WorldWideScience

Sample records for fuel program preliminary

  1. Fabrication of preliminary fuel rods for SFR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sun Ki; Oh, Seok Jin; Ko, Young Mo; Woo, Youn Myung; Kim, Ki Hwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Metal fuels was selected for fueling many of the first reactors in the US, including the Experimental Breeder Reactor-I (EBR-I) and the Experimental Breeder Reactor-II (EBR-II) in Idaho, the FERMI-I reactor, and the Dounreay Fast Reactor (DFR) in the UK. Metallic U.Pu.Zr alloys were the reference fuel for the US Integral Fast Reactor (IFR) program. Metallic fuel has advantages such as simple fabrication procedures, good neutron economy, high thermal conductivity, excellent compatibility with a Na coolant and inherent passive safety. U-Zr-Pu alloy fuels have been used for SFR (sodium-cooled fast reactor) related to the closed fuel cycle for managing minor actinides and reducing a high radioactivity levels since the 1980s. Fabrication technology of metallic fuel for SFR has been in development in Korea as a national nuclear R and D program since 2007. For the final goal of SFR fuel rod fabrication with good performance, recently, three preliminary fuel rods were fabricated. In this paper, the preliminary fuel rods were fabricated, and then the inspection for QC(quality control) of the fuel rods was performed

  2. Preliminary waste acceptance criteria for the ICPP spent fuel and waste management technology development program

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, L.L.; Shikashio, R.

    1993-09-01

    The purpose of this document is to identify requirements to be met by the Producer/Shipper of Spent Nuclear Fuel/High-LeveL Waste SNF/HLW in order for DOE to be able to accept the packaged materials. This includes defining both standard and nonstandard waste forms.

  3. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR {section}261.4(a)(4), ``Identification and Listing of Hazardous Waste,`` as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues.

  4. Fuel Cell Demonstration Program

    Energy Technology Data Exchange (ETDEWEB)

    Gerald Brun

    2006-09-15

    In an effort to promote clean energy projects and aid in the commercialization of new fuel cell technologies the Long Island Power Authority (LIPA) initiated a Fuel Cell Demonstration Program in 1999 with six month deployments of Proton Exchange Membrane (PEM) non-commercial Beta model systems at partnering sites throughout Long Island. These projects facilitated significant developments in the technology, providing operating experience that allowed the manufacturer to produce fuel cells that were half the size of the Beta units and suitable for outdoor installations. In 2001, LIPA embarked on a large-scale effort to identify and develop measures that could improve the reliability and performance of future fuel cell technologies for electric utility applications and the concept to establish a fuel cell farm (Farm) of 75 units was developed. By the end of October of 2001, 75 Lorax 2.0 fuel cells had been installed at the West Babylon substation on Long Island, making it the first fuel cell demonstration of its kind and size anywhere in the world at the time. Designed to help LIPA study the feasibility of using fuel cells to operate in parallel with LIPA's electric grid system, the Farm operated 120 fuel cells over its lifetime of over 3 years including 3 generations of Plug Power fuel cells (Lorax 2.0, Lorax 3.0, Lorax 4.5). Of these 120 fuel cells, 20 Lorax 3.0 units operated under this Award from June 2002 to September 2004. In parallel with the operation of the Farm, LIPA recruited government and commercial/industrial customers to demonstrate fuel cells as on-site distributed generation. From December 2002 to February 2005, 17 fuel cells were tested and monitored at various customer sites throughout Long Island. The 37 fuel cells operated under this Award produced a total of 712,635 kWh. As fuel cell technology became more mature, performance improvements included a 1% increase in system efficiency. Including equipment, design, fuel, maintenance

  5. EPRI fuel cladding integrity program

    Energy Technology Data Exchange (ETDEWEB)

    Yang, R. [Electric Power Research Institute, Palo Alto, CA (United States)

    1997-01-01

    The objectives of the EPRI fuel program is to supplement the fuel vendor research to assure that utility economic and operational interests are met. To accomplish such objectives, EPRI has conducted research and development efforts to (1) reduce fuel failure rates and mitigate the impact of fuel failures on plant operation, (2) provide technology to extend burnup and reduce fuel cycle cost. The scope of R&D includes fuel and cladding. In this paper, only R&D related to cladding integrity will be covered. Specific areas aimed at improving fuel cladding integrity include: (1) Fuel Reliability Data Base; (2) Operational Guidance for Defective Fuel; (3) Impact of Water Chemistry on Cladding Integrity; (4) Cladding Corrosion Data and Model; (5) Cladding Mechanical Properties; and (6) Transient Fuel Cladding Response.

  6. SNTP program fuel element design

    Science.gov (United States)

    Walton, Lewis A.; Ales, Matthew W.

    1993-06-01

    The SNTP program is evaluating the feasibility of utilizing a particle bed reactor to develop a high-performance nuclear thermal rocket engine. The optimum fuel element arrangement depends on the power level desired and the intended application. The key components of the fuel element have been developed and are being tested.

  7. The DUPIC fuel development program in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Yang, M. S.; Park, H. S. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-07-01

    This study describes the DUPIC fuel development program in KAERI as follows; Burning spent PWR fuel again in CANDU by DUPIC, Compatibility with existing CANDU system, Feasibility of DUPIC fuel fabrication, Waste reduction, Safeguard ability, Economics of DUPIC fuel cycle, The DUPIC fuel development program, and International prospective. 5 refs., 10 figs.

  8. Alcohol fuels program technical review

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-07-01

    The last issue of the Alcohol Fuels Process R/D Newsletter contained a work breakdown structure (WBS) of the SERI Alcohol Fuels Program that stressed the subcontracted portion of the program and discussed the SERI biotechnology in-house program. This issue shows the WBS for the in-house programs and contains highlights for the remaining in-house tasks, that is, methanol production research, alcohol utilization research, and membrane research. The methanol production research activity consists of two elements: development of a pressurized oxygen gasifier and synthesis of catalytic materials to more efficiently convert synthesis gas to methanol and higher alcohols. A report is included (Finegold et al. 1981) that details the experimental apparatus and recent results obtained from the gasifier. The catalysis research is principally directed toward producing novel organometallic compounds for use as a homogeneous catalyst. The utilization research is directed toward the development of novel engine systems that use pure alcohol for fuel. Reforming methanol and ethanol catalytically to produce H/sub 2/ and CO gas for use as a fuel offers performance and efficiency advantages over burning alcohol directly as fuel in an engine. An application of this approach is also detailed at the end of this section. Another area of utilization is the use of fuel cells in transportation. In-house researchers investigating alternate electrolyte systems are exploring the direct and indirect use of alcohols in fuel cells. A workshop is being organized to explore potential applications of fuel cells in the transportation sector. The membrane research group is equipping to evaluate alcohol/water separation membranes and is also establishing cost estimation and energy utilization figures for use in alcohol plant design.

  9. Preliminary analysis of alternative fuel cycles for proliferation evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M. J.; Ripfel, H. C.F.; Rainey, R. H.

    1977-01-01

    The ERDA Division of Nuclear Research and Applications proposed 67 nuclear fuel cycles for assessment as to their nonproliferation potential. The object of the assessment was to determine which fuel cycles pose inherently low risk for nuclear weapon proliferation while retaining the major benefits of nuclear energy. This report is a preliminary analysis of these fuel cycles to develop the fuel-recycle data that will complement reactor data, environmental data, and political considerations, which must be included in the overall evaluation. This report presents the preliminary evaluations from ANL, HEDL, ORNL, and SRL and is the basis for a continuing in-depth study. (DLC)

  10. Dual-fuel, dual-throat engine preliminary analysis

    Science.gov (United States)

    Obrien, C. J.

    1979-01-01

    A propulsion system analysis of the dual fuel, dual throat engine for launch vehicle applications was conducted. Basic dual throat engine characterization data were obtained to allow vehicle optimization studies to be conducted. A preliminary baseline engine system was defined.

  11. Preliminary Calculation on a Spent Fuel Pool Accident using GOTHIC

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaehwan; Choi, Yu Jung; Hong, Tae Hyub; Kim, Hyeong-Taek [KHNP-CRI, Daejeon (Korea, Republic of)

    2015-10-15

    The probability of an accident happening at the spent fuel pool was believed to be quite low until the 2011 Fukushima accident occurred. Notably, large amount of spent fuel are normally stored in the spent fuel pool for a long time compared to the amount of fuel in the reactor core and the total heat released from the spent fuel is high enough to boil the water of the spent fuel pool when the cooling system does not operate. In addition, the enrichment and the burnup of the fuel have both increased in the past decade and heat generation from the spent fuel thereby has also increased. The failure of the cooling system at the spent fuel pool (hereafter, a loss-of-cooling accident) is one of the principal hypothetical causes of an accident that could occur at the spent fuel pool. In this paper, the preliminary calculation of a loss-of-cooling accident was performed. In this paper, the preliminary calculation of a loss-of cooling accident was performed with GOTHIC. The calculation results show boiling away of water in the spent fuel pool due to the loss-of-cooling accident and similar thermal performance of the spent fuel pool with previous research results.

  12. Connecticut Transit (CTTRANSIT) Fuel Cell Transit Bus: Preliminary Evaluation Results

    Energy Technology Data Exchange (ETDEWEB)

    Chandler, K.; Eudy, L.

    2008-10-01

    This report provides preliminary results from a National Renewable Energy Laboratory evaluation of a protoptye fuel cell transit bus operating at Connecticut Transit in Hartford. Included are descriptions of the planned fuel cell bus demonstration and equipment; early results and agency experience are also provided.

  13. Design and preliminary results of a fuel flexible industrial gas turbine combustor

    Science.gov (United States)

    Novick, A. S.; Troth, D. L.; Yacobucci, H. G.

    1981-01-01

    The design characteristics are presented of a fuel tolerant variable geometry staged air combustor using regenerative/convective cooling. The rich/quench/lean variable geometry combustor is designed to achieve low NO(x) emission from fuels containing fuel bound nitrogen. The physical size of the combustor was calculated for a can-annular combustion system with associated operating conditions for the Allison 570-K engine. Preliminary test results indicate that the concept has the potential to meet emission requirements at maximum continuous power operation. However, airflow sealing and improved fuel/air mixing are necessary to meet Department of Energy program goals.

  14. Design and preliminary results of a fuel flexible industrial gas turbine combustor

    Science.gov (United States)

    Novick, A. S.; Troth, D. L.; Yacobucci, H. G.

    1981-01-01

    The design characteristics are presented of a fuel tolerant variable geometry staged air combustor using regenerative/convective cooling. The rich/quench/lean variable geometry combustor is designed to achieve low NO(x) emission from fuels containing fuel bound nitrogen. The physical size of the combustor was calculated for a can-annular combustion system with associated operating conditions for the Allison 570-K engine. Preliminary test results indicate that the concept has the potential to meet emission requirements at maximum continuous power operation. However, airflow sealing and improved fuel/air mixing are necessary to meet Department of Energy program goals.

  15. 1986 fuel cell seminar: Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-10-01

    Ninety nine brief papers are arranged under the following session headings: gas industry's 40 kw program, solid oxide fuel cell technology, phosphoric acid fuel cell technology, molten carbonate fuel cell technology, phosphoric acid fuel cell systems, power plants technology, fuel cell power plant designs, unconventional fuels, fuel cell application and economic assessments, and plans for commerical development. The papers are processed separately for the data base. (DLC)

  16. Fuels from biomass program. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    An overview of the ongoing research, development, and demonstration efforts of the period Oct. 1, 1976--Sept. 30, 1977 is presented. Accomplishments are highlighted and plans for continued activities are included. Discussion is presented under the following section headings: the Fuels from Biomass Program; organizational and functional responsibilities; program funding; fiscal year 1977 summary tables; current projects: production and collection of biomass and conversion of biomass; bibliography; index of contractors; and, appendix--unsolicited proposal requirements. (JGB)

  17. Spent fuel data for waste storage programs

    Energy Technology Data Exchange (ETDEWEB)

    Greene, E M

    1980-09-01

    Data on LWR spent fuel were compiled for dissemination to participants in DOE-sponsored waste storage programs. Included are mechanical descriptions of the existing major types of LWR fuel assemblies, spent LWR fuel fission product inventories and decay heat data, and inventories of LWR spent fuel currently in storage, with projections of future quantities.

  18. Preliminary Nuclear Analysis for the HANARO Fuel Element with Burnable Absorber

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Chul Gyo; Kim, So Young; In, Won Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Burnable absorber is used for reducing reactivity swing and power peaking in high performance research reactors. Development of the HANARO fuel element with burnable absorber was started in the U-Mo fuel development program at HANARO, but detailed full core analysis was not performed because the current HANARO fuel management system is uncertain to analysis the HANARO core with burnable absorber. A sophisticated reactor physics system is required to analysis the core. The McCARD code was selected and the detailed McCARD core models, in which the basic HANARO core model was developed by one of the McCARD developers, are used in this study. The development of nuclear fuel requires a long time and correct developing direction especially by the nuclear analysis. This paper presents a preliminary nuclear analysis to promote the fuel development. Based on the developed fuel, the further nuclear analysis will improve reactor performance and safety. Basic nuclear analysis for the HANARO and the AHR were performed for getting the proper fuel elements with burnable absorber. Addition of 0.3 - 0.4% Cd to the fuel meat is promising for the current HANARO fuel element. Small addition of burnable absorber may not change any fuel characteristics of the HANARO fuel element, but various basic tests and irradiation tests at the HANARO core are required.

  19. Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Gilles Youinou; R. Sonat Sen

    2013-09-01

    The severe accident at Fukushima Daiichi nuclear plants illustrates the need for continuous improvements through developing and implementing technologies that contribute to safe, reliable and cost-effective operation of the nuclear fleet. Development of enhanced accident tolerant fuel contributes to this effort. These fuels, in comparison with the standard zircaloy – UO2 system currently used by the LWR industry, should be designed such that they tolerate loss of active cooling in the core for a longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, and design-basis events. This report presents a preliminary systems analysis related to most of these concepts. The potential impacts of these innovative LWR fuels on the front-end of the fuel cycle, on the reactor operation and on the back-end of the fuel cycle are succinctly described without having the pretension of being exhaustive. Since the design of these various concepts is still a work in progress, this analysis can only be preliminary and could be updated as the designs converge on their respective final version.

  20. General Motors automotive fuel cell program

    Energy Technology Data Exchange (ETDEWEB)

    Fronk, M.H.

    1995-08-01

    The objectives of the second phase of the GM/DOE fuel cell program is to develop and test a 30 kW fuel cell powerplant. This powerplant will be based on a methanol fuel processor and a proton exchange membrane PM fuel cell stack. In addition, the 10 kW system developed during phase I will be used as a {open_quotes}mule{close_quotes} to test automotive components and other ancillaries, needed for transient operation.

  1. Fuel consolidation demonstration program: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    1990-06-01

    EPRI, Northeast Utilities, Baltimore Gas and Electric, the US Department of Energy and Combustion Engineering are engaged in a program to develop a system for consolidating spent fuel and a method of storing the consolidated fuel in the spent fuel storage pool which is licensable by the US Nuclear Regulatory Commission. Fuel consolidation offers a means of substantially increasing the capacity of spent fuel storage pools. This is a final report of the Fuel Consolidation Demonstration Program. It provides a review of the overall program, a summary of the results obtained, the lessons learned, and an assessment of the present status of the consolidation system developed in the program. 7 refs., 15 figs., 5 tabs.

  2. Westinghouse accident tolerant fuel program. Current results and future plans

    Energy Technology Data Exchange (ETDEWEB)

    Ray, Sumit; Xu, Peng; Lahoda, Edward; Hallstadius, Lars; Boylan, Frank [Westinghouse Electric Company LLC, Hopkins, SC (United States)

    2016-07-15

    This paper discusses the current status, results from initial tests, as well as the future direction of the Westinghouse's Accident Tolerant Fuel (ATF) program. The current preliminary testing is addressed that is being performed on these samples at the Massachusetts Institute of Technology (MIT) test reactor, initial results from these tests, as well as the technical learning from these test results. In the Westinghouse ATF approach, higher density pellets play a significant role in the development of an integrated fuel system.

  3. Preliminary Modeling of Accident Tolerant Fuel Concepts under Accident Conditions

    Energy Technology Data Exchange (ETDEWEB)

    Gamble, Kyle A.; Hales, Jason D.

    2016-12-01

    The catastrophic events that occurred at the Fukushima-Daiichi nuclear power plant in 2011 have led to widespread interest in research of alternative fuels and claddings that are proposed to be accident tolerant. Thus, the United States Department of Energy through its NEAMS (Nuclear Energy Advanced Modeling and Simulation) program has funded an Accident Tolerant Fuel (ATF) High Impact Problem (HIP). The ATF HIP is funded for a three-year period. The purpose of the HIP is to perform research into two potential accident tolerant concepts and provide an in-depth report to the Advanced Fuels Campaign (AFC) describing the behavior of the concepts, both of which are being considered for inclusion in a lead test assembly scheduled for placement into a commercial reactor in 2022. The initial focus of the HIP is on uranium silicide fuel and iron-chromium-aluminum (FeCrAl) alloy cladding. Utilizing the expertise of three national laboratory participants (INL, LANL, and ANL) a comprehensive mulitscale approach to modeling is being used including atomistic modeling, molecular dynamics, rate theory, phase-field, and fuel performance simulations. In this paper, we present simulations of two proposed accident tolerant fuel systems: U3Si2 fuel with Zircaloy-4 cladding, and UO2 fuel with FeCrAl cladding. The simulations investigate the fuel performance response of the proposed ATF systems under Loss of Coolant and Station Blackout conditions using the BISON code. Sensitivity analyses are completed using Sandia National Laboratories’ DAKOTA software to determine which input parameters (e.g., fuel specific heat) have the greatest influence on the output metrics of interest (e.g., fuel centerline temperature). Early results indicate that each concept has significant advantages as well as areas of concern. Further work is required prior to formulating the proposition report for the Advanced Fuels Campaign.

  4. Fire Resistant Fuel Program Update

    Science.gov (United States)

    2011-09-13

    38°F Flashpoint • Objectives – developing new emulsified fuel formulations; – investigating anti-mist additives to diminish the fuel fireball ...unreacted diethanolamine. UNCLASSIFIED UNCLASSIFIED Current FRF Formulation – Mist Control Additive (MCA) – (125-250 ppm) reduces initial fireball ...size which results in reduced fireball size UNCLASSIFIED UNCLASSIFIED Current FRF Formulation – Water reduces or extinguishes pool fuel fires (10 vol

  5. Ansaldo programs on fuel cell vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Marcenaro, B.G.; Federici, F. [Ansaldo Ricerche Srl, Genova (Italy)

    1996-12-31

    The growth in traffic and the importance of maintaining a stable ecology at the global scale, particularly with regard to atmospheric pollution, raises the necessity to realize a new generation of vehicles which are more efficient, more economical and compatible with the environment. At European level, the Car of Tomorrow task force has identified fuel cells as a promising alternative propulsion system. Ansaldo Ricerche has been involved in the development of fuel cell vehicles since the early nineties. Current ongoing programs relates to: (1) Fuel cell bus demonstrator (EQHEPP BUS) Test in 1996 (2) Fuel cell boat demonstrator (EQHHPP BOAT) Test in 1997 (3) Fuel cell passenger car prototype (FEVER) Test in 1997 (4) 2nd generation Fuel cell bus (FCBUS) 1996-1999 (5) 2nd generation Fuel cell passenger car (HYDRO-GEN) 1996-1999.

