciable fraction of the world's supply of thorium, nuclear breeding is necessary. The two known possibilities for production of more fissionable material in the reactor than is consumed as fuel are fast breeders or thermal breeders. This dissertation analyzes a thermal

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.

Vapor cycle energy system for implantable circulatory assist devices. Final summary May--Oct 1976

International Nuclear Information System (INIS)

Watelet, R.P.; Ruggles, A.E.; Hagen, K.G.

1977-03-01

The report describes the development status of a heart assist system driven by a nuclear-fueled, electronically controlled vapor cycle engine termed the tidal regenerator engine (TRE). The TRE pressurization is controlled by a torque motor coupled to a displacer. The electrical power for the sensor, electronic logic and actuator is provided by thermoelectric modules interposed between the engine superheater and boiler. The TRE is direct-coupled to an assist blood pump which also acts as a blood-cooled heat exchanger, pressure-volume trasformer and sensor for the electronic logic. Engine cycle efficiency in excess of 14% has been demonstrated routinely. Overall system efficiency on 33 watts of over 9% has been demonstrated (implied 13% engine cycle efficiency). A binary version of this engine in the annular configuration is now being tested. The preliminary tests demonstrated 10% cycle efficiency on the first buildup which ran well and started easily

Validation of a new version of software for monitoring the core of nuclear power plant of Laguna Verde Unit 2, at the end of Cycle 10; Validacion de una nueva version del software para monitoreo del nucleo de la Central Laguna Verde Unidad 2, al final del Ciclo 10

Energy Technology Data Exchange (ETDEWEB)

Hernandez, G.; Calleros, G.; Mata, F. [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)], e-mail: gabriel.hernandez05@cfe.gob.mx

2009-10-15

This work shows the differences observed in thermal limits established in the technical specifications of operation, among the new software, installed at the end of Cycle 10 of Unit 2 of nuclear power plant of Laguna Verde, and the old software that was installed from the beginning of the cycle. The methodology allowed to validate the new software during the coast down stage, before finishing the cycle, for what could be used as tool during the shutdown of Unit 2 at the end of Cycle 10. (Author)

Final Technical Report for Quantum Embedding for Correlated Electronic Structure in Large Systems and the Condensed Phase

Energy Technology Data Exchange (ETDEWEB)

Chan, Garnet Kin-Lic [Princeton Univ., NJ (United States)

2017-04-30

This is the final technical report. We briefly describe some selected results below. Developments in density matrix embedding. DMET is a quantum embedding theory that we introduced at the beginning of the last funding period, around 2012-2013. Since the first DMET papers, which demonstrated proof-of- principle calculations on the Hubbard model and hydrogen rings, we have carried out a number of different developments, including: Extending the DMET technology to compute broken symmetry phases, including magnetic phases and super- conductivity (Pub. 13); Calibrating the accuracy of DMET and its cluster size convergence against other methods, and formulation of a dynamical cluster analog (Pubs. 4, 10) (see Fig. 1); Implementing DMET for ab-initio molecular calculations, and exploring different self-consistency criteria (Pubs. 9, 14); Using embedding to defi ne quantum classical interfaces Pub. 2; Formulating DMET for spectral functions (Pub. 7) (see Fig. 1); Extending DMET to coupled fermion-boson problems (Pub. 12). Together with these embedding developments, we have also implemented a wide variety of impurity solvers within our DMET framework, including DMRG (Pub. 3), AFQMC (Pub. 10), and coupled cluster theory (CC) (Pub. 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.

Spectral shift controlled reactors, denatured U-233/thorium cycle

International Nuclear Information System (INIS)

1978-05-01

This paper presents technical and economic data on the SSCR which may be of use in the International Fuel Cycle Evaluation Program to intercompare alternative nuclear systems. Included in this paper are data on the denatured U-233/thorium cycle. This cycle shows a proliferation advantage over more classical thorium fuel cycle (e.g., highly-enriched U-235/thorium or plutonium/thorium) due to the elimination of chemically-separable, concentrated fissile material from unirradiated nuclear fuel. The U-233 is denatured by mixing with depleted uranium to a concentration no greater than 12 w/o. An exogenous source of U-233 is assumed in this paper, since U-233 does not occur in nature and only a limited supply has been produced to date for research and development work