  6. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  7. Preliminary Economics for Hydrocarbon Fuel Production from Cellulosic Sugars

    Energy Technology Data Exchange (ETDEWEB)

    Collett, James R.; Meyer, Pimphan A.; Jones, Susanne B.

    2014-05-18

    Biorefinery process and economic models built in CHEMCAD and a preliminary, genome-scale metabolic model for the oleaginous yeast Lipomyces starkeyi were used to simulate the bioconversion of corn stover to lipids, and the upgrading of these hydrocarbon precursors to diesel and jet fuel. The metabolic model was based on the recently released genome sequence for L. starkeyi and on metabolic pathway information from the literature. The process model was based on bioconversion, lipid extraction, and lipid oil upgrading data found in literature, on new laboratory experimental data, and on yield predictions from the preliminary L. starkeyi metabolic model. The current plant gate production cost for a distillate-range hydrocarbon fuel was estimated by the process model Base Case to be $9.5/gallon ($9.0 /gallon of gasoline equivalent) with assumptions of 2011$, 10% internal return on investment, and 2205 ton/day dry feed rate. Opportunities for reducing the cost to below $5.0/gallon, such as improving bioconversion lipid yield and hydrogenation catalyst selectivity, are presented in a Target Case. The process and economic models developed for this work will be updated in 2014 with new experimental data and predictions from a refined metabolic network model for L. starkeyi. Attaining a production cost of $3.0/gallon will require finding higher value uses for lignin other than power generation, such as conversion to additional fuel or to a co-product.

  8. Climate Change Fuel Cell Program

    Energy Technology Data Exchange (ETDEWEB)

    Paul Belard

    2006-09-21

    Verizon is presently operating the largest Distributed Generation Fuel Cell project in the USA. Situated in Long Island, NY, the power plant is composed of seven (7) fuel cells operating in parallel with the Utility grid from the Long Island Power Authority (LIPA). Each fuel cell has an output of 200 kW, for a total of 1.4 mW generated from the on-site plant. The remaining power to meet the facility demand is purchased from LIPA. The fuel cell plant is utilized as a co-generation system. A by-product of the fuel cell electric generation process is high temperature water. The heat content of this water is recovered from the fuel cells and used to drive two absorption chillers in the summer and a steam generator in the winter. Cost savings from the operations of the fuel cells are forecasted to be in excess of $250,000 per year. Annual NOx emissions reductions are equivalent to removing 1020 motor vehicles from roadways. Further, approximately 5.45 million metric tons (5 millions tons) of CO2 per year will not be generated as a result of this clean power generation. The project was partially financed with grants from the New York State Energy R&D Authority (NYSERDA) and from Federal Government Departments of Defense and Energy.

  9. DEMONSTRATION OF FUEL CELLS TO RECOVER ENERGY FROM ANAEROBIC DIGESTER GAS - PHASE I. CONCEPTUAL DESIGN, PRELIMINARY COST, AND EVALUATION STUDY

    Science.gov (United States)

    The report discusses Phase I (a conceptual design, preliminary cost, and evaluation study) of a program to demonstrate the recovery of energy from waste methane produced by anaerobic digestion of waste water treatment sludge. The fuel cell is being used for this application becau...

  10. DEMONSTRATION OF FUEL CELLS TO RECOVER ENERGY FROM ANAEROBIC DIGESTER GAS - PHASE I. CONCEPTUAL DESIGN, PRELIMINARY COST, AND EVALUATION STUDY

    Science.gov (United States)

    The report discusses Phase I (a conceptual design, preliminary cost, and evaluation study) of a program to demonstrate the recovery of energy from waste methane produced by anaerobic digestion of waste water treatment sludge. The fuel cell is being used for this application becau...

  11. DOE Hydrogen and Fuel Cells Program Plan (September 2011)

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-09-01

    The Department of Energy Hydrogen and Fuel Cells Program Plan outlines the strategy, activities, and plans of the DOE Hydrogen and Fuel Cells Program, which includes hydrogen and fuel cell activities within the EERE Fuel Cell Technologies Program and the DOE offices of Nuclear Energy, Fossil Energy, and Science.

  12. Renewable Fuel Standard Program (RFS1): Final Rule Additional Resources

    Science.gov (United States)

    The final rule of fuels and fuel additives: renewable fuel standard program is published on May 1, 2007 and is effective on September 1, 2007. You will find the links to this final rule and technical amendments supporting this rule.

  13. PRELIMINARY PROGRAMMED WHOLE—BODY COUNTER

    Institute of Scientific and Technical Information of China (English)

    张少东; 郑文忠; 等

    1995-01-01

    It is capable of giving the initial intakes of radionuclides and the assessment quantitites used in radiation protection according to its measured results of radionuclides in vivo.It is accomplished by providing the software of controlling,interface and internal dose estimation programs to the original iron cabin shielding whole-body counter.The preliminary application shows that its data processing is rapid and correct,and can meet the requirement of rapid internal radioactive contamination monitoring and diagnosing in case of lots of internal contamination subjects happened in nuclear accident.

  14. Fuel Flexible Turbine System (FFTS) Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    2012-12-31

    In this fuel flexible turbine system (FFTS) program, the Parker gasification system was further optimized, fuel composition of biomass gasification process was characterized and the feasibility of running Capstone MicroTurbine(TM) systems with gasification syngas fuels was evaluated. With high hydrogen content, the gaseous fuel from a gasification process of various feed stocks such as switchgrass and corn stover has high reactivity and high flashback propensity when running in the current lean premixed injectors. The research concluded that the existing C65 microturbine combustion system, which is designed for natural gas, is not able to burn the high hydrogen content syngas due to insufficient resistance to flashback (undesired flame propagation to upstream within the fuel injector). A comprehensive literature review was conducted on high-hydrogen fuel combustion and its main issues. For Capstone?s lean premixed injector, the main mechanisms of flashback were identified to be boundary layer flashback and bulk flow flashback. Since the existing microturbine combustion system is not able to operate on high-hydrogen syngas fuels, new hardware needed to be developed. The new hardware developed and tested included (1) a series of injectors with a reduced propensity for boundary layer flashback and (2) two new combustion liner designs (Combustion Liner Design A and B) that lead to desired primary zone air flow split to meet the overall bulk velocity requirement to mitigate the risk of core flashback inside the injectors. The new injector designs were evaluated in both test apparatus and C65/C200 engines. While some of the new injector designs did not provide satisfactory performance in burning target syngas fuels, particularly in improving resistance to flashback. The combustion system configuration of FFTS-4 injector and Combustion Liner Design A was found promising to enable the C65 microturbine system to run on high hydrogen biomass syngas. The FFTS-4 injector was

  15. Fuel Flexible Turbine System (FFTS) Program

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2012-12-31

    In this fuel flexible turbine system (FFTS) program, the Parker gasification system was further optimized, fuel composition of biomass gasification process was characterized and the feasibility of running Capstone MicroTurbine(TM) systems with gasification syngas fuels was evaluated. With high hydrogen content, the gaseous fuel from a gasification process of various feed stocks such as switchgrass and corn stover has high reactivity and high flashback propensity when running in the current lean premixed injectors. The research concluded that the existing C65 microturbine combustion system, which is designed for natural gas, is not able to burn the high hydrogen content syngas due to insufficient resistance to flashback (undesired flame propagation to upstream within the fuel injector). A comprehensive literature review was conducted on high-hydrogen fuel combustion and its main issues. For Capstone's lean premixed injector, the main mechanisms of flashback were identified to be boundary layer flashback and bulk flow flashback. Since the existing microturbine combustion system is not able to operate on high-hydrogen syngas fuels, new hardware needed to be developed. The new hardware developed and tested included (1) a series of injectors with a reduced propensity for boundary layer flashback and (2) two new combustion liner designs (Combustion Liner Design A and B) that lead to desired primary zone air flow split to meet the overall bulk velocity requirement to mitigate the risk of core flashback inside the injectors. The new injector designs were evaluated in both test apparatus and C65/C200 engines. While some of the new injector designs did not provide satisfactory performance in burning target syngas fuels, particularly in improving resistance to flashback. The combustion system configuration of FFTS-4 injector and Combustion Liner Design A was found promising to enable the C65 microturbine system to run on high hydrogen biomass syngas. The FFTS-4 injector

  16. NP-MHTGR Fuel Development Program Results

    Energy Technology Data Exchange (ETDEWEB)

    Maki, John Thomas; Petti, David Andrew; Hobbins, Richard Redfield; McCardell, Richard K.; Shaber, Eric Lee; Southworth, Finis Hio

    2002-10-01

    In August 1988, the Secretary of Energy announced a strategy to acquire New Production Reactor capacity for producing tritium. The strategy involved construction of a New Production Modular High Temperature Gas-Cooled Reactor (NP-MHTGR) where the Idaho National Engineering and Environmental Laboratory (INEEL) was selected as the Management and Operations contractor for the project. Immediately after the announcement in August 1988, tritium target particle development began with the INEEL selected as the lead laboratory. Fuel particle development was initially not considered to be on a critical path for the project, therefore, the fuel development program was to run concurrently with the design effort of the NP-MHTGR.

  17. Preliminary concepts: coordinated safeguards for materials management in a thorium--uranium fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Barnes, J.W.; Dayem, H.A.; Dietz, R.J.; Shipley, J.P.

    1978-10-01

    This report addresses preliminary concepts for coordinated safeguards materials management in a typical generic thorium--uranium-fueled light-water reactor (LWR) fuels reprocessing plant. The reference facility is designed to recover thorium and uranium from first-generation (denatured /sup 235/U) startup fuels, first-recycle and equilibrium (denatured /sup 233/U) thorium--uranium LWR fuels, and to recover the plutonium generated in the /sup 238/U denaturant as well. 12 figures, 3 tables.

  18. Solid Polymer Electrolyte Fuel Cell Technology Program

    Science.gov (United States)

    1980-01-01

    Work is reported on phase 5 of the Solid Polymer Electrolyte (SPE) Fuel Cell Technology Development program. The SPE fuel cell life and performance was established at temperatures, pressures, and current densities significantly higher than those previously demonstrated in sub-scale hardware. Operation of single-cell Buildup No. 1 to establish life capabilities of the full-scale hardware was continued. A multi-cell full-scale unit (Buildup No. 2) was designed, fabricated, and test evaluated laying the groundwork for the construction of a reactor stack. A reactor stack was then designed, fabricated, and successfully test-evaluated to demonstrate the readiness of SPE fuel cell technology for future space applications.

  19. Fuel Cell Power Plant Initiative. Volume 2; Preliminary Design of a Fixed-Base LFP/SOFC Power System

    Science.gov (United States)

    Veyo, S.E.

    1997-01-01

    This report documents the preliminary design for a military fixed-base power system of 3 MWe nominal capacity using Westinghouse's tubular Solid Oxide Fuel Cell [SOFC] and Haldor Topsoe's logistic fuels processor [LFP]. The LFP provides to the fuel cell a methane rich sulfur free fuel stream derived from either DF-2 diesel fuel, or JP-8 turbine fuel. Fuel cells are electrochemical devices that directly convert the chemical energy contained in fuels such as hydrogen, natural gas, or coal gas into electricity at high efficiency with no intermediate heat engine or dynamo. The SOFC is distinguished from other fuel cell types by its solid state ceramic structure and its high operating temperature, nominally 1000'C. The SOFC pioneered by Westinghouse has a tubular geometry closed at one end. A power generation stack is formed by aggregating many cells in an ordered array. The Westinghouse stack design is distinguished from other fuel cell stacks by the complete absence of high integrity seals between cell elements, cells, and between stack and manifolds. Further, the reformer for natural gas [predominantly methane] and the stack are thermally and hydraulically integrated with no requirement for process water. The technical viability of combining the tubular SOFC and a logistic fuels processor was demonstrated at 27 kWe scale in a test program sponsored by the Advanced Research Projects Agency [ARPA) and carried out at the Southern California Edison's [SCE] Highgrove generating station near San Bernardino, California in 1994/95. The LFP was a breadboard design supplied by Haldor Topsoe, Inc. under subcontract to Westinghouse. The test program was completely successful. The LFP fueled the SOFC for 766 hours on JP-8 and 1555 hours of DF-2. In addition, the fuel cell operated for 3261 hours on pipeline natural gas. Over the 5582 hours of operation, the SOFC generated 118 MVVH of electricity with no perceptible degradation in performance. The LFP processed military

  20. Preliminary Design of U-Mo Alloy Dispersion Fuel Assembly

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>As a kind of new type fuel for research reactor, high density U-Mo alloy dispersion fuel which will substitute current fuel in the future is being studied and developed by RERTR. There are two characteristics

  1. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-10-01

    This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

  2. Preliminary ecotoxicity assessment of new generation alternative fuels in seawater.

    Science.gov (United States)

    Rosen, Gunther; Dolecal, Renee E; Colvin, Marienne A; George, Robert D

    2014-06-01

    The United States Navy (USN) is currently demonstrating the viability of environmentally sustainable alternative fuels to power its fleet comprised of aircraft and ships. As with any fuel used in a maritime setting, there is potential for introduction into the environment through transport, storage, and spills. However, while alternative fuels are often presumed to be eco-friendly relative to conventional petroleum-based fuels, their environmental fate and effects on marine environments are essentially unknown. Here, standard laboratory-based toxicity experiments were conducted for two alternative fuels, jet fuel derived from Camelina sativa (wild flax) seeds (HRJ5) and diesel fuel derived from algae (HRD76), and two conventional counterparts, jet fuel (JP5) and ship diesel (F76). Initial toxicity tests performed on water-accommodated fractions (WAF) from neat fuels partitioned into seawater, using four standard marine species in acute and chronic/sublethal tests, indicate that the alternative fuels are significantly less toxic to marine organisms.

  3. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

  4. Monitoring instrumentation spent fuel management program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Preliminary monitoring system methodologies are identified as an input to the risk assessment of spent fuel management. Conceptual approaches to instrumentation for surveillance of canister position and orientation, vault deformation, spent fuel dissolution, temperature, and health physics conditions are presented. In future studies, the resolution, reliability, and uncertainty associated with these monitoring system methodologies will be evaluated.

  5. Fourth annual report to Congress, Federal Alternative Motor Fuels Programs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This annual report to Congress presents the current status of the alternative fuel vehicle programs being conducted across the country in accordance with the Alternative Motor Fuels Act of 1988. These programs, which represent the most comprehensive data collection effort ever undertaken on alternative fuels, are beginning their fifth year. This report summarizes tests and results from the fourth year.

  6. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  7. Emergency fuels utilization guidebook. Alternative Fuels Utilization Program

    Energy Technology Data Exchange (ETDEWEB)

    1980-08-01

    The basic concept of an emergency fuel is to safely and effectively use blends of specification fuels and hydrocarbon liquids which are free in the sense that they have been commandeered or volunteered from lower priority uses to provide critical transportation services for short-duration emergencies on the order of weeks, or perhaps months. A wide variety of liquid hydrocarbons not normally used as fuels for internal combustion engines have been categorized generically, including limited information on physical characteristics and chemical composition which might prove useful and instructive to fleet operators. Fuels covered are: gasoline and diesel fuel; alcohols; solvents; jet fuels; kerosene; heating oils; residual fuels; crude oils; vegetable oils; gaseous fuels.

  8. HYDROGEN-OXYGEN PRIMARY EXTRATERRESTRIAL (HOPE) FUEL CELL PROGRAM

    Science.gov (United States)

    The HOPE (Hydrogen-Oxygen Primary Extraterrestrial) Fuel Cell Program is a multi-phase effort to advance the state-of-the-art of fuel cells by...configuration fuel cell module. The HOPE spacecraft, fuel supply tanks, pneumatics, and thermal systems were designed and fabricated to provide...verify water removal, thermal design, and 30-day shelf-life of the fuel cell . The 35-cell module was subjected to a series of performance tests

  9. Sustainable Harvest for Food and Fuel Preliminary Food & Fuel Gap Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Ray Grosshans; Kevin M. Kostelnik; Jake Jacobson

    2007-04-01

    To promote economic growth and energy security, and to protect the environment, the U.S. is pursuing a national strategy of energy independence and climatic protection in which domestic renewable carbon-neutral biofuels displace 30 percent of U.S. oil consumption by the mid-21st century. Such fuels, including ethanol and biodiesel, will be produced from biological feed stocks (biomass). The availability of this billion-ton biomass will hinge on the application of modern scientific and engineering tools to create a highly-integrated biofuel production system. Efforts are underway to identify and develop energy crops, ranging from agricultural residues to genetically engineered perennials; to develop biology-based processing methods; and, to develop large-scale biorefineries to economically convert biomass into fuels. In addition to advancing the biomass-to-biofuel research and development agenda, policy makers are concurrently defining the correct mix of governmental supports and regulations. Given the volumes of biomass and fuels that must flow to successfully enact a national biomass strategy, policies must encourage large-scale markets to form and expand around a tightly integrated system of farmers, fuel producers and transporters, and markets over the course of decades. In formulating such policies, policy makers must address the complex interactions of social, technical, economic, and environmental factors that bound energy production and use. The Idaho National Laboratory (INL) is a science-based, applied engineering national laboratory dedicated to supporting the U.S. Department of Energy (DOE). The INL Bioenergy Program supports the DOE and the U.S. Department of Agriculture. Key multidisciplinary INL capabilities are being leveraged to address major science and technology needs associated with the cost-effective utilization of biomass. INL’s whole crop utilization (WCU) vision is focused on the use of the entire crop, including both the grain and

  10. Hawaii alternative fuels utilization program. Phase 3, final report

    Energy Technology Data Exchange (ETDEWEB)

    Kinoshita, C.M.; Staackmann, M.

    1996-08-01

    The Hawaii Alternative Fuels Utilization Program originated as a five-year grant awarded by the US Department of Energy (USDOE) to the Hawaii Natural Energy Institute (HNEI) of the University of Hawaii at Manoa. The overall program included research and demonstration efforts aimed at encouraging and sustaining the use of alternative (i.e., substitutes for gasoline and diesel) ground transportation fuels in Hawaii. Originally, research aimed at overcoming technical impediments to the widespread adoption of alternative fuels was an important facet of this program. Demonstration activities centered on the use of methanol-based fuels in alternative fuel vehicles (AFVs). In the present phase, operations were expanded to include flexible fuel vehicles (FFVs) which can operate on M85 or regular unleaded gasoline or any combination of these two fuels. Additional demonstration work was accomplished in attempting to involve other elements of Hawaii in the promotion and use of alcohol fuels for ground transportation in Hawaii.