Pseudo-simple heteroclinic cycles in R4

Science.gov (United States)

Chossat, Pascal; Lohse, Alexander; Podvigina, Olga

2018-06-01

We study pseudo-simple heteroclinic cycles for a Γ-equivariant system in R4 with finite Γ ⊂ O(4) , and their nearby dynamics. In particular, in a first step towards a full classification - analogous to that which exists already for the class of simple cycles - we identify all finite subgroups of O(4) admitting pseudo-simple cycles. To this end we introduce a constructive method to build equivariant dynamical systems possessing a robust heteroclinic cycle. Extending a previous study we also investigate the existence of periodic orbits close to a pseudo-simple cycle, which depends on the symmetry groups of equilibria in the cycle. Moreover, we identify subgroups Γ ⊂ O(4) , Γ ⊄ SO(4) , admitting fragmentarily asymptotically stable pseudo-simple heteroclinic cycles. (It has been previously shown that for Γ ⊂ SO(4) pseudo-simple cycles generically are completely unstable.) Finally, we study a generalized heteroclinic cycle, which involves a pseudo-simple cycle as a subset.

MONITORED GEOLOGIC REPOSITORY LIFE CYCLE COST ESTIMATE ASSUMPTIONS DOCUMENT

International Nuclear Information System (INIS)

R.E. Sweeney

2001-01-01

The purpose of this assumptions document is to provide general scope, strategy, technical basis, schedule and cost assumptions for the Monitored Geologic Repository (MGR) life cycle cost (LCC) estimate and schedule update incorporating information from the Viability Assessment (VA) , License Application Design Selection (LADS), 1999 Update to the Total System Life Cycle Cost (TSLCC) estimate and from other related and updated information. This document is intended to generally follow the assumptions outlined in the previous MGR cost estimates and as further prescribed by DOE guidance

Monitored Geologic Repository Life Cycle Cost Estimate Assumptions Document

International Nuclear Information System (INIS)

Sweeney, R.

2000-01-01

The purpose of this assumptions document is to provide general scope, strategy, technical basis, schedule and cost assumptions for the Monitored Geologic Repository (MGR) life cycle cost estimate and schedule update incorporating information from the Viability Assessment (VA), License Application Design Selection (LADS), 1999 Update to the Total System Life Cycle Cost (TSLCC) estimate and from other related and updated information. This document is intended to generally follow the assumptions outlined in the previous MGR cost estimates and as further prescribed by DOE guidance

TCR as supervisor of technical systems

CERN Document Server

Laeger, H

1998-01-01

Our Technical Control Room (TCR) provides continuous supervision of CERN's technical infrastructure. It also serves the inhabitants of CERN's premises as a contact point in case of problems. Every year we initiate eleven thousand recorded corrective interventions; about half subsequent to user phone calls, the other half to automatic alarms. TCR tasks are essentially fourfold: collect and distribute information on abnormal operation states; supervise those technical systems for which we have a mandate; initiate corrective interventions; and perform corrective on-site interventions outside normal working hours. A TCR operator normally has an education corresponding to a French BTS and initially little professional experience. He holds short-term contracts, up to a maximum of six years. This paper outlines TCR tasks and presents some statistical data. It also indicates relations between users, equipment groups, contract firms and the TCR as go-between. Finally, it gives an account of our seven years experience ...

The role of spent fuel test facilities in the fuel cycle strategy

International Nuclear Information System (INIS)

Huang, S. T.; Gross, D. L.; Snyder, N. W.; Woods, W. D.

1988-01-01

Disposal of commercial spent nuclear fuels in the major industrialized countries may be categorized into two broad approaches: a once-through policy which will dispose of spent fuels and recycle fissile materials. Within reprocess spent fuels and recycle fissile materials. Within each policy, various technical, licensing, institutional and public issues exist. These issues tend to complicate the formulation of an effective and acceptable fuel cycle strategy which will meet various cost, schedule, and legislative constraints. This paper examines overall fuel cycle strategies from the viewpoint of these underlying technical issues and assesses the roles of spent fuel test facilities in the overall fuel cycles steps. Basic functions of such test facilities are also discussed. The main emphasis is placed on the once-through policy although the reprocessing / recycle policy is also discussed. Benefits of utilizing test facilities in the fuel cycle strategies are explored. The results indicate that substantial benefits may be obtained in terms of minimizing programmatic risks, increasing public confidence, and more effective utilization of overall budgetary resources by structuring and highlighting the test facilities as an important element in the overall strategy

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.

Technical bid evaluation

International Nuclear Information System (INIS)

Bruchhausen, E. v.

1975-01-01

It is shown which kind of problems arise for the owners of the project and what is the recommendable method of approach. A detailed description of the necessary working team, information in delegation of work and tasks of procedure, criteria of valuation and classification method. Examples of schemes are shown which are the basis of the technical bid evaluation: tables 'data of system/component' and 'scope of supply'. The procedure of normalization of the bids and of specifying the owners supplies are explained. The content of the final report is described. (HP) [de

Job and task analysis for technical staff

International Nuclear Information System (INIS)

Toline, B.C.

1991-01-01

In September of 1989 Cooper Nuclear Station began a project to upgrade the Technical Staff Training Program. This project's roots began by performing job and Task Analysis for Technical Staff. While the industry has long been committed to Job and Task Analysis to target performance based instruction for single job positions, this approach was unique in that it was not originally considered appropriate for a group as diverse as Tech Staff. Much to his satisfaction the Job and Task Analysis Project was much less complicated for Technical Staff than the author had imagined. The benefits of performing the Job and Task Analysis for Technical Staff have become increasingly obvious as he pursues lesson plan development and course revisions. The outline for this presentation will be as follows: philosophy adopted; preparation of the job survey document; performing the job analysis; performing task analysis for technical staff and associated pitfalls; clustering objectives for training and comparison to existing program; benefits now and in the future; final phase (comparison to INPO guides and meeting the needs of non-degreed engineering professionals); and conclusion. By focusing on performance based needs for engineers rather than traditional academics for training the author is confident the future Technical Staff Program will meet the challenges ahead and will exceed requirements for accreditation

Evaluation of spectral shift controlled reactors operating on the uranium fuel cycle. Final report

International Nuclear Information System (INIS)

Matzie, R.A.; Sider, F.M.

1979-08-01

The performance of the spectral shift controlled reactor (SSCR) operating on uranium fuel cycles was evaluated and compared with the conventional pressurized water reactor (PWR). In order to analyze the SSCR, the PSR design methodology was extended to include systems moderated by mixtures of light water and heavy water and these methods were validated by comparison with experimental results. Once the design methods had been formulated, the resouce requirements and power costs were determined for the uranium-fueled SSCR. The ore requirements of the UO 2 once-through fuel cycle and the UO 2 fuel cycle with self-generated recycle (SGR) of plutonium were found to be 10% and 19% less than those of similarly fueled PWRs, respectively. A fuel cycle optimization study was performed for the UO 2 once-through SSCR and the SGR SSCR. By individually altering lattice parameters, discharge exposure or number of in-core batches, savings of less than 8% in resource requirements and less than 1% in power costs were obtained

Size of the coming solar cycle 24 based on Ohl's Precursor Method, final estimate

Directory of Open Access Journals (Sweden)

R. P. Kane

2010-07-01

Full Text Available In Ohl's Precursor Method (Ohl, 1966, 1976, the geomagnetic activity during the declining phase of a sunspot cycle is shown to be well correlated with the size (maximum sunspot number Rz(max of the next cycle. For solar cycle 24, Kane (2007a used aa(min=15.5 (12-month running mean, which occurred during March–May of 2006 and made a preliminary estimate Rz(max=124±26 (12-month running mean. However, in the next few months, the aa index first increased and then decreased to a new low value of 14.8 in July 2007. With this new low value, the prediction was Rz(max=117±26 (12-month running mean. However, even this proved a false signal. Since then, the aa values have decreased considerably and the last 12-monthly value is 8.7, centered at May 2009. For solar cycle 24, using aa(min=8.7, the latest prediction is, Rz(max=58.0±25.0.

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.

In pile AISI 316L. Low cycle fatigue. Final report

International Nuclear Information System (INIS)

Van Nieuwenhove, R.; Moons, F.