  11. EPAct Alternative Fuel Transporation Program - State and Alternative Fuel Provider Fleets: Frequently Asked Questions

    Energy Technology Data Exchange (ETDEWEB)

    None

    2010-03-01

    Factsheet answering frequently asked questions about the U.S. Department of Energy's Alternative Fuel Transportation Program (the Program) that implements provisions of Titles III–V of the Energy Policy Act of 1992 (EPAct). Answers to questions that are frequently asked about the Program by managers of state government and alternative fuel provider fleets are provided in the factsheet.

  12. Neutronic experiment planning for the Fuels Refabrication and Development Program

    Energy Technology Data Exchange (ETDEWEB)

    Gore, B.F.; NcNeese, J.P.; Zimmerman, M.G.; Konzek, G.J.

    1979-12-01

    A program of experiments using /sup 233/UO/sub 2/ - ThO/sub 2/ fuel was proposed to provide new and improved neutronic and criticality data for thorium based nuclear fuels, in order to support the licensing of /sup 233/UO/sub 2/ - ThO/sub 2/ fuels in LWR cores. This would support the goal to develop technology for proliferation resistant fuel cycles to a point where fuel cycle choice is not limited by refabrication technology. The proposed experimental program is described in this document, along with initial planning and fuel acquisition activities undertaken during FY 1979. The program was terminated following notification that the DOE-sponsored denatured LWR Fuel Program which the experiments supported was to be discontinued.

  13. The preliminary study of urbanization, fossil fuels consumptions and ...

    African Journals Online (AJOL)

    STORAGESEVER

    2010-03-29

    Mar 29, 2010 ... As a result the demand of more energy in form of fossil fuels increased for domestic ... Key words: Urbanization, fossil fuels, CO2 emission, energy consumption, population growth. ..... energy and biofuels. It will help to reduce ...

  14. LOFT fuel modules design, characterization, and fabrication program

    Energy Technology Data Exchange (ETDEWEB)

    Russell, M. L.

    1977-06-01

    The loss-of-fluid test (LOFT) fuel modules have evolved from a comprehensive five-year design, characterization, and fabrication program which has resulted in the accomplishment of many technical activities of interest in pressurized water reactor fuel design development and safety research. Information is presented concerning: determination of fundamental high-temperature reactor material properties; design invention related to in-core instrumentation attachment; implementation of advanced and/or unique fuel bundle characterization techniques; implementation of improved fuel bundle fabrication techniques; and planning and execution of a multimillion dollar design, characterization, and fabrication program for pressurized water reactor fuel.

  15. Fuel cell energy service Enron`s commerical program

    Energy Technology Data Exchange (ETDEWEB)

    Jacobson, M.W.

    1996-04-01

    Enron, the premier provider of clean fuels worldwide, has launched a unique energy service based on fuel cell technology. The goal of this program is to bring the benefits of fuel cell power to the broad commercial marketplace. Enron`s Energy Service is currently based on a 200 kilowatt phosphoric acid power plant manufactured by ONSI Corporation. This plant is fueled by natural gas or propane, and exhibits superior performance. Enron offers a `no hassle` package that provides customers with immediate benefits with no upfront capital or technical risks. This paper describes Enron`s fuel cell commercial program.

  16. 1990 fuel cell seminar: Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-31

    This volume contains author prepared short resumes of the presentations at the 1990 Fuel Cell Seminar held November 25-28, 1990 in Phoenix, Arizona. Contained herein are 134 short descriptions organized into topic areas entitled An Environmental Overview, Transportation Applications, Technology Advancements for Molten Carbonate Fuel Cells, Technology Advancements for Solid Fuel Cells, Component Technologies and Systems Analysis, Stationary Power Applications, Marine and Space Applications, Technology Advancements for Acid Type Fuel Cells, and Technology Advancement for Solid Oxide Fuel Cells.

  17. PHOEBUS/UHTREX: a preliminary study of a low-cost facility for transient tests of LMFBR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kirk, W.L. (comp.)

    1976-08-01

    The results of a brief preliminary design study of a facility for transient nuclear tests of fast breeder reactor fuel are described. The study is based on the use of a reactor building originally built for the UHTREX reactor, and the use of some reactor hardware and reactor design and fabrication technology remaining from the Phoebus-2 reactor of the Rover nulcear rocket propulsion program. The facility is therefore currently identified as the PHOEBUS/UHTREX facility. This facility is believed capable of providing early information regarding fast reactor core accident energetics issues which will be very valuable to the overall LMFBR safety program. Facility performance in conjunction with a reference 127-fuel pin experiment is described. Low cost and early availability of the facility were emphasized in the selection of design features and parameters.

  18. Alcohol Fuels Program technical review, Spring 1984

    Energy Technology Data Exchange (ETDEWEB)

    1984-10-01

    The alcohol fuels program consists of in-house and subcontracted research for the conversion of lignocellulosic biomass into fuel alcohols via thermoconversion and bioconversion technologies. In the thermoconversion area, the SERI gasifier has been operated on a one-ton per day scale and produces a clean, medium-Btu gas that can be used to manufacture methanol with a relatively small gas-water shift reaction requirement. Recent research has produced catalysts that make methanol and a mixture of higher alcohols from the biomass-derived synthetic gas. Three hydrolysis processes have emerged as candidates for more focused research. They are: a high-temperature, dilute-acid, plug-flow approach based on the Dartmouth reactor; steam explosion pretreatment followed by hydrolysis using the RUT-C30 fungal organism; and direct microbial conversion of the cellulose to ethanol using bacteria in a single or mixed culture. Modeling studies, including parametric and sensitivity analyses, have recently been completed. The results of these studies will lead to a better definition of the present state-of-the-art for these processes and provide a framework for establishing the research and process engineering issues that still need resolution. In addition to these modeling studies, economic feasibility studies are being carried out by commercial engineering firms. Their results will supplement and add commercial validity to the program results. The feasibility contractors will provide input at two levels: Technical and economic assessment of the current state-of-the-art in alcohol production from lignocellulosic biomass via thermoconversion to produce methanol and higher alcohol mixtures and bioconversion to produce ethanol; and identification of research areas having the potential to significantly reduce the cost of production of alcohols.

  19. Fuel Cell Seminar, 1992: Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    This year`s theme, ``Fuel Cells: Realizing the Potential,`` focuses on progress being made toward commercial manufacture and use of fuel cell products. Fuel cell power plants are competing for market share in some applications and demonstrations of market entry power plants are proceeding for additional applications. Development activity on fuel cells for transportation is also increasing; fuel cell products have potential in energy and transportation industries, with very favorable environmental impacts. This Seminar has the purpose of fostering communication by providing a forum for the international community interested in development, application, and business opportunities related fuel cells. Over 190 technical papers are included, the majority being processed for the data base.

  20. National Fire Plan - Hazardous Fuels Reduction Program - Direct Download

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — This map layer portrays county level data for the fiscal-year-2004 National Fire Plan - Hazardous Fuels Reduction Program. The purpose of this program is to reduce...

  1. 2015 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-12-23

    The 2015 Annual Progress Report summarizes fiscal year 2015 activities and accomplishments by projects funded by the DOE Hydrogen and Fuel Cells Program. It covers the program areas of hydrogen production; hydrogen delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes and standards; systems analysis; and market transformation.

  2. Certification Report: Army Aviation Alternative Fuels Certification Program

    Science.gov (United States)

    2016-08-01

    SPECIAL REPORT RDMR-AE-16-02 CERTIFICATION REPORT: ARMY AVIATION ALTERNATIVE FUELS CERTIFICATION PROGRAM Dale Cox...NOT TO BE CONSTRUED AS AN OFFICIAL DEPARTMENT OF THE ARMY POSITION UNLESS SO DESIGNATED BY OTHER AUTHORIZED DOCUMENTS. TRADE NAMES USE...COVERED Final 4. TITLE AND SUBTITLE Certification Report: Army Aviation Alternative Fuels Certification Program 5. FUNDING NUMBERS 6

  3. Office of Alcohol Fuels Program plan, FY 1981

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-10-01

    The goal of the Office of Alcohol Fuels is to promote the production, distribution, and use of alcohol fuels. The program objectives are defined and the strategy for implementation is described. An organizational model of the operation is included. The roles of the 3 program offices and various field offices are described. (DMC)

  4. Preliminary Studies of New Water Removal Element in Purification Applications of Diesel Fuels

    Directory of Open Access Journals (Sweden)

    Ruijun Chen

    2014-01-01

    Full Text Available To effectively and efficiently remove water contamination dispersed in petrodiesel fuels, a new water removal element with both coalescence and separation features is studied in this paper. The unique droplet coalescence and separation mechanism occurring in the new water removal element is proposed. The conceptual design of this filter element is presented and the basic features of FCP filtration systems are briefly introduced. A laboratory test stand and fuel analysis procedure are described. The results from preliminary water removal tests with number 2 petrodiesel fuel demonstrate the filtration performance of the new water removal element. For example, within one single fuel flow pass through FCP filtration system equipped with the new water removal element and running at 2 GPM flow rate, the water content in 80°F, number 2 petrodiesel fuel stream can be reduced from up to 40,000 ppm upstream to 64.8 ppm or less downstream.

  5. Hydrocarbon Biocomponents use in Aviation Fuels - Preliminary Analysis of Issues

    Directory of Open Access Journals (Sweden)

    Gawron Bartosz

    2015-01-01

    Full Text Available Article is related to the aspect of the introduction of biofuels to power turbine aircraft engines. The paper presents the current trends in the use of alternative fuels in aviation and the problems connected with the introduction of hydrocarbon biocomponents. It is pointed to the need to take research and implementation works in the field of the subject, also in Poland.

  6. Fuel cell transit bus development & commercialization programs at Gerogetown University

    Energy Technology Data Exchange (ETDEWEB)

    Wimmer, R.; Larkins, J.; Romano, S. [Georgetown Univ., Washington, DC (United States)

    1996-12-31

    Fourteen years ago, Georgetown University (GU) perceived the need for a clean, efficient power systems for transportation that could operate on non-petroleum based fuels. The transit bus application was selected to begin system development. GU recognized the range and recharge constraints of a pure battery powered transit bus. A Fuel Cell power system would circumvent these limitations and, with an on board reformer, accommodate liquid fuel for rapid refueling. Feasibility studies for Fuel Cell power systems for transit buses were conducted with the Los Alamos National Laboratory in 1983. Successful results of this investigation resulted in the DOT/DOE Fuel Cell transit bus development program. The first task was to prove that small Fuel Cell power plants were possible. This was achieved with the Phase I development of two 25 kW Phosphoric Acid Fuel Cell (PAFC) brassboard systems. A liquid cooled version was selected for the Phase II activity in which three 30-foot Fuel Cell powered Test Bed Buses (TBBs) were fabricated. The first of these TBBs was delivered in the spring of 1994. All three of these development vehicles are now in Phase III of the program to conduct testing and evaluation, is conducting operational testing of the buses. The test will involve two fuel cell-operated buses; one with a proton exchange fuel cell and the other with a phosphoric acid fuel cell.

  7. Preliminary investigation of the effects of coal-water slurry fuels on the combustion in GE coal fueled diesel engine (Task 1. 1. 2. 2. 1, Fuels)

    Energy Technology Data Exchange (ETDEWEB)

    1990-06-01

    In prior work with the coal fired diesel research engine, a necessity to determine the sensitivity of the engine to a wider range of fuels was resolved and included in the R and D Test Plan submitted on 2/9/89. In general, the economic viability and universal acceptance of the commercial engine will be a factor of its ability to tolerate the widest range of source fuels with minimal fuel beneficiation. As detailed in the R and D Test Plan, a preliminary investigation on the effects of coal-water slurry (CWS) fuels on the combustion in a GE single cylinder test engine was conducted. The following conclusions are obtained from this investigation. All the test CWS fuels were successfully burned in the GE engine combustion system. They include: 3 to 15 microns mean particle size; 0.7 to 2.8% ash level; KY Blue Gem and PA Mariana bituminous coal, WY Kemmer and Spring Creek Sub-Bituminous coal; coal beneficiated with physical and chemical processes; two kinds of additives for OTISCA CWS; and burnout is not effected by ash or particle size within the test range. For each kind of CWS fuel, the detail design parameters of the fuel injection system has to be compatible. With sufficiently high fuel injection pressure, the 3 micron mean particle size OTISCA fuel burns faster than the 5 micron ones. For OTISCA fuel, the burn rate using Ammonium Lignosulfonate as additive is faster than using Ammonium Condensed Naphthalene Sulfonate. Appendices contain data on heat release, fuel characterization reports from two laboratories, general engine test data, and particulate size distribution. 3 refs.

  8. Preliminary Reactor Physics Assessment of the HTR Module with 14% Enriched UCO Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Gerhard Strydom; Hans D. Gougar

    2013-03-01

    The high temperature reactor (HTR) Module (Lohnert, 1990) is a graphite-moderated, helium cooled pebble bed design that has been extensively used as a reference template for the former South African (Matzner, 2004) and current Chinese (Zhang et al., 2009) HTR programs. This design utilizes spherical fuel elements packed into a dynamic pebble bed, consisting of tri-structural isotropic (TRISO) coated uranium oxide (UO2) 500 µm fuel kernels with a U-235 enrichment of 7.8% and a heavy metal loading of 7 g per pebble. This fuel type was previously qualified for use in Germany for pebble bed HTRs, as well as undergoing re-qualification in South Africa for the PBMR project. It is also the fuel type being tested for use in the high temperature reactor (HTR-PM) under construction in China. In the United States, however, a different TRISO fuel form is the subject of a qualification program. The U.S. experience with HTRs has been focused upon the batch-fueled prismatic reactor in which TRISO particles are embedded in cylindrical compacts and stacked inside the graphite blocks which comprise the core. Under this type of operating regime, a smaller TRISO with a different composition and enrichment performs better than the fuel historically used in PBRs. Fuel kernels and compacting techniques more suited to prismatic core duty are currently being developed and qualified under the U.S. Department of Energy's Advanced Gas Reactor (AGR) fuel development program and in support of the Next Generation Nuclear Plant project. Interest in the pebble bed concept remains high, however, and a study was undertaken by the authors to assess the viability of using AGR fuel in a pebble bed reactor. Using the German HTR Module as the reference plant, key neutronic and thermal-hydraulic parameters were compared between the nominal design and one fueled with the fuel that is the focus of the AGR program.

  9. 76 FR 67287 - Alternative Fuel Transportation Program; Alternative Fueled Vehicle Credit Program (Subpart F...

    Science.gov (United States)

    2011-10-31

    ... ``dedicated [alternative fuel] or dual fueled vehicle,'' and sections 501 (42 U.S.C. 13251) and 507 (42 U.S.C... example, B20 (a 20 percent blend of biodiesel with 80 percent petroleum diesel) is not an alternative fuel... that operate solely on alternative fuel, or ``dual fueled vehicles,'' which have some capability for...

  10. Breeder Spent Fuel Handling Program multipurpose cask design basis document

    Energy Technology Data Exchange (ETDEWEB)

    Duckett, A.J.; Sorenson, K.B.

    1985-09-01

    The Breeder Spent Fuel Handling (BSFH) Program multipurpose cask Design Basis Document defines the performance requirements essential to the development of a legal weight truck cask to transport FFTF spent fuel from reactor to a reprocessing facility and the resultant High Level Waste (HLW) to a repository. 1 ref.

  11. Fire, Fuel, and Smoke Science Program: 2013 Research accomplishments

    Science.gov (United States)

    Faith Ann Heinsch; Robin J. Innes; Colin C. Hardy; Kristine M. Lee

    2014-01-01

    The Fire, Fuel, and Smoke Science Program (FFS) of the U.S. Forest Service, Rocky Mountain Research Station, focuses on fundamental and applied research in wildland fire, from fire physics and fire ecology to fuels management and smoke emissions. Located at the Missoula Fire Sciences Laboratory in Montana, the scientists, engineers, technicians, and support staff in...

  12. Farm Fuel Alcohol Project: preliminary report on facility design

    Energy Technology Data Exchange (ETDEWEB)

    Pile, R S; Badger, P C; Roetheli, J C; Waddell, Jr, E L

    1979-09-01

    This report describes the design of a farm-based ethanol production system to be built by TVA at Muscle Shoals, Alabama. This facility will include cooking, fermentation, and distillation equipment to allow production of 8000 to 12,000 gallons of fuel ethanol during a three to four month period each year. Output will be about 10 gallons of 190-proof ethanol per hour. Present components are sized to allow 12 to 14 hour daily operation as a semi-continuous batch system. Intent of the project is to document equipment and energy requirements, ethanol yields, and feasibility of small farm-based ethanol plants for farm fuel self-sufficiency. Cooking and fermentation will be batch-type operations, and packed distillation columns will be used for separating ethanol from the fermented beer. Energy recovery and waste heat use are integrated when feasible. The fermented beer will be fed directly to the distillation columns without separation of solids. Although this is an area of concern, an economical method of separation could not be identified.

  13. The US Army Foreign Comparative Test fuel cell program

    Science.gov (United States)

    Bostic, Elizabeth; Sifer, Nicholas; Bolton, Christopher; Ritter, Uli; Dubois, Terry

    The US Army RDECOM initiated a Foreign Comparative Test (FCT) Program to acquire lightweight, high-energy dense fuel cell systems from across the globe for evaluation as portable power sources in military applications. Five foreign companies, including NovArs, Smart Fuel Cell, Intelligent Energy, Ballard Power Systems, and Hydrogenics, Inc., were awarded competitive contracts under the RDECOM effort. This paper will report on the status of the program as well as the experimental results obtained from one of the units. The US Army has interests in evaluating and deploying a variety of fuel cell systems, where these systems show added value when compared to current power sources in use. For low-power applications, fuel cells utilizing high-energy dense fuels offer significant weight savings over current battery technologies. This helps reduce the load a solider must carry for longer missions. For high-power applications, the low operating signatures (acoustic and thermal) of fuel cell systems make them ideal power generators in stealth operations. Recent testing has been completed on the Smart Fuel Cell A25 system that was procured through the FCT program. The "A-25" is a direct methanol fuel cell hybrid and was evaluated as a potential candidate for soldier and sensor power applications.