1994-12-01

In pile testing of the effect of neutron irradiation on the fatigue life of the reference material AISI 316L was performed in the framework of the European fusion technology program. The overall programme, carried out at SCK CEN (Mol,Belgium), exists of two instrumented rigs for low cycle fatigue testing, which were consecutively loaded in the BR-2 reactor during periods Jan (94) June (94) and Aug (94)-Dec(94). In each experiment, two identical samples were loaded by means of a pneumatically driven system. The samples were instrumented with thermocouples, strain gages, linear variable displacement transducers, and activation monitors. The experimental conditions are given. Type of fatigue test: load controlled, symmetric, uniaxial, triangular wave shape; stress range: about 580 MPa; sample shape: hourglass, diameter 3.2 mm, radius 12.5 mm; environment: NaK (peritectic); temperature: 250 C; maximum dpa value up to fracture: 1.7. Two of four samples were broken (one in each experiment) after having experienced 17 419 respectively 11 870 stress cycles. These new data points confirm earlier results from pile fatigue tests: irradiation causes no degradation of fatigue life of AISI 316L steel, at least for the parameters corresponding to these experiments

Spatio-temporal structure and cycle to cycle variations of an in-cylinder tumbling flow

Science.gov (United States)

Voisine, M.; Thomas, L.; Borée, J.; Rey, P.

2011-05-01

The aim of this paper is to make use of PIV and high-speed PIV in a research engine of moderate tumbling ratio in order to analyze both the spatial structure of the flow and its temporal evolution during series of consecutive cycles. Appropriate analyzing tools are introduced, and four different points are addressed: (1) the chain of events driving the generation of the three-dimensional mean tumbling motion is investigated; (2) a Lagrangian analysis of the roll-up of the tumbling jet in individual cycles demonstrates a strong cycle to cycle variation during the compression phase (the rms of the position of the jet front being approximately 10% of the piston stroke); (3) focussing on the "breakdown" phase, phase invariant proper orthogonal decomposition enables us to distinguish cycles according to their structure near top dead center (TDC). We show that when the coherent energy of the flow is conserved, there is no increase in the fluctuating kinetic energy; (4) finally, the phase-averaged Reynolds stresses is decomposed into a contribution of the in-cycle coherence and the turbulence carried by the flow states. Approximately 30% of the fluctuating kinetic energy is due to cycle to cycle fluctuations in this chamber near TDC.

CEEM Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

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

2014-11-26

concentrating photovoltaic applications thathave substantially higher efficiency than single substrate cells made of elemental semiconductors such as silicon. This task required the development of new cell bonding methods with excellent coupling of both photons and electrons between the sub-cells. To accomplish this, we developed (1) GaInN solar cells with enhanced performance by using quantum-well absorbers and front-surface optical texturing, (2) a hybrid "pillar-array" bond which uses an array of metal pillars for electrical coupling, and (3) a "hybrid moth-eye" optical coating which combines the benefits of nano-imprinted moth-eye coatings and traditional multilayer coatings. The technical effectiveness was assessed by measurement of the photovoltaic efficiency of solar cells made using these techniques; the ultrahigh efficiencies targeted by this work are of compelling economic value for concentrating photovoltaics.

Measurable Control System Security through Ideal Driven Technical Metrics

Energy Technology Data Exchange (ETDEWEB)

Miles McQueen; Wayne Boyer; Sean McBride; Marie Farrar; Zachary Tudor

2008-01-01

The Department of Homeland Security National Cyber Security Division supported development of a small set of security ideals as a framework to establish measurable control systems security. Based on these ideals, a draft set of proposed technical metrics was developed to allow control systems owner-operators to track improvements or degradations in their individual control systems security posture. The technical metrics development effort included review and evaluation of over thirty metrics-related documents. On the bases of complexity, ambiguity, or misleading and distorting effects the metrics identified during the reviews were determined to be weaker than necessary to aid defense against the myriad threats posed by cyber-terrorism to human safety, as well as to economic prosperity. Using the results of our metrics review and the set of security ideals as a starting point for metrics development, we identified thirteen potential technical metrics - with at least one metric supporting each ideal. Two case study applications of the ideals and thirteen metrics to control systems were then performed to establish potential difficulties in applying both the ideals and the metrics. The case studies resulted in no changes to the ideals, and only a few deletions and refinements to the thirteen potential metrics. This led to a final proposed set of ten core technical metrics. To further validate the security ideals, the modifications made to the original thirteen potential metrics, and the final proposed set of ten core metrics, seven separate control systems security assessments performed over the past three years were reviewed for findings and recommended mitigations. These findings and mitigations were then mapped to the security ideals and metrics to assess gaps in their coverage. The mappings indicated that there are no gaps in the security ideals and that the ten core technical metrics provide significant coverage of standard security issues with 87% coverage. Based