  14. Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Renfro, David G [ORNL; Chandler, David [ORNL; Cook, David Howard [ORNL; Ilas, Germina [ORNL; Jain, Prashant K [ORNL; Valentine, Jennifer R [ORNL

    2014-11-01

    Engineering design studies of the feasibility of conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel are ongoing at Oak Ridge National Laboratory (ORNL) as part of an effort sponsored by the U.S. Department of Energy s Global Threat Reduction Initiative (GTRI)/Reduced Enrichment for Research and Test Reactors (RERTR) program. The fuel type selected by the program for the conversion of the five high-power research reactors in the U.S. that still use HEU fuel is a new U-Mo monolithic fuel. Studies by ORNL have previously indicated that HFIR can be successfully converted using the new fuel provided (1) the reactor power can be increased from 85 MW to 100 MW and (2) the fuel can be fabricated to a specific reference design. Fabrication techniques for the new fuel are under development by the program but are still immature, especially for the complex aspects of the HFIR fuel design. In FY 2012, the program underwent a major shift in focus to emphasize developing and qualifying processes for the fabrication of reliable and affordable LEU fuel. In support of this new focus and in an effort to ensure that the HFIR fuel design is as suitable for reliable fabrication as possible, ORNL undertook the present study to propose and evaluate several alternative design features. These features include (1) eliminating the fuel zone axial contouring in the previous reference design by substituting a permanent neutron absorber in the lower unfueled region of all of the fuel plates, (2) relocating the burnable neutron absorber from the fuel plates of the inner fuel element to the side plates of the inner fuel element (the fuel plates of the outer fuel element do not contain a burnable absorber), (3) relocating the fuel zone inside the fuel plate to be centered on the centerline of the depth of the plate, and (4) reshaping the radial contour of the relocated fuel zone to be symmetric about this centerline. The present

  15. Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Renfro, David [ORNL; Chandler, David [ORNL; Cook, David [ORNL; Ilas, Germina [ORNL; Jain, Prashant [ORNL; Valentine, Jennifer [ORNL

    2014-10-30

    Engineering design studies of the feasibility of conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel are ongoing at Oak Ridge National Laboratory (ORNL) as part of an effort sponsored by the U.S. Department of Energy’s Global Threat Reduction Initiative (GTRI)/Reduced Enrichment for Research and Test Reactors (RERTR) program. The fuel type selected by the program for the conversion of the five high-power research reactors in the U.S. that still use HEU fuel is a new U-Mo monolithic fuel. Studies by ORNL have previously indicated that HFIR can be successfully converted using the new fuel provided (1) the reactor power can be increased from 85 MW to 100 MW and (2) the fuel can be fabricated to a specific reference design. Fabrication techniques for the new fuel are under development by the program but are still immature, especially for the “complex” aspects of the HFIR fuel design. In FY 2012, the program underwent a major shift in focus to emphasize developing and qualifying processes for the fabrication of reliable and affordable LEU fuel. In support of this new focus and in an effort to ensure that the HFIR fuel design is as suitable for reliable fabrication as possible, ORNL undertook the present study to propose and evaluate several alternative design features. These features include (1) eliminating the fuel zone axial contouring in the previous reference design by substituting a permanent neutron absorber in the lower unfueled region of all of the fuel plates, (2) relocating the burnable neutron absorber from the fuel plates of the inner fuel element to the side plates of the inner fuel element (the fuel plates of the outer fuel element do not contain a burnable absorber), (3) relocating the fuel zone inside the fuel plate to be centered on the centerline of the depth of the plate, and (4) reshaping the radial contour of the relocated fuel zone to be symmetric about this centerline. The

  16. Preliminary Thermal Hydraulic Analyses of the Conceptual Core Models with Tubular Type Fuel Assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Chae, Hee Taek; Park, Jong Hark; Park, Cheol

    2006-11-15

    A new research reactor (AHR, Advanced HANARO Reactor) based on the HANARO has being conceptually developed for the future needs of research reactors. A tubular type fuel was considered as one of the fuel options of the AHR. A tubular type fuel assembly has several curved fuel plates arranged with a constant small gap to build up cooling channels, which is very similar to an annulus pipe with many layers. This report presents the preliminary analysis of thermal hydraulic characteristics and safety margins for three conceptual core models using tubular fuel assemblies. Four design criteria, which are the fuel temperature, ONB (Onset of Nucleate Boiling) margin, minimum DNBR (Departure from Nucleate Boiling Ratio) and OFIR (Onset of Flow Instability Ratio), were investigated along with various core flow velocities in the normal operating conditions. And the primary coolant flow rate based a conceptual core model was suggested as a design information for the process design of the primary cooling system. The computational fluid dynamics analysis was also carried out to evaluate the coolant velocity distributions between tubular channels and the pressure drop characteristics of the tubular fuel assembly.

  17. Solid fuel block as an alternate fuel for cooking and barbecuing: Preliminary results

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, Monikankana [Center for Energy, Indian Institute of Technology Guwahati, Guwahati 781 039 (India); Mukunda, H.S.; Sridhar, G. [Combustion Gasification Propulsion Laboratory, Department of Aerospace Engineering, Indian Institute of Science Bangalore, Bangalore 560 012 (India)

    2009-04-15

    A large part of the rural people of developing countries use traditional biomass stoves to meet their cooking and heating energy demands. These stoves possess very low thermal efficiency; besides, most of them cannot handle agricultural wastes. Thus, there is a need to develop an alternate cooking contrivance which is simple, efficient and can handle a range of biomass including agricultural wastes. In this reported work, a highly densified solid fuel block using a range of low cost agro residues has been developed to meet the cooking and heating needs. A strategy was adopted to determine the best suitable raw materials, which was optimized in terms of cost and performance. Several experiments were conducted using solid fuel block which was manufactured using various raw materials in different proportions; it was found that fuel block composed of 40% biomass, 40% charcoal powder, 15% binder and 5% oxidizer fulfilled the requirement. Based on this finding, fuel blocks of two different configurations viz. cylindrical shape with single and multi-holes (3, 6, 9 and 13) were constructed and its performance was evaluated. For instance, the 13 hole solid fuel block met the requirement of domestic cooking; the mean thermal power was 1.6 kW{sub th} with a burn time of 1.5 h. Furthermore, the maximum thermal efficiency recorded for this particular design was 58%. Whereas, the power level of single hole solid fuel block was found to be lower but adequate for barbecue cooking application. (author)

  18. Preliminary evaluation of the air and fuel specific-impulse characteristics of several potential ram-jet fuels IV : hydrogen, a-methylnaphthalene, and carbon / Benson E. Gammon

    Science.gov (United States)

    Gammon, Benson E

    1951-01-01

    A preliminary analytical evaluation of the air and fuel specific-impulse characteristics of hydrogen, a-methylnapthalene, and graphite carbon has been made. Adiabatic constant-pressure combustion flame temperatures for each fuel at several equivalence ratios were calculated for an initial air temperature of 560 degrees R and a pressure of 2 atmospheres.

  19. Results of 200 KW fuel cell evaluation programs

    Energy Technology Data Exchange (ETDEWEB)

    Torrey, J.M.; Merten, G.P. [SAIC, San Diego, CA (United States); Binder, M.J. [Army Construction Engineering Research Labs., Champaign, IL (United States)] [and others

    1996-12-31

    Science Applications International Corporation (SAIC) has installed six monitoring systems on ONSI Corporation 200 kW phosphoric acid fuel cells. Three of the systems were installed for the U.S. Army Construction Engineering Research Laboratories (USACERL) which is coordinating the Department of Defense (DoD) fuel cell Demonstration Program and three were installed under a contract with the New York State Energy Research and Development Authority (NYSERDA). Monitoring of the three NYSERDA sites has been completed. Monitoring systems for the DoD fuel cells were installed in August, 1996 and thus no operating data was available at the time of this writing, but will be presented at the Fuel Cell Seminar. This paper will present the monitoring configuration and research approach for each program. Additionally, summary performance data is presented for the completed NYSERDA program.

  20. Segmented fuel irradiation program: investigation on advanced materials

    Energy Technology Data Exchange (ETDEWEB)

    Uchida, H. [NUPEC (Japan); Goto, K. [KEPCO, Osaka (Japan); Sabate, R. [A.N. Asco - C.N. Vandellos, Barcelona (Spain); Abeta, S.; Baba, T. [MHI, Nishi-Ku, Yokohama (Japan); Matias, E. de; Alonso, J. [ENUSA, Madrid (Spain)

    1999-07-01

    The Segmented Fuel Irradiation Program, started in 1991, is a collaboration between the Japanese organisations Nuclear Power Engineering Corporation (NUPEC), the Kansai Electric Power Co., Inc. (KEPCO) representing other Japanese utilities, and Mitsubishi Heavy Industries, Ltd. (MHI); and the Spanish Organisations Empresa Nacional de Electricidad, S.A. (ENDESA) representing A.N. Vandellos 2, and Empresa Nacional Uranio, S.A. (ENUSA); with the collaboration of Westinghouse. The objective of the Program is to make substantial contribution to the development of advanced cladding and fuel materials for better performance at high burn-up and under operational power transients. For this Program, segmented fuel rods were selected as the most appropriate vehicle to accomplish the aforementioned objective. Thus, a large number of fuel and cladding combinations are provided while minimising the total amount of new material, at the same time, facilitating an eventual irradiation extension in a test reactor. The Program consists of three major phases: phase I: design, licensing, fabrication and characterisation of the assemblies carrying the segmented rods (1991 - 1994); phase II: base irradiation of the assemblies at Vandellos 2 NPP, and on-site examination at the end of four cycles (1994-1999). Phase III: ramp testing at the Studsvik facilities and hot cell PIE (1996-2001). The main fuel design features whose effects on fuel behaviour are being analysed are: alloy composition (MDA and ZIRLO vs. Zircaloy-4); tubing texture; pellet grain size. The Program is progressing satisfactorily as planned. The base irradiation is completed in the first quarter of 1999, and so far, tests and inspections already carried out are providing useful information on the behaviour of the new materials. Also, the Program is delivering a well characterized fuel material, irradiated in a commercial reactor, which can be further used in other fuel behaviour experiments. The paper presents the main

  1. Fully Fueled TACOM Vehicle Storage Test Program.

    Science.gov (United States)

    1981-12-01

    AFLRL with a water bottom were tested as control samples. This fuel sample had been previously innoculated with a culture of Cladosporium resinae and was...turbid, light pink color * Containing active growth of Cladosporium resinae ** Sample was shaken and allowed to stand for 24 hours prior to obtaining

  2. 2013 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-12-01

    The 2013 Annual Progress Report summarizes fiscal year 2013 activities and accomplishments by projects funded by the DOE Hydrogen Program. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing; technology validation; safety, codes and standards; market transformation; and systems analysis.

  3. 2011 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    Satyapal, Sunita [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States)

    2011-11-01

    The 2011 Annual Progress Report summarizes fiscal year 2011 activities and accomplishments by projects funded by the DOE Hydrogen Program. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing; technology validation; safety, codes and standards; education; market transformation; and systems analysis.

  4. 2014 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2014-11-01

    The 2014 Annual Progress Report summarizes fiscal year 2014 activities and accomplishments by projects funded by the DOE Hydrogen Program. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing; technology validation; safety, codes and standards; market transformation; and systems analysis.

  5. 40 CFR 80.610 - What acts are prohibited under the diesel fuel sulfur program?

    Science.gov (United States)

    2010-07-01

    ... AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Motor Vehicle Diesel... supply, store or transport motor vehicle diesel fuel, NRLM diesel fuel, ECA marine fuel or heating oil... transport any diesel fuel for use in motor vehicle or nonroad engines that contains greater than...

  6. Program Area of Interest: Fuel Transformer Solid Oxide Fuel Cell

    Energy Technology Data Exchange (ETDEWEB)

    Norman Bessette; Douglas S. Schmidt; Jolyon Rawson; Rhys Foster; Anthony Litka

    2006-02-01

    The following report documents the technical approach and conclusions made by Acumentrics Corporation during latest budget period toward the development of a low cost 10kW tubular SOFC power system. The present program, guided under direction from the National Energy Technology Laboratory of the US DOE, is a nine-year cost shared Cooperative Agreement totaling close to $74M funded both by the US DOE as well as Acumentrics Corporation and its partners. The latest budget period ran from July of 2005 through December 2005. Work focused on cell technology enhancements as well as BOP and power electronics improvements and overall system design. Significant progress was made in increasing cell power enhancements as well as decreasing material cost in a drive to meet the SECA cost targets. The following report documents these accomplishments in detail as well as the layout plans for further progress in next budget period.

  7. 2015 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    Popovich, Neil

    2015-12-01

    In the past year, the DOE Hydrogen Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  8. 2012 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    2012-12-01

    In the past year, the DOE Hydrogen Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  9. 2016 Annual Progress Report: DOE Hydrogen and Fuel Cells Program

    Energy Technology Data Exchange (ETDEWEB)

    Satyapal, Sunita [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2017-02-01

    In the past year, the DOE Hydrogen Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  10. Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul

    2013-04-30

    The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

  11. Solid Polymer Electrolyte (SPE) fuel cell technology program

    Science.gov (United States)

    1979-01-01

    The overall objectives of the Phase IV Solid Polymer Electrolyte Fuel Cell Technology Program were to: (1) establish fuel cell life and performance at temperatures, pressures and current densities significantly higher than those previously demonstrated; (2) provide the ground work for a space energy storage system based on the solid polymer electrolyte technology (i.e., regenerative H2/O2 fuel cell); (3) design, fabricate and test evaluate a full-scale single cell unit. During this phase, significant progress was made toward the accomplishment of these objectives.

  12. Advanced Coal-Fueled Gas Turbine Program

    Energy Technology Data Exchange (ETDEWEB)

    Horner, M.W.; Ekstedt, E.E.; Gal, E.; Jackson, M.R.; Kimura, S.G.; Lavigne, R.G.; Lucas, C.; Rairden, J.R.; Sabla, P.E.; Savelli, J.F.; Slaughter, D.M.; Spiro, C.L.; Staub, F.W.

    1989-02-01

    The objective of the original Request for Proposal was to establish the technological bases necessary for the subsequent commercial development and deployment of advanced coal-fueled gas turbine power systems by the private sector. The offeror was to identify the specific application or applications, toward which his development efforts would be directed; define and substantiate the technical, economic, and environmental criteria for the selected application; and conduct such component design, development, integration, and tests as deemed necessary to fulfill this objective. Specifically, the offeror was to choose a system through which ingenious methods of grouping subcomponents into integrated systems accomplishes the following: (1) Preserve the inherent power density and performance advantages of gas turbine systems. (2) System must be capable of meeting or exceeding existing and expected environmental regulations for the proposed application. (3) System must offer a considerable improvement over coal-fueled systems which are commercial, have been demonstrated, or are being demonstrated. (4) System proposed must be an integrated gas turbine concept, i.e., all fuel conditioning, all expansion gas conditioning, or post-expansion gas cleaning, must be integrated into the gas turbine system.

  13. Syringe exchange programs in Brazil: preliminary assessment of 45 programs

    Directory of Open Access Journals (Sweden)

    Fonseca Elize Massard da

    2006-01-01

    Full Text Available The present study aims to evaluate the current operation of Brazilian syringe exchange programs (SEP. After consulting national and regional networks of people working in projects/ programs aiming to reduce drug-related harm, we identified 134 potential participant programs. Unfortunately, only 45 SEPs answered a survey, even after repeated attempts. The survey addressed: coverage, funding, procurement of basic supplies, managerial capacity, and the local political environment. Findings were triangulated with in-depth interviews with key informants. The main findings included: satisfactory adherence to the initiatives and adequate documentation, but deficiencies in terms of coverage and monitoring, and uneven procurement of resources. Program personnel work mostly on a provisional basis, despite the efforts of local coordinators. Most programs are funded by the National STDs/AIDS Program. A comprehensive agenda aiming to improve current operations should include: concerted efforts to improve local and regional databanks, incentives/sanctions toward full accountability of initiatives carried by the programs, and a genuine culture of monitoring and evaluation.

  14. Syringe exchange programs in Brazil: preliminary assessment of 45 programs

    Directory of Open Access Journals (Sweden)

    Elize Massard da Fonseca

    2006-04-01

    Full Text Available The present study aims to evaluate the current operation of Brazilian syringe exchange programs (SEP. After consulting national and regional networks of people working in projects/ programs aiming to reduce drug-related harm, we identified 134 potential participant programs. Unfortunately, only 45 SEPs answered a survey, even after repeated attempts. The survey addressed: coverage, funding, procurement of basic supplies, managerial capacity, and the local political environment. Findings were triangulated with in-depth interviews with key informants. The main findings included: satisfactory adherence to the initiatives and adequate documentation, but deficiencies in terms of coverage and monitoring, and uneven procurement of resources. Program personnel work mostly on a provisional basis, despite the efforts of local coordinators. Most programs are funded by the National STDs/AIDS Program. A comprehensive agenda aiming to improve current operations should include: concerted efforts to improve local and regional databanks, incentives/sanctions toward full accountability of initiatives carried by the programs, and a genuine culture of monitoring and evaluation.

  15. 75 FR 14669 - Regulation of Fuels and Fuel Additives: Changes to Renewable Fuel Standard Program

    Science.gov (United States)

    2010-03-26

    ... that the corn ethanol production co-product, distillers grains and solubles (DGS), is more efficient as... Renewable Fuel 3. Additional Control Cases Considered B. Renewable Fuel Production 1. Corn/Starch Ethanol a... Costs a. Corn Ethanol b. Cellulosic Ethanol i. Feedstock Costs ii. Production Costs for...

  16. 75 FR 26049 - Regulation of Fuels and Fuel Additives: Modifications to Renewable Fuel Standard Program

    Science.gov (United States)

    2010-05-10

    ... Technologies for Renewable Fuel Pathways The final RFS2 rule includes two corn ethanol pathways in Table 1 of... fuels such as ethanol and biodiesel. Regulated categories and entities affected by this action include... basic organic chemical manufacturers. Industry 424690 5169 Chemical and allied products...

  17. 75 FR 26025 - Regulation of Fuels and Fuel Additives: Modifications to Renewable Fuel Standard Program

    Science.gov (United States)

    2010-05-10

    ... Technologies for Renewable Fuel Pathways The final RFS2 rule includes two corn ethanol pathways in Table 1 of..., or renewable fuels such as ethanol and biodiesel. Regulated categories and entities affected by this... products merchant wholesalers. Industry 424710 5171 Petroleum bulk stations and terminals. Industry...

  18. A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

    2012-08-01

    This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

  19. Modeling the complete Otto cycle: Preliminary version. [computer programming

    Science.gov (United States)

    Zeleznik, F. J.; Mcbride, B. J.

    1977-01-01

    A description is given of the equations and the computer program being developed to model the complete Otto cycle. The program incorporates such important features as: (1) heat transfer, (2) finite combustion rates, (3) complete chemical kinetics in the burned gas, (4) exhaust gas recirculation, and (5) manifold vacuum or supercharging. Changes in thermodynamic, kinetic and transport data as well as model parameters can be made without reprogramming. Preliminary calculations indicate that: (1) chemistry and heat transfer significantly affect composition and performance, (2) there seems to be a strong interaction among model parameters, and (3) a number of cycles must be calculated in order to obtain steady-state conditions.