Study of visualized simulation and analysis of nuclear fuel cycle system based on multilevel flow model

Institute of Scientific and Technical Information of China (English)

LIU Jing-Quan; YOSHIKAWA Hidekazu; ZHOU Yang-Ping

2005-01-01

Complex energy and environment system, especially nuclear fuel cycle system recently raised social concerns about the issues of economic competitiveness, environmental effect and nuclear proliferation. Only under the condition that those conflicting issues are gotten a consensus between stakeholders with different knowledge background, can nuclear power industry be continuingly developed. In this paper, a new analysis platform has been developed to help stakeholders to recognize and analyze various socio-technical issues in the nuclear fuel cycle system based on the functional modeling method named Multilevel Flow Models (MFM) according to the cognition theory of human being. Its character is that MFM models define a set of mass, energy and information flow structures on multiple levels of abstraction to describe the functional structure of a process system and its graphical symbol representation and the means-end and part-whole hierarchical flow structure to make the represented process easy to be understood. Based upon this methodology, a micro-process and a macro-process of nuclear fuel cycle system were selected to be simulated and some analysis processes such as economics analysis, environmental analysis and energy balance analysis related to those flows were also integrated to help stakeholders to understand the process of decision-making with the introduction of some new functions for the improved Multilevel Flow Models Studio, and finally the simple simulation such as spent fuel management process simulation and money flow of nuclear fuel cycle and its levelised cost analysis will be represented as feasible examples.

Economic Reform Orchestra And Technical Manpower Development ...

African Journals Online (AJOL)

The study examined economic reform issues in Nigeria since 1986 and the impact on technical manpower development in Rivers State in particular. Two sets of structured questionnaire were used to elicit responses from target respondents who ultimately comprised 105 instructors and 340 final year students in the four ...

Current technical issues in international safeguards

International Nuclear Information System (INIS)

Bennett, C.A.

1977-01-01

Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

IT logistics support life cycle of products in air engine

Directory of Open Access Journals (Sweden)

М.С. Кулик

2009-02-01

Full Text Available  Questions of increase of efficiency of a supply with information of creation and support in operation of modern aviation engines are considered. The revealed most perspective directions of development of complex systems of support of life cycle aviation technics.

[Review comments on the Draft DOE Area Recommendation Report for the Crystalline Repository Project]: Final technical report

International Nuclear Information System (INIS)

Dutch, S.I.; Stiegliltz, R.D.

1986-03-01

Research performed under the grant primarily involved review and comment on the Draft Area Recommendations Report (DARR). However, because data and ''recommendations'' included in the DARR are unquestionably tied to years of research and dozens of technical reports and documents, i.e., Screening Methodologies, Regional characterization Reports, etc., it is essential that consultants to the Menominee Tribe review all the relevant DOE documents, working papers, etc. Given the short period provided for technical comment and limited funds available to the Tribe, a well designed and thorough technical review was (and is) without question impossible. What review and comment that did occur on a geotechnical level is included in this report

Life Cycle Management at Brødrene Hartmann A/S - strategy,- organisation and implementation

DEFF Research Database (Denmark)

Pedersen, Claus Stig; Alting, Leo; Mortensen, Anna Lise

1997-01-01

decisionmaking is under development.The implementation of life cycle management in Hartmann is organised with respect to the divisional areas: strategic management, product development, purchase, production, sale and distribution. The implementation of life cycle managment is assisted by tools to support...... decision making. The tools are developed in coorporation with the Department of Manufacturing Engineering at the Technical University of Denmark.This paper presents- The Hartmann environmental strategy, based on the life cycle concept- Experiences and results from developing a life cycle orientated...... organisation- Experiences and results from developing and implementing tools for life cycle management...