  20. Direct Methanol Fuel Cell Battery Replacement Program

    Science.gov (United States)

    2011-04-11

    Electrochemical Society Meeting, ABS#1089, Oct. 16th 2008, Hawaii, USA. 2. Hall, T.D.; Grice, C.R.; Swenson, L.R.; Smotkin, E.S., “Reversible and irreversible...degradation modes of DMFC anode catalysts”, 212th Electrochemical Society Meeting, ABS#819, Oct. 14th 2008, Hawaii, USA. 3. Yuan Zhang, James Cooper...Paul McGinn “Combinatorial Screening of Fuel Cell Catalysts” 211th Electrochemical Society Meeting, Phoenix, AZ, May, 2008 4. Hall, T.D.; Grice, Corey

  1. Preliminary Content Evaluation of the North Anna High Burn-Up Sister Fuel Rod Segments for Transportation in the 10-160B and NAC-LWT

    Energy Technology Data Exchange (ETDEWEB)

    Ketusky, E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-08-09

    The U.S. Department of Energy’s (DOE’s) Used Fuel Disposition Campaign (UFDC) Program has transported high-burnup nuclear sister fuel rods from a commercial nuclear power plant for purposes of evaluation and testing. The evaluation and testing of high-burnup used nuclear fuel is integral to DOE initiatives to collect information useful in determining the integrity of fuel cladding for future safe transportation of the fuel, and for determining the effects of aging, on the integrity of UNF subjected to extended storage and subsequent transportation. The UFDC Program, in collaboration with the U.S. Nuclear Regulatory Commission and the commercial nuclear industry, has obtained individual used nuclear fuel rods for testing. The rods have been received at Oak Ridge National Laboratory (ORNL) for both separate effects testing (SET) and small-scale testing (SST). To meet the research objectives, testing on multiple 6 inch fuel rod pins cut from the rods at ORNL will be performed at Pacific Northwest National Laboratory (PNNL). Up to 10 rod equivalents will be shipped. Options were evaluated for multiple shipments using the 10-160B (based on 4.5 rod equivalents) and a single shipment using the NAC-LWT. Based on the original INL/Virginia Power transfer agreement, the rods are assumed to 152 inches in length with a 0.374-inch diameter. This report provides a preliminary content evaluation for use of the 10-160B and NAC-LWT for transporting those fuel rod pins from ORNL to PNNL. This report documents the acceptability of using these packagings to transport the fuel segments from ORNL to PNNL based on the following evaluations: enrichment, A2 evaluation, Pu-239 FGE evaluation, heat load, shielding (both gamma and neutron), and content weight/structural evaluation.

  2. ENVIRONMENTAL TECHNOLOGY VERIFICATION (ETV) PROGRAM: FUEL CELLS

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) Environmental Technology Verification (ETV) Program evaluates the performance of innovative air, water, pollution prevention and monitoring technologies that have the potential to improve human health and the environment. This techno...

  3. Consolidated fuel reprocessing. Program progress report, April 1-June 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    This progress report is compiled from major contributions from three programs: (1) the Advanced Fuel Recycle Program at ORNL; (2) the Converter Fuel Reprocessing Program at Savannah River Laboratory; and (3) the reprocessing components of the HTGR Fuel Recycle Program, primarily at General Atomic and ORNL. The coverage is generally overview in nature; experimental details and data are limited.

  4. Fuel Tank Non-Nuclear Vulnerability Test Program

    Science.gov (United States)

    1975-02-01

    Pressure Rise lime vs JP-4 Temperature 115 vii i" r - 7 7. t n .-- LIST CF ILLUSTRATIONS (continued) FIGURE Paso 23 JP-4 Vapor Concentration vs Fuel...these parameters is considered random for any set of specified tesi : conditions, thereby rznuiring a statistical approach to the program. A statistical

  5. Solid Polymer Electrolyte (SPE) fuel cell technology, program review, phase 2

    Science.gov (United States)

    1976-01-01

    The purpose of the solid polymer electrolyte (SPE) fuel cell program is to advance the SPE fuel cell technology in four target areas. These areas are: (1) reduced fuel cell costs; (2) reduced fuel cell weight; (3) improved fuel cell efficiency; and (4) increased systems compatibility.

  6. Characterization of Bond Strength of U-Mo Fuel Plates Using the Laser Shockwave Technique: Capabilities and Preliminary Results

    Energy Technology Data Exchange (ETDEWEB)

    J. A. Smith; D. L. Cottle; B. H. Rabin

    2013-09-01

    This report summarizes work conducted to-date on the implementation of new laser-based capabilities for characterization of bond strength in nuclear fuel plates, and presents preliminary results obtained from fresh fuel studies on as-fabricated monolithic fuel consisting of uranium-10 wt.% molybdenum alloys clad in 6061 aluminum by hot isostatic pressing. Characterization involves application of two complementary experimental methods, laser-shock testing and laser-ultrasonic imaging, collectively referred to as the Laser Shockwave Technique (LST), that allows the integrity, physical properties and interfacial bond strength in fuel plates to be evaluated. Example characterization results are provided, including measurement of layer thicknesses, elastic properties of the constituents, and the location and nature of generated debonds (including kissing bonds). LST provides spatially localized, non-contacting measurements with minimum specimen preparation, and is ideally suited for applications involving radioactive materials, including irradiated materials. The theoretical principles and experimental approaches employed in characterizing nuclear fuel plates are described, and preliminary bond strength measurement results are discussed, with emphasis on demonstrating the capabilities and limitations of these methods. These preliminary results demonstrate the ability to distinguish bond strength variations between different fuel plates. Although additional development work is necessary to validate and qualify the test methods, these results suggest LST is viable as a method to meet fuel qualification requirements to demonstrate acceptable bonding integrity.

  7. Preliminary decommissioning plan for Clab (Central interim storage for spent fuels); Preliminaer avvecklingsplan foer Clab

    Energy Technology Data Exchange (ETDEWEB)

    Gatter, Patrik; Wikstroem, Nina [SWECO, Stockholm (Sweden); Hallberg, Bengt [Studsvik Nuclear AB, Nykoeping (Sweden)

    2005-12-15

    In the The Swedish Radiation Protection Authority's Regulations SSI FS 2002:04 and The Swedish Nuclear Power Inspectorate's Regulations SKI FS 2004:1 it is stated that the owner of a nuclear facility must have a preliminary plan for decommissioning of the plant. The present report is a preliminary plan for decommissioning the Central interim storage for spent fuels (Clab). Clab will be decommissioned when all spent fuels and reactor core components have been sent to final disposal. The time for the decommissioning is dependent on the time for phasing out the last Swedish nuclear reactor. At present it is thought that Clab will remain in operation until after year 2050. During the work with this project, nothing has been found that indicates that decommissioning Clab could be more complicated than other plants whose decommissioning is closer in time. On the contrary, smaller radiation doses to the personnel are expected, as well as limited amounts of low and medium activity waste. This plan will be updated and more detailed as the time for decommissioning approaches.

  8. Spent fuel disassembly and canning programs at the Barnwell Nuclear Fuel Plant (BNFP). [For storage or transport

    Energy Technology Data Exchange (ETDEWEB)

    Townes, III, George A.

    1980-10-01

    Methods of disassembling and canning spent fuel to allow more efficient storage are being investigated at the BNFP. Studies and development programs are aimed at dry disassembly of fuel to allow storage and shipment of fuel pins rather than complete fuel assemblies. Results indicate that doubling existing storage capacity or tripling the carrying capacity of existing transportation equipment is achievable. Disassembly could be performed in the BNFP hot cells at rates of about 12 to 15 assemblies per day.

  9. Preliminary assessment of off-season fuels for electricity generation at Indian sugar mills

    Energy Technology Data Exchange (ETDEWEB)

    Perlack, R.D. [Oak Ridge National Lab., TN (United States); Ranney, J.W. [Joint Inst. for Energy and Environment, Knoxville, TN (United States)

    1995-11-07

    This report on off-season fuels is part of a preliminary feasibility assessment to retrofit Indian sugar mills to cogenerate heat and power with sales of excess electricity to the local grid. To justify the high capital costs of retrofitting existing facilities, sugar mill operators must attempt to maximize the amount of power they sell to the local grid. This fact means that sugar mills must operate and sell power well-beyond the milling season, which typically lasts about 200 days. The purpose of this report is to assess and determine whether low cost and reliable sources of off-season fuels can be secured for two sugar mills (Simbhaoli and Daurala) within their respective sugar growing districts, located in western Uttar Pradesh. Off-season fuels under consideration include excess bagasse that is stored for off-season use, agricultural field residues (e.g., wheat straw), forest residues (e.g., bark and small limbs), and dedicated energy crops (short-rotation woody crops and herbaceous energy crops). Results of the pre-feasibility indicate that bagasse and some agricultural residues are available in sufficient quantity and may be available at reasonable cost.

  10. Non destructive examination of UN / U-Si fuel pellets using neutrons (preliminary assessment)

    Energy Technology Data Exchange (ETDEWEB)

    Bourke, Mark Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Vogel, Sven C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Voit, Stewart Lancaster [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mcclellan, Kenneth James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Losko, Adrian S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tremsin, Anton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-31

    Tomographic imaging and diffraction measurements were performed on nine pellets; four UN/ U Si composite formulations (two enrichment levels), three pure U3Si5 reference formulations (two enrichment levels) and two reject pellets with visible flaws (to qualify the technique). The U-235 enrichments ranged from 0.2 to 8.8 wt.%. The nitride/silicide composites are candidate compositions for use as Accident Tolerant Fuel (ATF). The monophase U3Si5 material was included as a reference. Pellets from the same fabrication batches will be inserted in the Advanced Test Reactor at Idaho during 2016. The goal of the Advanced Non-destructive Fuel Examination work package is the development and application of non-destructive neutron imaging and scattering techniques to ceramic and metallic nuclear fuels. Data reported in this report were collected in the LANSCE run cycle that started in September 2015 and ended in March 2016. Data analysis is ongoing; thus, this report provides a preliminary review of the measurements and provides an overview of the characterized samples.

  11. DOD Residential Proton Exchange Membrane (PEM) Fuel Cell Demonstration Program. Volume 1. Summary of the Fiscal Year 2001 Program

    Science.gov (United States)

    2004-02-01

    electricity, heat, and water There are several kinds of fuel cells, categorized by the type of electrolyte the re- action uses. This project used...Residential PEM Fuel Cell Demonstration Program.” Subse- quent funding in FY02 and FY03 has extended the Program, and has placed additional fuel...for large-scale Phos- phoric Acid Fuel Cells ( PAFC ), set the groundwork for program management. The release of a Broad Agency Announcement (BAA) for

  12. The DOE advanced gas reactor fuel development and qualification program

    Science.gov (United States)

    Petti, David; Maki, John; Hunn, John; Pappano, Pete; Barnes, Charles; Saurwein, John; Nagley, Scott; Kendall, Jim; Hobbins, Richard

    2010-09-01

    The high outlet temperatures and high thermal-energy conversion efficiency of modular high-temperature gas-cooled reactors (HTGRs) enable an efficient and cost-effective integration of the reactor system with non-electricity-generation applications, such as process heat and/or hydrogen production, for the many petrochemical and other industrial processes that require temperatures between 300°C and 900°C. The U.S. Department of Energy (DOE) has selected the HTGR concept for the Next Generation Nuclear Plant (NGNP) Project as a transformative application of nuclear energy that will demonstrate emissions-free nuclear-assisted electricity, process heat, and hydrogen production, thereby reducing greenhouse-gas emissions and enhancing energy security. The objective of the DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification program is to qualify tristructural isotropic (TRISO)-coated particle fuel for use in HTGRs. An overview of the program and recent progress is presented.

  13. Current status of Westinghouse tubular solid oxide fuel cell program

    Energy Technology Data Exchange (ETDEWEB)

    Parker, W.G. [Westinghouse Science and Technology Center, Pittsburgh, PA (United States)

    1996-04-01

    In the last ten years the solid oxide fuel cell (SOFC) development program at Westinghouse has evolved from a focus on basic material science to the engineering of fully integrated electric power systems. Our endurance for this cell is 5 to 10 years. To date we have successfully operated at power for over six years. For power plants it is our goal to have operated before the end of this decade a MW class power plant. Progress toward these goals is described.

  14. Proscriptive Bayesian Programming and Maximum Entropy: a Preliminary Study

    Science.gov (United States)

    Koike, Carla Cavalcante

    2008-11-01

    Some problems found in robotics systems, as avoiding obstacles, can be better described using proscriptive commands, where only prohibited actions are indicated in contrast to prescriptive situations, which demands that a specific command be specified. An interesting question arises regarding the possibility to learn automatically if proscriptive commands are suitable and which parametric function could be better applied. Lately, a great variety of problems in robotics domain are object of researches using probabilistic methods, including the use of Maximum Entropy in automatic learning for robot control systems. This works presents a preliminary study on automatic learning of proscriptive robot control using maximum entropy and using Bayesian Programming. It is verified whether Maximum entropy and related methods can favour proscriptive commands in an obstacle avoidance task executed by a mobile robot.

  15. HTGR Fuel Technology Program. Semiannual report for the period ending March 31, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-07-01

    This document reports the technical accomplishments of the HTGR Fuel Technology Program at GA Technologies Inc. during the first half of FY 83. The activities include the fuel process, fuel materials, fuel cycle, fission product transport, core component verification, and core technology transfer tasks necessary to support the design and development of a steam cycle/cogeneration (SC/C) version of the HTGR.

  16. The Australian Hydrogen and Fuel Cells Education Program

    Energy Technology Data Exchange (ETDEWEB)

    Luigi Bonadio [Senior Consultant Luigi Bonadio and Associates (Australia)

    2006-07-01

    The next generation of engineers and scientists will face great technical, economic and political challenges to satisfy increasing demands for a secure, reliable and affordable global energy system that maintains and enhances current standards of living. The Australian Hydrogen and Fuel Cells Education Program aims to bolster the quality and relevance of primary and secondary school teaching in emerging areas of science, technology and environmental/sustainability studies using hydrogen, in its capacity as a versatile energy carrier, as the educational basis for teacher and student learning. Critical advances in specific areas of hydrogen production, distribution, storage and end-use technologies arise when students are engaged to develop and apply a broad range of disciplinary and interdisciplinary knowledge and practical skills. A comprehensive hydrogen and fuel cell technology teaching module will be developed to complement existing fuels and energy curricula across Australian schools. The pilot program will be delivered via the collaboration of nine trial schools, a broad range of technical and pedagogy experts and representatives of professional bodies and industry. The program features essential and extensive teacher consultation, a professional learning and development course, industry site visits and a dedicated research and evaluation study. This initiative aims to bolster teacher literacy and student participation in the design, construction and operation of various hydrogen and fuel cell devices and extended activities. Students will reflect on and formally present their learning experiences via several dedicated fora including an awards ceremony where outstanding performance of leading schools, teachers and student groups within the cluster will be acknowledged. (authors)

  17. Preliminary conceptual designs for advanced packages for the geologic disposal of spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Westerman, R.E.

    1979-04-01

    The present study assumes that the spent fuel will be disposed of in mined repositories in continental geologic formations, and that the post-emplacement control of the radioactive species will be accomplished independently by both the natural barrier, i.e., the geosphere, and the engineered barrier system, i.e., the package components consisting of the stabilizer, the canister, and the overpack; and the barrier components external to the package consisting of the hole sleeve and the backfill medium. The present document provides an overview of the nature of the spent fuel waste; the general approach to waste containment, using the defense-in-depth philosophy; material options, both metallic and nonmetallic, for the components of the engineered barrier system; a set of strawman criteria to guide the development of package/engineered barrier systems; and four preliminary concepts representing differing approaches to the solution of the containment problem. These concepts use: a corrosion-resistant meta canister in a special backfill (2 barriers); a mild steel canister in a corrosion-resistant metallic or nonmetallic hole sleeve, surrounded by a special backfill (2 barriers); a corrosion-resistant canister and a corrosion-resistant overpack (or hole sleeve) in a special backfill (3 barriers); and a mild steel canister in a massive corrosion-resistant bore sleeve surrounded by a polymer layer and a special backfill (3 barriers). The lack of definitive performance requirements makes it impossible to evaluate these concepts on a functional basis at the present time.

  18. Consolidated Fuel Reprocessing Program. Progress report, January 1 to March 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Unger, W.E. (comp.)

    1979-06-01

    On Oct. 1, 1978, a transition phase was begun to concentrate all US fuel reprocessing research in one major program, the Consolidated Fuel Reprocessing Program (CFRP). The CFRP is organized into the following: process R and D, engineering research, engineering systems, technical support, HTGR fuel reprocessing, and pyrochemical and dry processing methods. Progress is reported in each area. (DLC)

  19. Liquid Tin Anode Direct Coal Fuel Cell Final Program Report

    Energy Technology Data Exchange (ETDEWEB)

    Tao, Thomas

    2012-01-26

    This SBIR program will result in improved LTA cell technology which is the fundamental building block of the Direct Coal ECL concept. As described below, ECL can make enormous efficiency and cost contributions to utility scale coal power. This program will improve LTA cells for small scale power generation. As described in the Commercialization section, there are important intermediate military and commercial markets for LTA generators that will provide an important bridge to the coal power application. The specific technical information from this program relating to YSZ electrolyte durability will be broadly applicable SOFC developers working on coal based SOFC generally. This is an area about which very little is currently known and will be critical for successfully applying fuel cells to coal power generation.

  20. Pathways to Commercial Success. Technologies and Products Supported by the Fuel Cell Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2010-08-01

    This report identifies the commercial and near-commercial (emerging) hydrogen and fuel cell technologies and products that resulted from Department of Energy support through the Fuel Cell Technologies Program in the Office of Energy Efficiency and Renewable Energy.

  1. Characterization of Zircaloy-4 tubing procured for fuel cladding research programs

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, R.H. (comp.)

    1976-06-14

    A quantity of Zircaloy-4 tubing (10.92 mm outside diameter by 0.635 mm wall thickness) was purchased specifically for use in a number of related fuel cladding research programs sponsored by the Division of Reactor Safety Research, Nuclear Regulatory Commission (NRC/RSR). Identical tubing (produced simultaneously and from the same ingot) was purchased concurrently by the Electric Power Research Institute (EPRI) for use in similar research programs sponsored by that organization. In this way, source variability and prior fabrication history were eliminated as parameters, thus permitting direct comparison (as far as as-received material properties are concerned) of experimental results from the different programs. The tubing is representative of current reactor technology. Consecutive serial numbers assigned to each tube identify the sequence of the individual tubes through the final tube wall reduction operation. The report presented documents the procurement activities, provides a convenient reference source of manufacturer's data and tubing distribution to the various users, and presents some preliminary characterization data. The latter have been obtained routinely in various research programs and are not complete. Although the number of analyses, tests, and/or examinations performed to date are insufficient to draw statistically valid conclusions with regard to material characterization, the data are expected to be representative of the as-received tubing. It is anticipated that additional characterizations will be performed and reported routinely by the various research programs that use the tubing.

  2. Post-irradiation examination and R and D programs using irradiated fuels at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Yong Bum; Min, Duck Kee; Kim, Eun Ka and others

    2000-12-01

    This report describes the Post-Irradiation Examination(PIE) and R and D programs using irradiated fuels at KAERI. The objectives of post-irradiation examination (PIE) for the PWR irradiated fuels, CANDU fuels, HANARO fuels and test fuel materials are to verify the irradiation performance and their integrity as well as to construct a fuel performance data base. The comprehensive utilization program of the KAERI's post-irradiation examination related nuclear facilities such as Post-Irradiation Examination Facility (PIEF), Irradiated Materials Examination Facility (IMEF) and HANARO is described.

  3. Preliminary Study of Lead-Oxide Cooled Fast Reactor with Natural Uranium as an Input Fuel with Reactor Shuffling Strategy

    Science.gov (United States)

    Mahmudah, Rida SN; Su’ud, Zaki

    2017-01-01

    A preliminary study of lead-oxide cooled fast reactor with natural uranium as an input fuel using reactor shuffling strategy has been conducted. In this study, reactor core is divided into four zone with the same volume, each zone use different uranium enrichment. The enrichment number is estimated so that in the end of reactor’s operation, we only need to add natural uranium as the fresh input fuel. This study used UN-PuN as the fuel and lead oxide as the coolant. Several parameter studies have been conducted to determine the most suitable input condition. It is confirmed in this study that with fuel : cladding : coolant ratio of 53 : 10 : 37, and uranium enrichment in the first to the fourth zone of 0%, 6.25%, 7.5% and 8%, respectively, the reactor can operate as long as 20 years of operation with terminal k-eff of 1.0004.

  4. NEPA implementation: The Department of Energy`s program to manage spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Shipler, D.B.

    1994-05-01

    The Department of Energy (DOE) is implementing the National Environmental Protection Act (NEPA) in its management of spent nuclear fuel. The DOE strategy is to address the short-term safety concerns about existing spent nuclear fuel, to study alternatives for interim storage, and to develop a long-range program to manage spent nuclear fuel. This paper discusses the NEPA process, the environmental impact statements for specific sites as well as the overall program, the inventory of DOE spent nuclear fuel, the alternatives for managing the fuel, and the schedule for implementing the program.

  5. Impacts of the Weatherization Assistance Program in fuel-oil heated houses

    Energy Technology Data Exchange (ETDEWEB)

    Levins, W.P.; Ternes, M.P.

    1994-09-01

    The U.S. DOE Weatherization Assistance Program (WAP) Division requested Oak Ridge National Laboratory to help design and conduct an up-to-date assessment of the Program. The evaluation includes five separate studies; the fuel oil study is the subject of this paper. The primary goal of the fuel-oil study was to provide a region-wide estimate of the space-heating fuel oil saved by the Program in the Northeast during the 1991 and 1992 program years. Other goals include assessing the cost effectiveness of the Program within the fuel-oil submarket, and identifying factors which caused fuel-oil savings to vary. This paper reports only the highlights from the fuel-oil study`s final report.

  6. Fuel performance improvement program. Quarterly progress report, April--June 1978. [LWR

    Energy Technology Data Exchange (ETDEWEB)

    Crouthamel, C.E. (comp.)

    1978-07-01

    The Fuel Performance Improvement Program has as its objective the identification and demonstration of fuel concepts with improved power ramp performance. Improved fuels are being sought to allow reduction or elimination of fuel related operating guidelines on nuclear power plants such that the fuel may be power maneuvered within the rates allowed by the system technical specifications. The program contains a combination of out-of-reactor studies, in-reactor experiments and in-reactor demonstrations. Fuel concepts initially being considered include annular pellets, cladding internally coated with graphite and packed-particle fuels. The performance capability of each concept will be compared to a reference fuel of contemporary pellet design by irradiations in the Halden Boiling Water Reactor. Fuel design and process development is being completed and fuel rod fabrication will begin for the Halden test rods and for the first series of in-reactor experiments. The in-reactor demonstrations are being performed in the Big Rock Point reactor to show that the concepts pose no undue risk to commercial operation. Additional concepts may be considered as the result of a state-of-the-technology review of fuel-cladding interaction and assessment of fuel concepts and the out-of-reactor studies. The results of the program will be used to establish the technical bases for design of fuels with improved power ramp performance.

  7. Phosphoric acid fuel cell power plant system performance model and computer program

    Science.gov (United States)

    Alkasab, K. A.; Lu, C. Y.

    1984-01-01

    A FORTRAN computer program was developed for analyzing the performance of phosphoric acid fuel cell power plant systems. Energy mass and electrochemical analysis in the reformer, the shaft converters, the heat exchangers, and the fuel cell stack were combined to develop a mathematical model for the power plant for both atmospheric and pressurized conditions, and for several commercial fuels.

  8. Preliminary design report: Babcock and Wilcox BR-100 100-ton rail/barge spent fuel shipping cask

    Energy Technology Data Exchange (ETDEWEB)

    None

    1990-02-01

    The purpose of this document is to provide information on burnup credit as applied to the preliminary design of the BR-100 shipping cask. There is a brief description of the preliminary basket design and the features used to maintain a critically safe system. Following the basket description is a discussion of various criticality analyses used to evaluate burnup credit. The results from these analyses are then reviewed in the perspective of fuel burnups expected to be shipped to either the final repository or a Monitored Retrievable Storage (MRS) facility. The hurdles to employing burnup credit in the certification of any cask are then outlines and reviewed. the last section gives conclusions reached as to burnup credit for the BR-100 cask, based on our analyses and experience. All information in this study refers to the cask configured to transport PWR fuel. Boiling Water Reactor (BWR) fuel satisfies the criticality requirements so that burnup credit is not needed. All calculations generated in the preparation of this report were based upon the preliminary design which will be optimized during the final design. 8 refs., 19 figs., 16 tabs.

  9. PRELIMINARY EVALUATION OF FeCrAl CLADDING AND U-Si FUEL FOR ACCIDENT TOLERANT FUEL CONCEPTS

    Energy Technology Data Exchange (ETDEWEB)

    Hales, J. D.; Gamble, K. A.

    2015-09-01

    Since the accident at the Fukushima Daiichi Nuclear Power Station, enhancing the accident tolerance of light water reactors (LWRs) has become an important research topic. In particular, the community is actively developing enhanced fuels and cladding for LWRs to improve safety in the event of accidents in the reactor or spent fuel pools. Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system, can tolerate loss of active cooling in the reactor core for a considerably longer time period during design-basis and beyond design-basis events while maintaining or improving the fuel performance during normal operations and operational transients. This paper presents early work in developing thermal and mechanical models for two materials that may have promise: U-Si for fuel, and FeCrAl for cladding. These materials would not necessarily be used together in the same fuel system, but individually have promising characteristics. BISON, the finite element-based fuel performance code in development at Idaho National Laboratory, was used to compare results from normal operation conditions with Zr-4/UO2 behavior. In addition, sensitivity studies are presented for evaluating the relative importance of material parameters such as ductility and thermal conductivity in FeCrAl and U-Si in order to provide guidance on future experiments for these materials.

  10. Simulated Coal-Gas-Fueled Molten Carbonate Fuel Cell Development Program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1992-08-01

    This final report summarizes the technical work performed under Department of Energy Contract DE-AC21-91MC27393, ``Simulated Coal- Gas-Fueled Molten Carbonate Fuel Cell Development Program.`` This work consists of five major tasks and their respective subtasks as listed below. A brief description of each task is also provided. The Stack Design Requirements task focused on requirements and specification for designing, constructing, and testing a nominal 100-kilowatt integrated stack and on requirements for the balance-of-plant equipment to support a 1000-kilowatt integrated stack demonstrator. The Stack Design Preparation task focused on the mechanical design of a 100-kilowatt stack comprised of 8-ft{sup 2} cells incorporating the new cell configuration and component technology improvements developed in the previous DOE MCFC contract. Electrode Casting focused on developing a faster drying solvent for use in the electrode tape casting process. Electrode Heat Treatment was directed at scaling up the laboratory continuous debinding process to a new full-size IFC debinding oven coupled to a continuous belt furnace that will both debind and sinter the electrodes in one continuous process train. Repeat Part Quality Assurance and Testing provided the appropriate effort to ensure consistent, high-quality, reproducible and comparable repeat parts.

  11. Simulated Coal-Gas-Fueled Molten Carbonate Fuel Cell Development Program

    Energy Technology Data Exchange (ETDEWEB)

    1992-08-01

    This final report summarizes the technical work performed under Department of Energy Contract DE-AC21-91MC27393, Simulated Coal- Gas-Fueled Molten Carbonate Fuel Cell Development Program.'' This work consists of five major tasks and their respective subtasks as listed below. A brief description of each task is also provided. The Stack Design Requirements task focused on requirements and specification for designing, constructing, and testing a nominal 100-kilowatt integrated stack and on requirements for the balance-of-plant equipment to support a 1000-kilowatt integrated stack demonstrator. The Stack Design Preparation task focused on the mechanical design of a 100-kilowatt stack comprised of 8-ft[sup 2] cells incorporating the new cell configuration and component technology improvements developed in the previous DOE MCFC contract. Electrode Casting focused on developing a faster drying solvent for use in the electrode tape casting process. Electrode Heat Treatment was directed at scaling up the laboratory continuous debinding process to a new full-size IFC debinding oven coupled to a continuous belt furnace that will both debind and sinter the electrodes in one continuous process train. Repeat Part Quality Assurance and Testing provided the appropriate effort to ensure consistent, high-quality, reproducible and comparable repeat parts.

  12. Simulated coal-gas-fueled molten carbonate fuel cell development program

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, W.H.

    1992-07-01

    In previous work, International Fuel Cells Corporation (EFC) found interactions between molten carbonate fuel cell cathode materials being considered as replacements for the presently used nickel oxide and matrix materials. Consequently, this work was conducted to screen additional new materials for mutual compatibility. As part of this program, experiments were performed to examine the compatibility of several candidate, alternative cathode materials with the standard lithium aluminate matrix material in the presence of electrolyte at cell potentials. Initial cathode candidates were materials lithium ferrite, yttrium iron garnet, lithium manganite and doped ceria which were developed by universities, national laboratories, or contractors to DOE, EPRI, or GRI. These investigations were conducted in laboratory scale experiments. None of the materials tested can directly replace nickel oxide or indicate greater stability of cell performance than afforded by nickel oxide. Specifically: (1) no further work on niobium doped ceria is warranted; (2) cobalt migration was found in the lithium ferrite cathode tested. This could possibly lead to shorting problems similiar to those encountered with nickel oxide; (3) Possible shorting problems may also exist with the proprietary dopant in YIG; (4) lithium ferrite and YIG cathode were not single phase materials. Assessment of the chemical stability, i.e., dopant loss, was severely impeded by dissolution of these second phases in the electrolyte; and (5) Magnesium doped lithium manganite warrants further work. Electrolytes should contain Mg ions to suppress dopant loss.

  13. Simulated coal-gas-fueled molten carbonate fuel cell development program. Topical report: Cathode compatibility tests

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, W.H.

    1992-07-01

    In previous work, International Fuel Cells Corporation (EFC) found interactions between molten carbonate fuel cell cathode materials being considered as replacements for the presently used nickel oxide and matrix materials. Consequently, this work was conducted to screen additional new materials for mutual compatibility. As part of this program, experiments were performed to examine the compatibility of several candidate, alternative cathode materials with the standard lithium aluminate matrix material in the presence of electrolyte at cell potentials. Initial cathode candidates were materials lithium ferrite, yttrium iron garnet, lithium manganite and doped ceria which were developed by universities, national laboratories, or contractors to DOE, EPRI, or GRI. These investigations were conducted in laboratory scale experiments. None of the materials tested can directly replace nickel oxide or indicate greater stability of cell performance than afforded by nickel oxide. Specifically: (1) no further work on niobium doped ceria is warranted; (2) cobalt migration was found in the lithium ferrite cathode tested. This could possibly lead to shorting problems similiar to those encountered with nickel oxide; (3) Possible shorting problems may also exist with the proprietary dopant in YIG; (4) lithium ferrite and YIG cathode were not single phase materials. Assessment of the chemical stability, i.e., dopant loss, was severely impeded by dissolution of these second phases in the electrolyte; and (5) Magnesium doped lithium manganite warrants further work. Electrolytes should contain Mg ions to suppress dopant loss.

  14. Evaluation of unthrottled combustion system options for light duty applications with future syncrude derived fuels. Alternative Fuels Utilization Program

    Energy Technology Data Exchange (ETDEWEB)

    Needham, J. R.; Cooper, B. M.; Norris-Jones, S. R.

    1982-12-01

    An experimental program examining the interaction between several fuel and light duty automotive engine combinations is detailed. Combustion systems addressed covered indirect and direct injection diesel and spark ignited stratified charge. Fuels primarily covered D2, naphtha and intermediate broadcut blends. Low ignition quality diesel fuels were also evaluated. The results indicate the baseline fuel tolerance of each combustion system and enable characteristics of the systems to be compared. Performance, gaseous and particulate emissions aspects were assessed. The data obtained assists in the selection of candidate combustion systems for potential future fuels. Performance and environmental penalties as appropriate are highlighted relative to the individual candidates. Areas of further work for increased understanding are also reviewed.

  15. Developing an Undergraduate Teaching Assistant Program in Communication: Values, Curriculum, and Preliminary Assessment.

    Science.gov (United States)

    Socha, Thomas J.

    1998-01-01

    Describes a case study of a Communication Undergraduate Teaching Assistant (UTA) program and reports a limited, preliminary assessment of the teaching effectiveness of 25 UTAs. Concludes by identifying various benefits and drawbacks of such programs and offers recommendations for departments interested in developing similar programs. (RS)

  16. Chemical Engineering Division fuel cycle programs. Quarterly progress report, October-December 1978

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M J; Ader, M; Barletta, R E

    1980-01-01

    In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, tungsten crucibles were successfully spun for use in laboratory-scale experiments. Corrosion testing of refractory metals and alloys in PDPM environments was done. Ceramic substrates were successfully coated with tungsten. Solubility measurements were made to determine Cd/Mg alloy composition and temperature at which dissolved Th will precipitate. Experiments were started to study the reduction of high-fired ThO/sub 2/ with Ca in a molten metal-molten salt system. Work on the fused salt electrolysis of CaO was started. Equipment for determining phase diagrams for U-Cu-Mg system was set up. The reaction of UO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ was studied as part of a project to identify chemically feasible nonaqueous fuel reprocessing methods. Work was continued on development of a flowsheet for reprocessing actinide oxides by extracting actinides into ammonium chloro-aluminate (and alternative salts) from a bismuth solution. Preparation of Th, U, and Pu nitrides after dissolution of spent fuel elements in molten tin is being studied. Leach rates of glass beads, pulverized beads, and beads encapsulated in a lead matrix with no protective envelope were studied. A method (employing no pressure or vacuum systems) of encapsulating various solid wastes in a lead metal matrix was developed and tested. A preliminary integration was made of earlier data on effects of impacts on metal-matrix waste forms.Leach migration experiments were compared with conventional infiltration experiments as methods of evaluating geologic formations as barriers to nuclide migration. The effect of the streaming potential on the rates of transport of radioactive I/sup -/ and Na/sup +/ through kaolinite columns was measured, as well as adsorption of iodide and iodate by several compounds; implications of the results upon the disposal of radioactive iodine are discussed.

  17. Preliminary plan for the qualification of the LEU/Th fuel cycle for the Fort St. Vrain HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Gulden, T.D.; Gainey, B.W.; Altschwager, C.J. (comps.)

    1980-03-01

    This plan was prepared to ensure that low-enriched uranium/thorium (LEU/Th) would be available as a backup to the highly enriched uranium/thorium (HEU/Th) fuel cycle currently being used in the Fort St. Vrain (FSV) high-temperature gas-cooled reactor (HTGR) in the event that the US nonproliferation policies require it. It describes the program that would be required to develop, qualify, and introduce an LEU/Th fuel cycle into the FSV HTGR on the earliest possible and most optimistic schedule. The results of the study indicate that licensing of the LEU/Th fuel cycle for FSV could be completed and fuel manufacturing could begin about 4.5 years from inception of the program.

  18. 2013 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-10-01

    This report summarizes comments from the Peer Review Panel at the 2013 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on May 13-17, 2013, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; market transformation; and systems analysis.

  19. 2011 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-09-01

    This report summarizes comments from the Peer Review Panel at the 2011 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on May 9-13, 2011, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; education; market transformation; and systems analysis.

  20. 2012 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2012-09-01

    This report summarizes comments from the Peer Review Panel at the 2012 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on May 14-18, 2012, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; education; market transformation; and systems analysis.

  1. 2014 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2014-10-01

    This report summarizes comments from the Peer Review Panel at the 2014 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on June 16-20, 2014, in Washington, DC. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; market transformation; and systems analysis.

  2. 2015 DOE Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2015-10-01

    This report summarizes comments from the Peer Review Panel at the 2015 DOE Hydrogen and Fuel Cells Program Annual Merit Review, held on June 8-12, 2015, in Arlington, Virginia. It covers the program areas of hydrogen production and delivery; hydrogen storage; fuel cells; manufacturing R&D; technology validation; safety, codes, and standards; market transformation; and systems analysis.

  3. 78 FR 45983 - Acceptability of Corrective Action Programs for Fuel Cycle Facilities

    Science.gov (United States)

    2013-07-30

    ...The U.S. Nuclear Regulatory Commission (NRC) is withdrawing draft NUREG-2154, ``Acceptability of Corrective Action Programs for Fuel Cycle Facilities,'' based on receipt and review of public comments. The draft NUREG provided guidance to NRC staff on how to determine whether a submittal for a Corrective Action Program (CAP), voluntarily submitted by fuel cycle facility licensees, was......

  4. 40 CFR 52.351 - United States Postal Service substitute Clean Fuel Fleet Program.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 3 2010-07-01 2010-07-01 false United States Postal Service substitute Clean Fuel Fleet Program. 52.351 Section 52.351 Protection of Environment ENVIRONMENTAL PROTECTION... § 52.351 United States Postal Service substitute Clean Fuel Fleet Program. Revisions to the...

  5. The DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification Program

    Energy Technology Data Exchange (ETDEWEB)

    David Petti; Hans Gougar; Gary Bell

    2005-05-01

    The Department of Energy has established the Advanced Gas Reactor Fuel Development and Qualification Program to address the following overall goals: Provide a baseline fuel qualification data set in support of the licensing and operation of the Next Generation Nuclear Plant (NGNP). Gas-reactor fuel performance demonstration and qualification comprise the longest duration research and development (R&D) task for the NGNP feasibility. The baseline fuel form is to be demonstrated and qualified for a peak fuel centerline temperature of 1250°C. Support near-term deployment of an NGNP by reducing market entry risks posed by technical uncertainties associated with fuel production and qualification. Utilize international collaboration mechanisms to extend the value of DOE resources. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, postirradiation examination (PIE) and safety testing, fuel performance modeling, and fission product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete fundamental understanding of the relationship between the fuel fabrication process, key fuel properties, the irradiation performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. Fuel performance modeling and analysis of the fission product behavior in the primary circuit are important aspects of this work. The performance models are considered essential for several reasons, including guidance for the plant designer in establishing the core design and operating limits, and demonstration to the licensing authority that the applicant has a thorough understanding of the in-service behavior of the fuel system. The fission product behavior task will also provide primary source term data needed for licensing. An overview of the program and recent progress will be presented.