Current status of feasibility studies on commercialized fuel cycle system for Fast Breeder Reactor

International Nuclear Information System (INIS)

Ojima, Hisao; Nagaoki, Yoshihiro

2000-01-01

A 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' is underway at the Japan Nuclear Cycle Development Institute (JNC). The study will select the promising concepts with their R and D tasks in order to commercialize the fast breeder reactor (FBR) cycle system. The feasibility studies (F/S) have to present surveyed and screened various relevant technologies, and defined the design requirement of the commercialized fuel cycle system for FBR. The promising technical options are being evaluated and conceptual designs are being examined. At the end of JFY2000, several candidate concepts of the commercialized FBR cycle system will be proposed. (author)

Improved Barriers to Turbine Engine Fragments: Final Annual Report

National Research Council Canada - National Science Library

Shockey, Donald

2002-01-01

This final annual technical report describes the progress rnade during year 4 of the SPI International Phase II effort to develop a computational capability for designing lightweight fragment barriers...

How to be an Effective Technical Writer?

Directory of Open Access Journals (Sweden)

M Solaiman Ali

2012-07-01

(patterns of organization of information to suit the technical writing task, checking for technical accuracy and following three levels of editing to help increase the readability of a technical text. Finally, in part 8 (Ethical/legal considerations for the technical writer, the authors suggest ways for the technical writer to overcome ethical/legal dilemmas on the job.

Final Scientific/Technical Report for Low Cost, High Capacity Non- Intercalation Chemistry Automotive Cells

Energy Technology Data Exchange (ETDEWEB)

Berdichevsky, Gene [Sila Nanotechnologies, Inc., Alameda, CA (United States)

2017-09-08

Commercial Li-ion batteries typically use Ni- and Co-based intercalation cathodes. As the demand for improved performance from batteries increases, these cathode materials will no longer be able to provide the desired energy storage characteristics since they are currently approaching their theoretical limits. Conversion cathode materials are prime candidates for improvement of Li-ion batteries. On both a volumetric and gravimetric basis they have higher theoretical capacity than intercalation cathode materials. Metal fluoride (MFx) cathodes offer higher specific energy density and dramatically higher volumetric energy density. Challenges associated with metal fluoride cathodes were addressed through nanostructured material design and synthesis. A major goal of this project was to develop and demonstrate Li-ion cells based on Si-comprising anodes and metal fluoride (MFx) comprising cathodes. Pairing the high-capacity MFx cathode with a high-capacity anode, such as an alloying Si anode, allows for the highest possible energy density on a cell level. After facing and overcoming multiple material synthesis and electrochemical instability challenges, we succeeded in fabrication of MFx half cells with cycle stability in excess of 500 cycles (to 20% or smaller degradation) and full cells with MFx-based cathodes and Si-based anodes with cycle stability in excess of 200 cycles (to 20% or smaller degradation).

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

Review of the IAEA Nuclear Fuel Cycle Materials Section activities related to WWER fuel

International Nuclear Information System (INIS)

Killeen, J.

2003-01-01

The IAEA Nuclear Fuel Cycle Programme, designated as Programme B, has the main objective of supporting Member States in policy making, strategic planning, developing technology and addressing issues with respect to safe, reliable, economically efficient, proliferation resistant and environmentally sound nuclear fuel cycle. This paper is concentrated on describing the work within Sub-programme B.2 'Fuel Performance and Technology'. Two Technical Working Groups assist in the preparation of the IAEA programme in the nuclear fuel cycle area - Technical Working Group on Water Reactor Fuel Performance and Technology and Technical Working Group on Nuclear Fuel Cycle Options. The activities of the Unit within the Nuclear Fuel Cycle and Materials Section working on Fuel Performance and Technology are given, based on the sub-programme structure of the Agency programme and budget for 2002-2003. Within the framework of Co-ordinated Research Projects a study of the delayed hydride cracking (DHC) of the zirconium alloys used in pressurised heavy water reactors (PHWR) involving 10 countries has been completed. It achieved very effective transfer of know-how at the laboratory level in three technologically important areas: 1) Controlled hydriding of samples to predetermined levels; 2) Accurate measurement of hydrogen concentrations at the relatively low levels found in pressure tubes and RBMK channel tubes; and 3) In the determination of DHC rates under various conditions of temperature and stress. A new project has been started on the 'Improvement of Models used for Fuel Behaviour Simulation' (FUMEX II) to assist Member States in improving the predictive capabilities of computer codes used in modelling fuel behaviour for extended burnup. The IAEA also collaborates with organisations in the Member States to support activities and meetings on nuclear fuel cycle related topics