  6. The DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification Program

    Energy Technology Data Exchange (ETDEWEB)

    David Petti; Hans Gougar; Gary Bell

    2005-05-01

    The Department of Energy has established the Advanced Gas Reactor Fuel Development and Qualification Program to address the following overall goals: Provide a baseline fuel qualification data set in support of the licensing and operation of the Next Generation Nuclear Plant (NGNP). Gas-reactor fuel performance demonstration and qualification comprise the longest duration research and development (R&D) task for the NGNP feasibility. The baseline fuel form is to be demonstrated and qualified for a peak fuel centerline temperature of 1250°C. Support near-term deployment of an NGNP by reducing market entry risks posed by technical uncertainties associated with fuel production and qualification. Utilize international collaboration mechanisms to extend the value of DOE resources. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, postirradiation examination (PIE) and safety testing, fuel performance modeling, and fission product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete fundamental understanding of the relationship between the fuel fabrication process, key fuel properties, the irradiation performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. Fuel performance modeling and analysis of the fission product behavior in the primary circuit are important aspects of this work. The performance models are considered essential for several reasons, including guidance for the plant designer in establishing the core design and operating limits, and demonstration to the licensing authority that the applicant has a thorough understanding of the in-service behavior of the fuel system. The fission product behavior task will also provide primary source term data needed for licensing. An overview of the program and recent progress will be presented.

  7. 40 CFR 80.500 - What are the implementation dates for the motor vehicle diesel fuel sulfur control program?

    Science.gov (United States)

    2010-07-01

    ... the motor vehicle diesel fuel sulfur control program? 80.500 Section 80.500 Protection of Environment... Motor Vehicle Diesel Fuel; Nonroad, Locomotive, and Marine Diesel Fuel; and ECA Marine Fuel General Information § 80.500 What are the implementation dates for the motor vehicle diesel fuel sulfur control...

  8. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

  9. Alameda-Contra Costa Transit District (AC Transit) Fuel Cell Transit Buses: Preliminary Evaluation Results

    Energy Technology Data Exchange (ETDEWEB)

    Chandler, K.; Eudy, L.

    2007-03-01

    This report provides an evaluation of three prototype fuel cell-powered transit buses operating at AC Transit in Oakland, California, and six baseline diesel buses similar in design to the fuel cell buses.

  10. Program description for the program Fuel program supply July 1, 2011 up to June 30, 2015; Programbeskrivning foer programmet Braensleprogrammet tillfoersel 1 juli 2011 till 30 juni 2015

    Energy Technology Data Exchange (ETDEWEB)

    2011-04-15

    The Fuel program supply is included as one of three programs in a cohesive commitment to increased, sustainable and efficient production and use of indigenous and renewable fuels that are implemented by the Swedish Energy Agency from July 1, 2011 to June 30, 2015. The program focuses on growing, maintenance and harvesting of biomass from forestry and agriculture. The program consists of three areas: - The sub-area Efficient forest fuel system consists of efforts to reduce costs, improve quality and increase the supply of forest fuels. - The sub-area Energy crops from agriculture consists of investments in issues related to tillage, construction, maintenance, harvesting and logistics for energy crops, and by an ongoing project on more efficient plant breeding of willow for new markets. - The sub-area Silviculture for increased biofuel production includes both forestry measures and new forms of cultivation of fast growing tree species for energy purposes. It does not address environmental issues, processing of fuels, fuel quality or processes in which fuel is converted to heat, electricity or fuel. Questions about conversion and processing as well as sustainability, environment and resource use are treated in the two parallel running programs, the Fuel program conversion and the Fuel program sustainability

  11. EPAct Alternative Fuel Transportation Program: State and Alternative Fuel Provider Fleet Compliance Annual Report; Fleet Compliance Results for MY 2013/FY 2014

    Energy Technology Data Exchange (ETDEWEB)

    2015-09-01

    Compliance rates for covered state government and alternative fuel provider fleets under the Alternative Fuel Transportation Program (pursuant to the Energy Policy Act or EPAct) are reported for MY 2013/FY 2014 in this publication.

  12. Thermionic Fuel Element performance: TFE Verification Program. Final test report

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The program objective is to demonstrate the technology readiness of a Thermionic Fuel Element (TFE) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full power life of 7 years. A TFE was designed that met the reliability and lifetime requirements for a 2 MW(e) conceptual reactor design. Analysis showed that this TFE could be used over the range of 0.5 to 5 megawatts. This was used as the basis for designing components for test and evaluation. The demonstration of a 7-year component lifetime capability was through the combined use of analytical models and accelerated, confirmatory tests in a fast test reactor. Iterative testing was performed in which the results of one test series led to evolutionary improvements in the next test specimens. The TFE components underwent screening and initial development testing in ex-reactor tests. Several design and materials options were considered for each component. As screening tests permitted, down selection occurred to very specific designs and materials. In parallel with ex-reactor testing, and fast reactor component testing, components were integrated into a TFE and tested in the TRIGA test reactor at GA. Realtime testing of partial length TFEs was used to test support, alignment and interconnective TFE components, and to verify TFE performance in-reactor with integral cesium reservoirs. Realtime testing was also used to verify the relation between TFE performance and fueled emitter swelling, to test the durability of intercell insulation, to check temperature distributions, and to verify the adequacy over time of the fission gas venting channels. Predictions of TFE lifetime rested primarily on the accelerated component testing results, as correlated and extended to realtime by the use of analytical models.

  13. Methodology and a preliminary data base for examining the health risks of electricity generation from uranium and coal fuels

    Energy Technology Data Exchange (ETDEWEB)

    El-Bassioni, A.A.

    1980-08-01

    An analytical model was developed to assess and examine the health effects associated with the production of electricity from uranium and coal fuels. The model is based on a systematic methodology that is both simple and easy to check, and provides details about the various components of health risk. A preliminary set of data that is needed to calculate the health risks was gathered, normalized to the model facilities, and presented in a concise manner. Additional data will become available as a result of other evaluations of both fuel cycles, and they should be included in the data base. An iterative approach involving only a few steps is recommended for validating the model. After each validation step, the model is improved in the areas where new information or increased interest justifies such upgrading. Sensitivity analysis is proposed as the best method of using the model to its full potential. Detailed quantification of the risks associated with the two fuel cycles is not presented in this report. The evaluation of risks from producing electricity by these two methods can be completed only after several steps that address difficult social and technical questions. Preliminary quantitative assessment showed that several factors not considered in detail in previous studies are potentially important. 255 refs., 21 figs., 179 tabs.

  14. Preliminary report on CX-2 N-inner fuel tube number 1055-8

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlken, L.E.; Wheeler, R.G.

    1963-02-07

    The real cost of metallurgical examination of irradiated fuel elements is several times that of fuels before irradiation. Since post-irradiation study is necessary to determine the performance of prototype fuel designs in a reactor environment, complete physical characterization before irradiation provides an economical and efficient basis for comparing experimental data. Without such comparative study, unexpected damage to fuels in the reactor would be difficult, if not impossible, to interpret. This report presents such a characterization of one fuel element from a group of fuels prototypic of the initial charge in Hanford`s N-Reactor. This fuel element, 1055-8, is significant because it belongs to the Production Work Request CX-2 family of elements.

  15. Test program on the release characteristics of Kr-85 from remote fuel fabrication process

    Energy Technology Data Exchange (ETDEWEB)

    Park, Geun Il; Lee, J. W.; Kim, S. S. [and others

    2003-01-01

    In order to investigate the release kinetics of Kr-85 fission gas during DUPIC fuel fabrication process using spent fuel materials, the test equipment and its procedure was developed. The purpose of this test involves the measurement of Kr-85 released during OREOX process in DUPIC fuel fabrication as well as the analysis of fission- gas release kinetics with the variation of fuel fabrication conditions. Gas monitoring system installed inside glove box was located at out-cell of DFDF(DUPIC Fuel Fabrication Facility) at which OREOX and tube furnaces have already installed inside hot cell. The use of glove box is aimed for preventing a gas release from sampling gas line under negative pressure. Based on the allowable discharge concentration of Kr-85 to environment and the preliminary analysis assuming total released amount a year, environmental impact according to Kr-85 measuring test would be minimal.

  16. Fuel performance improvement program. Quarterly/annual progress report, October 1977--September 1978. [BWR; PWR

    Energy Technology Data Exchange (ETDEWEB)

    Crouthamel, C.E. (comp.)

    1978-10-01

    This quarterly/annual report reviews and summarizes the activities performed in support of the Fuel Performance Improvement Program (FPIP) during Fiscal Year 1978 with emphasis on those activities that transpired during the quarter ending September 30, 1978. Significant progress has been made in achieving the primary objectives of the program, i.e., to demonstrate commercially viable fuel concepts with improved fuel - cladding interaction (FCI) behavior. This includes out-of-reactor experiments to support the fuel concepts being evaluated, initiation of instrumented test rod experiments in the Halden Boiling Water Reactor (HBWR), and fabrication of the first series of demonstration rods for irradiation in the Big Rock Point Reactor (BRPR).

  17. LWR fuel recycle program quarterly progress report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    Jarrett, J.H. (comp.)

    1977-08-01

    The LWR Fuel Recycle Program is designed to provide information needed by industry to close the back end of the commercial light water reactor (LWR) fuel cycle. Included in this program are activities in support of specific design studies as well as activities with more general application to fuel recycle technology: economic and environmental studies; spent fuel receipt and storage; head-end processes; off-gas treatment; purex process (solvent extraction); finishing processes; waste management; environmental effects; and general support. 11 figures, 7 tables. (DLC)

  18. A Preliminary Assessment of a Deep Borehole disposal of Spent Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Younmyoung; Jeon, Jongtae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Deep borehole disposal (DBD) of such radioactive waste as spent nuclear fuels (SFs) and other waste forms has been investigating mainly at Sandia National Labs for the US DOE as an alternative option. DBD can give advantages over less deep geological disposal since the disposal of wastes at a great depth where a low degree of permeability in the potentially steady rock condition will be beneficial for nuclide movement. Groundwater in the deep basement rock can even have salinity and less chance to mix with groundwater above. The DBD concept is quite straightforward and even simple: Waste canisters are simply emplaced in the lower 2 km part of the borehole down to 5 km deep. Through this study, a conceptual DBD is assessed for a similar case as the US DOE's approach, in which 400 SF canisters are to be emplaced at a deep bottom between 3km and 5km depths, upon which an additional 1km-thick compacted bentonite is overbuffered, and the remaining upper part of the borehole is backfilled again with a mixture of crushed rock and bentonite. Then, the total 5km-deep borehole has three zones: a disposal zone at the bottom 2km, a buffer zone at the next 1km, and backfill zone at the rest top 2km, as illustrated conceptually in Fig. 1. To demonstrate the feasibility in view of long-term radiological safety, a rough model for a safety assessment of this conceptual deep borehole repository system, providing detailed models for nuclide transport in and around the geosphere and biosphere under normal nuclide release scenarios that can occur after a closure of the repository, has been developed using GoldSim. A simple preliminary result in terms of the dose exposure rate from a safety assessment of the DBD is also presented and compared to the case of direct disposal of SFs in a KBS-3V vertical type repository, carried out in previous studies. For different types and shapes of repositories at each different depth, direct comparison between a DBD and a KBS-3 type disposal of

  19. Zero-gravity cloud physics laboratory: Experiment program definition and preliminary laboratory concept studies

    Science.gov (United States)

    Eaton, L. R.; Greco, E. V.

    1973-01-01

    The experiment program definition and preliminary laboratory concept studies on the zero G cloud physics laboratory are reported. This program involves the definition and development of an atmospheric cloud physics laboratory and the selection and delineations of a set of candidate experiments that must utilize the unique environment of zero gravity or near zero gravity.

  20. 2011 Annual Progress Report: DOE Hydrogen and Fuel Cells Program (Book)

    Energy Technology Data Exchange (ETDEWEB)

    2011-11-01

    In the past year, the DOE Hydrogen and Fuel Cells Program (the Program) made substantial progress toward its goals and objectives. The Program has conducted comprehensive and focused efforts to enable the widespread commercialization of hydrogen and fuel cell technologies in diverse sectors of the economy. With emphasis on applications that will effectively strengthen our nation's energy security and improve our stewardship of the environment, the Program engages in research, development, and demonstration of critical improvements in the technologies. Highlights of the Program's accomplishments can be found in the sub-program chapters of this report.

  1. Voluntary Truck and Bus Fuel-Economy-Program marketing plan. Final technical report, September 29, 1980-January 29, 1982

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    The aim of the program is to improve the utilization of fuel by commercial trucks and buses by updating and implementing specific approaches for educating and monitoring the trucking industry on methods and means of conserving fuels. The following outlines the marketing plan projects: increase use of program logo by voluntary program members and others; solicit trade publication membership and support; brief Congressional delegations on fuel conservation efforts; increase voluntary program presence before trade groups; increase voluntary program presence at truck and trade shows; create a voluntary program display for use at trade shows and in other areas; review voluntary program graphics; increase voluntary program membership; and produce placemats carrying fuel conservation messages; produce a special edition of Fuel Economy News, emphasizing the driver's involvement in fuel conservation; produce posters carrying voluntary program fuel conservation message. Project objectives, activities, and results for each project are summarized.

  2. Charcoal-Oil Mixture as an Alternative Fuel: A Preliminary Study

    Directory of Open Access Journals (Sweden)

    Roila Awang

    2009-01-01

    Full Text Available The fast depletion of fuel oil and continuous increase in the demand for power is a global issue. The world energy consumption is projected to grow at an average of 2.7-3.7% from 1996 to 2010. Therefore search for alternative fuel is highly prioritized. Thus this study presents the results on the characteristic of charcoal-oil mixture as an alternative fuel. The calorific value, ash content and stability of the mixture are determined.

  3. OSU TOMF Program Site Selection and Preliminary Concept Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Spadling, Steve [Oklahoma State Univ., Stillwater, OK (United States)

    2012-05-10

    The purpose of this report is to confirm the programmatic requirements for the new facilities, identify the most appropriate project site, and develop preliminary site and building concepts that successfully address the overall project goals and site issues. These new facilities will be designed to accommodate the staff, drivers and maintenance requirements for the future mixed fleet of passenger vehicles, Transit Style Buses and School Buses.

  4. Contextualizing avian mortality. A preliminary appraisal of bird and bat fatalities from wind, fossil-fuel, and nuclear electricity

    Energy Technology Data Exchange (ETDEWEB)

    Sovacool, Benjamin K. [Energy Governance Program, Centre on Asia and Globalisation, Lee Kuan Yew School of Public Policy, National University of Singapore, Singapore 259772 (Singapore)

    2009-06-15

    This article explores the threats that wind farms pose to birds and bats before briefly surveying the recent literature on avian mortality and summarizing some of the problems with it. Based on operating performance in the United States and Europe, this study offers an approximate calculation for the number of birds killed per kWh generated for wind electricity, fossil-fuel, and nuclear power systems. The study estimates that wind farms and nuclear power stations are responsible each for between 0.3 and 0.4 fatalities per gigawatt-hour (GWh) of electricity while fossil-fueled power stations are responsible for about 5.2 fatalities per GWh. While this paper should be respected as a preliminary assessment, the estimate means that wind farms killed approximately seven thousand birds in the United States in 2006 but nuclear plants killed about 327,000 and fossil-fueled power plants 14.5 million. The paper concludes that further study is needed, but also that fossil-fueled power stations appear to pose a much greater threat to avian wildlife than wind and nuclear power technologies. (author)

  5. Contextualizing avian mortality: A preliminary appraisal of bird and bat fatalities from wind, fossil-fuel, and nuclear electricity

    Energy Technology Data Exchange (ETDEWEB)

    Sovacool, Benjamin K. [Energy Governance Program, Centre on Asia and Globalisation, Lee Kuan Yew School of Public Policy, National University of Singapore, Singapore 259772 (Singapore)], E-mail: bsovacool@nus.edu.sg

    2009-06-15

    This article explores the threats that wind farms pose to birds and bats before briefly surveying the recent literature on avian mortality and summarizing some of the problems with it. Based on operating performance in the United States and Europe, this study offers an approximate calculation for the number of birds killed per kWh generated for wind electricity, fossil-fuel, and nuclear power systems. The study estimates that wind farms and nuclear power stations are responsible each for between 0.3 and 0.4 fatalities per gigawatt-hour (GWh) of electricity while fossil-fueled power stations are responsible for about 5.2 fatalities per GWh. While this paper should be respected as a preliminary assessment, the estimate means that wind farms killed approximately seven thousand birds in the United States in 2006 but nuclear plants killed about 327,000 and fossil-fueled power plants 14.5 million. The paper concludes that further study is needed, but also that fossil-fueled power stations appear to pose a much greater threat to avian wildlife than wind and nuclear power technologies.

  6. Development of a mobility and fuel strategy for Germany. Preliminary investigation; Entwicklung einer Mobilitaets- und Kraftstoffstrategie fuer Deutschland. Voruntersuchung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-08-15

    Mobility is a key element in our society and often synonymous with traffic. It is desirable to secure a clean and diversified energy supply, to design a more sustainable transport structure and to minimize the burden on people and environment. This requires an updating of the fuel strategy 2004 and its progress toward a comprehensive mobility strategy and fuel strategy. Under this aspect, the contribution under consideration presents a preliminary investigation of the development of a mobility strategy and fuel strategy in Germany. Over the past ten years, the transport sector has reduced its energy consumption only slightly. The targets for the energy reduction now are -10 % up to 2020 and -40 % up to 2050. The transport sector challenges a significant contribution to the reduction of greenhouse gas emissions. In order to advance the necessary energy political as well as climate political changes the Federal Government wants to develop a comprehensive mobility strategy and fuel strategy. For this purpose, the contribution under consideration provides nine concrete recommendations for action for this.

  7. Preliminary safety analysis for offgas treatment system of DUPIC fuel manufacturing process at DFDF

    Energy Technology Data Exchange (ETDEWEB)

    Shin, J. M.; Lee, H. H.; Park, J. J.; Yang, M. S

    2000-09-01

    DUPIC fuel fabrication process is a dry processing technology to manufacture CANDU compatible fuel through a direct refabrication process from spent PWR fuel. DUPIC fuel fabrication process consists of the slitting of the spent PWR fuel rods, OREOX processing, homogeneous mixing, pelletizing and sintering. All these processes should be conducted by remote means in a M6 hot cell at IMEF. Since there is a lot of highly radioactive spent fuel(200 kg) to be used in DUPIC fuel fabrication process, safety analysis on DFDF facility is very important to improve the safety of hot cell and to reduce the dose exposure to operator. This report describes the design of IMEF facility, manufacturing equipment and process, offgas treatment system necessary for DUPIC fuel manufacturing process. Also, it provides the flow chart of arising and activity for each nuclide in offgas treatment system and final arising and activity for gaseous waste discharged from offgas treatment equipment into inside of M6 cell during OREOX and sintering processes in DUPIC fuel manufacturing process.

  8. Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K.M.; Kelman, J.A.

    1982-08-01

    Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described.

  9. Assessment of the environmental aspects of the DOE phosphoric acid fuel cell program

    Science.gov (United States)

    Lundblad, H. L.; Cavagrotti, R. R.

    1983-01-01

    The likely facets of a nationwide phosphoric acid fuel cell (PAFC) power plant commercial system are described. The beneficial and adverse environmental impacts produced by the system are assessed. Eleven specific system activities are characterized and evaluated. Also included is a review of fuel cell technology and a description of DOE's National Fuel Cell Program. Based on current and reasonably foreseeable PAFC characteristics, no environmental or energy impact factor was identified that would significantly inhibit the commercialization of PAFC power plant technology.

  10. Preliminary Study on Method of Quantitative Measurement of Nuclear Fuel Rod by Neutron CT at CARR

    Institute of Scientific and Technical Information of China (English)

    WEI; Guo-hai; HAN; Song-bai; WANG; Hong-li; HE; Lin-feng; WANG; Yu; WU; Mei-mei; LIU; Yun-tao; CHEN; Dong-feng

    2015-01-01

    Neutron CT technique was applied to the quantitative measurement of the key parameters of nuclear fuel rods at China Advanced Research Reactor(CARR).The sample of dummy nuclear fuel rod was rotated in 180°range,and 900neutron projections were obtained.The 3-D neutron

  11. National Evaluation of the Weatherization Assistance Program: Preliminary Evaluation Plan for Program Year 2006

    Energy Technology Data Exchange (ETDEWEB)

    Ternes, Mark P [ORNL; Schweitzer, Martin [ORNL; Tonn, Bruce Edward [ORNL; Schmoyer, Richard L [ORNL; Eisenberg, Joel Fred [ORNL

    2007-02-01

    federal, state, and local initiatives. For example, the use of computerized audits has increased, cooling and baseload measures have been added, weatherization approaches tailored to the unique construction characteristics of mobile homes have been developed, the weatherization of large multifamily buildings has expanded and become more sophisticated, the flexibility to improve 'energy-related' health and safety has been provided, and leveraging with utilities, other state programs, and owners of large multifamily buildings has increased considerably. The Department of Energy tasked ORNL with planning the new evaluation in light of its experience in conducting the previous national evaluation and the metaevaluations. This preliminary evaluation plan, developed by ORNL, documents how the new national evaluation will be performed. In the remaining portion of this section, the purpose and fundamental questions the evaluation will address are identified and how these questions were derived is discussed.

  12. Preliminary Investigation of Candidate Materials for Use in Accident Resistant Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Jason M. Harp; Paul A. Lessing; Blair H. Park; Jakeob Maupin

    2013-09-01

    As part of a Collaborative Research and Development Agreement (CRADA) with industry, Idaho National Laboratory (INL) is investigating several options for accident resistant uranium compounds including silicides, and nitrides for use in future light water reactor (LWR) fuels. This work is part of a larger effort to create accident tolerant fuel forms where changes to the fuel pellets, cladding, and cladding treatment are considered. The goal fuel form should have a resistance to water corrosion comparable to UO2, have an equal to or larger thermal conductivity than uranium dioxide, a melting temperature that allows the material to stay solid under power reactor conditions, and a uranium loading that maintains or improves current LWR power densities. During the course of this research, fuel fabricated at INL will be characterized, irradiated at the INL Advanced Test Reactor, and examined after irradiation at INL facilities to help inform industrial partners on candidate technologies.

  13. Preliminary Technical Risk Analysis for the Geothermal Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    2009-01-18

    This report explains the goals, methods, and results of a probabilistic analysis of technical risk for a portfolio of R&D projects in the DOE Geothermal Technologies Program (The Program). The analysis is a task by Princeton Energy Resources International, LLC, in support of the National Renewable Energy Laboratory on behalf of the Program. The main challenge in the analysis lies in translating R&D results to a quantitative reflection of technical risk for a key Program metric: levelized cost of energy (LCOE).

  14. Preliminary diagnosis of areal density in the deuterium fuel capsule by proton measurement at SG-III facility

    Science.gov (United States)

    Zhang, Xing; Luo, Xing; Zheng, Jianhua; Chen, Zhongjing; Yan, Ji; Pu, Yudong; Jiang, Wei; Huang, Tianxuan; Yang, Zhenghua; Yang, Pin; Tang, Qi; Song, Zifeng; Jiang, Shao'en; Liu, Shenye; Yang, Jiamin; Wang, Feng

    2017-05-01

    Areal density (ρR) is one of the crucial parameters in the inertial confinement fusion. Measurement of the fusion products is a more feasible method to diagnose ρR than other methods, such as X-ray. In the capsules filled with D2 fuel or D-3He fuel, proton is an ideal probe to diagnose the implosion ρR in different emission times and directions by measurements of the proton yields and spectra. By D-D reaction protons and D-3He reaction protons, the diagnostics of the total and fuel ρR, ρR evolution, implosion asymmetry and mix effect have been demonstrated at OMEGA and NIF facilities. Also some advanced proton diagnostics instruments are developed with a high level capability. Preliminary diagnosis of ρR in the deuterium involved fuel capsules by measurement of protons at SG-III facility was implemented. A fusion product emission and transport code by Monte-Carlo method was developed. The primary and secondary protons emission and transport in the fuel and shell plasmas were able to be simulated. The relations of the proton energy loss and the secondary proton yields with the areal density were inspected. Several proton spectrometers have been built up at SG-III facility, such as a step ranged filter (SRF) proton spectrometer and a wedged range filter (WRF) proton spectrometer. Some proton response simulation codes and the codes for proton spectra reconstruction were also developed. The demonstrations of ρR diagnostics at SG-III facility by D-D reaction and D-3He reaction proton spectra measurements are presented.

  15. Preliminary Analysis for Flow Blockage of Plate Fuel using a Commercial CFD Code

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong-Pil; Park, Suki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    A plate-type fuel assembly is widely used in the research reactors in order to enhance power density. This type fuel assembly consists of a number of fuel plates, supporting plates, and narrow rectangular cooling channels between the fuel plates. Due to the narrow rectangular channels consisting of parallel plate fuels and side plates, the cooling channels are isolated from each other so that the cross flow between the channels are completely restricted. When blockage at the inlet of the channel occurs, therefore, the coolant flow through the blocked channel will be greatly reduced or completely interrupted. Accordingly, the blocked channel loses its own cooling capability. This event may cause initiation of nucleate boiling and two phase flow instability (FI) in the blocked channel. In recent years, CFD analyses of flow blockage of a research reactor have been performed by many researchers. The present study reports a 3-dimensional CFD simulation using two-phase model for flow blockage of two channels of a plate-type fuel assembly. The present result shows limited information since the simulation is working at the moment. However, the present study indicates that it is possible to predict a damage propagation of a plate-type fuel assembly due to the flow instability caused by flow blockage using a commercial CFD code.

  16. Preliminary Technical Risk Analysis for the Geothermal Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    McVeigh, J.; Cohen, J.; Vorum, M.; Porro, G.; Nix, G.

    2007-03-01

    This report explains the goals, methods, and results of a probabilistic analysis of technical risk for a portfolio of R&D projects in the DOE Geothermal Technologies Program ('the Program'). The analysis is a task by Princeton Energy Resources International, LLC (PERI), in support of the National Renewable Energy Laboratory (NREL) on behalf of the Program. The main challenge in the analysis lies in translating R&D results to a quantitative reflection of technical risk for a key Program metric: levelized cost of energy (LCOE). This requires both computational development (i.e., creating a spreadsheet-based analysis tool) and a synthesis of judgments by a panel of researchers and experts of the expected results of the Program's R&D.

  17. Bitumen/Water Emulsions as Fuels for High-Speed Ci Engines Preliminary Investigations

    DEFF Research Database (Denmark)

    Schramm, Jesper; Sigvardsen, R.; Forman, M.

    2003-01-01

    Mixtures of bitumen and water, are cheap fuel alternatives for combustion engines. There are, however, several problems that have to be solved before these fuels can be applied in high-speed diesel engines. These are: - emulsion break up due to high temperature or high shear stress in the injection...... system - high content of heavy metals - high emissions of particulate matter and PAH This investigation deals with the problem of separation due to high shear stress in the injection system. It is shown that the viscosity of the injected fuel can be used to estimate whether the emulsion has separated...

  18. Super-Efficient Refrigerator Program (SERP) evaluation volume 2: Preliminary impact and market transformation assessment

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A.D.; Conger, R.L.

    1996-08-01

    The Super Efficient Refrigerator Program (SERP) is a collaborative utility program intended to transform the market for energy-efficient and environmentally friendly refrigerators. It is one of the first examples of a large-scale {open_quotes}market transformation{close_quotes} energy efficiency program. This report documents the preliminary impact and market transformation evaluation of SERP ({open_quotes}the Program{close_quotes}). Pacific Northwest National Laboratory (PNNL) conducted this evaluation for the U.S. Department of Energy. This study focuses on the preliminary impact evaluation and market transformation assessment, but also presents limited process evaluation information. It is based on interviews with refrigerator dealers and manufacturers, interviews with utility participants, industry data, and information from the Program administrators. Results from this study complement those from prior process evaluation also conducted by PNNL. 42 refs., 5 figs., 4 tabs.

  19. The new revision of NPP Krsko decommissioning, radioactive waste and spent fuel management program: analyses and results

    Energy Technology Data Exchange (ETDEWEB)

    Zeleznik, Nadja; Kralj, Metka [ARAO, Parmova 53, 1000 Ljubljana (Slovenia); Lokner, Vladimir; Levanat, Ivica; Rapic, Andrea [APO, Savska 41, Zagreb (Croatia); Mele, Irena [IAEA, Vienna (Austria)

    2010-07-01

    The preparation of the new revision of the Decommissioning and Spent Fuel (SF) and Low and Intermediate level Waste (LILW) Disposal Program for the NPP Krsko (Program) started in September 2008 after the acceptance of the Term of Reference for the work by Intergovernmental Committee responsible for implementation of the Agreement between the governments of Slovenia and Croatia on the status and other legal issues related to investment, exploitation, and decommissioning of the Nuclear power plant Krsko. The responsible organizations, APO and ARAO together with NEK prepared all new technical and financial data and relevant inputs for the new revision in which several scenarios based on the accepted boundary conditions were investigated. The strategy of immediate dismantling was analyzed for planned and extended NPP life time together with linked radioactive waste and spent fuel management to calculate yearly annuity to be paid by the owners into the decommissioning funds in Slovenia and Croatia. The new Program incorporated among others new data on the LILW repository including the costs for siting, construction and operation of silos at the location Vrbina in Krsko municipality, the site specific Preliminary Decommissioning Plan for NPP Krsko which included besides dismantling and decontamination approaches also site specific activated and contaminated radioactive waste, and results from the referenced scenario for spent fuel disposal but at very early stage. Important inputs for calculations presented also new amounts of compensations to the local communities for different nuclear facilities which were taken from the supplemented Slovenian regulation and updated fiscal parameters (inflation, interest, discount factors) used in the financial model based on the current development in economical environment. From the obtained data the nominal and discounted costs for the whole nuclear program related to NPP Krsko which is jointly owned by Slovenia and Croatia have

  20. Vehicle Technologies and Fuel Cell Technologies Program: Prospective Benefits Assessment Report for Fiscal Year 2016

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, T. S. [Argonne National Lab. (ANL), Argonne, IL (United States); Taylor, C. H. [TA Engineering, Inc., Catonsville, MD (United States); Moore, J. S. [TA Engineering, Inc., Catonsville, MD (United States); Ward, J. [United States Department of Energy, Washington, DC (United States). Office of Energy Efficiency and Renewable Energy

    2016-02-23

    Under a diverse set of programs, the Vehicle Technologies and Fuel Cell Technologies offices of DOE’s Office of Energy Efficiency and Renewable Energy invest in research, development, demonstration, and deployment of advanced vehicle, hydrogen production, delivery and storage, and fuel cell technologies. This report estimates the benefits of successfully developing and deploying these technologies (a “Program Success” case) relative to a base case (the “No Program” case). The Program Success case represents the future with completely successful deployment of Vehicle Technologies Office (VTO) and Fuel Cell Technologies Office (FCTO) technologies. The No Program case represents a future in which there is no contribution after FY 2016 by the VTO or FCTO to these technologies. The benefits of advanced vehicle, hydrogen production, delivery and storage, and fuel cell technologies were estimated on the basis of differences in fuel use, primary energy use, and greenhouse gas (GHG) emissions from light-, medium- and heavy-duty vehicles, including energy and emissions from fuel production, between the base case and the Program Success case. Improvements in fuel economy of various vehicle types, growth in the stock of fuel cell vehicles and other advanced technology vehicles, and decreased GHG intensity of hydrogen production and delivery in the Program Success case over the No Program case were projected to result in savings in petroleum use and GHG emissions. Benefits were disaggregated by individual program technology areas, which included the FCTO program and the VTO subprograms of batteries and electric drives; advanced combustion engines; fuels and lubricants; materials (for reduction in vehicle mass, or “lightweighting”); and, for medium- and heavy-duty vehicles, reduction in rolling and aerodynamic resistance. Projections for the Program Success case indicate that by 2035, the average fuel economy of on-road, light-duty vehicle stock could be 47% to 76

  1. Preliminary Study of Gas Cooled Fast Breeder Reactor with Heterogen Percentage of Uranium–Plutonium Carbide based fuel and 300 MWt Power

    Science.gov (United States)

    Clief Pattipawaej, Sandro; Su’ud, Zaki

    2017-01-01

    A preliminary design study of GFR with helium gas-cooled has been performed. In this study used natural uranium and plutonium results LWR waste as fuel. Fuel with a small percentage of plutonium are arranged on the inside of the core area, and the fuel with a greater percentage set on the outside of the core area. The configuration of such fuel is deliberately set to increase breeding in this part of the central core and reduce the leakage of neutrons on the outer side of the core, in order to get long-lived reactor with a small reactivity. Configuration of fuel as it is also useful to generate a peak power reactors with relatively low in both the direction of axial or radial. Optimization has been done to fuel fraction 45.0% was found that the reactor may be operating in more than 10 year time with excess reactivity less than 1%.

  2. Summary of Fuel Cell Programs at the NASA Glenn Research Center

    Science.gov (United States)

    Perez-Davis, Marla

    2000-01-01

    The objective of this program is to develop passive ancillary component technology to be teamed with a hydrogen-oxygen unitized regenerative fuel cell (URFC) stack to form a revolutionary new regenerative fuel cell energy (RFC) storage system for aerospace applications. Replacement of active RFC ancillary components with passive components minimizes parasitic power losses and allows the RFC to operate as a H2/O2 battery. The goal of this program is to demonstrate an integrated passive lkW URFC system.

  3. Exploration for fossil and nuclear fuels from orbital altitudes. [results of ERTS program for oil exploration

    Science.gov (United States)

    Short, N. M.

    1974-01-01

    Results from the ERTS program pertinent to exploration for oil, gas, and uranium are discussed. A review of achievements in relevant geological studies from ERTS, and a survey of accomplishments oriented towards exploration for energy sources are presented along with an evaluation of the prospects and limitations of the space platform approach to fuel exploration, and an examination of continuing programs designed to prove out the use of ERTS and other space system in exploring for fuel resources.

  4. Fuel Gas Demonstration Plant Program. Volume I. Demonstration plant

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    The objective of this project is for Babcock Contractors Inc. (BCI) to provide process designs, and gasifier retort design for a fuel gas demonstration plant for Erie Mining Company at Hoyt Lake, Minnesota. The fuel gas produced will be used to supplement natural gas and fuel oil for iron ore pellet induration. The fuel gas demonstration plant will consist of five stirred, two-stage fixed-bed gasifier retorts capable of handling caking and non-caking coals, and provisions for the installation of a sixth retort. The process and unit design has been based on operation with caking coals; however, the retorts have been designed for easy conversion to handle non-caking coals. The demonstration unit has been designed to provide for expansion to a commercial plant (described in Commercial Plant Package) in an economical manner.

  5. Spent LWR fuel leach tests: Waste Isolation Safety Assessment program

    Energy Technology Data Exchange (ETDEWEB)

    Katayama, Y.B.

    1979-04-01

    Spent light-water-reactor (LWR) fuels with burnups of 54.5, 28 and 9 MWd/kgU were leach-tested in deionized water at 25/sup 0/C. Fuel burnup has no apparent effect on the calculated leach rates based upon the behavior of /sup 137/Cs and /sup 239 +240/Pu. A leach test of 54.5 MWd/kgU spent fuel in synthetic sea brine showed that the cesium-based leach rate is lower in sea brine than in deionized water. A rise in the leach rate was observed after approximately 600 d of cumulative leaching. During the rise, the leach rate for all the measured radionuclides become nearly equal. Evidence suggests that exposure of new surfaces to the leachant may cause the increase. As a result, experimental work to study leaching mechanisms of spent fuel has been initiated. 22 figures.

  6. Fuel cells for transportation program: FY1997 national laboratory annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The Department of Energy (DOE) Fuel Cells for Transportation Program is structured to effectively implement the research and development (R and D) required for highly efficient, low or zero emission fuel cell power systems to be a viable replacement for the internal combustion engine in automobiles. The Program is part of the Partnership for a New Generation of Vehicles (PNGV), a government-industry initiative aimed at development of an 80 mile-per-gallon vehicle. This Annual Report summarizes the technical accomplishments of the laboratories during 1997. Participants include: Argonne National Laboratory (ANL), Brookhaven National Laboratory (BNL), Lawrence Berkeley National Laboratory (LBNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and the National Renewable Energy Laboratory (NREL). During 1997, the laboratory R and D included one project on solid oxide fuel cells; this project has since been terminated to focus Department resources on PEM fuel cells. The technical component of this report is divided into five key areas: fuel cell stack research and development; fuel processing; fuel cell modeling, testing, and evaluation; direct methanol PEM fuel cells; and solid oxide fuel cells.

  7. Alternative fuels for vehicles fleet demonstration program. Final report, volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    The Alternative Fuels for Vehicles Fleet Demonstration Program (AFV-FDP) was a multiyear effort to collect technical data for use in determining the costs and benefits of alternative-fuel vehicles (AFVs) in typical applications in New York State. This report, Volume 2, includes 13 appendices to Volume 1 that expand upon issues raised therein. Volume 1 provides: (1) Information about the purpose and scope of the AFV-FDP; (2) A summary of AFV-FDP findings organized on the basis of vehicle type and fuel type; (3) A short review of the status of AFV technology development, including examples of companies in the State that are active in developing AFVs and AFV components; and (4) A brief overview of the status of AFV deployment in the State. Volume 3 provides expanded reporting of AFV-FDP technical details, including the complete texts of the brochure Garage Guidelines for Alternative Fuels and the technical report Fleet Experience Survey Report, plus an extensive glossary of AFV terminology. The appendices cover a wide range of issues including: emissions regulations in New York State; production and health effects of ozone; vehicle emissions and control systems; emissions from heavy-duty engines; reformulated gasoline; greenhouse gases; production and characteristics of alternative fuels; the Energy Policy Act of 1992; the Clean Fuel Fleet Program; garage design guidelines for alternative fuels; surveys of fleet managers using alternative fuels; taxes on conventional and alternative fuels; and zero-emission vehicle technology.

  8. Direct Methanol Fuel Cell (DMFC) Battery Replacement Program

    Science.gov (United States)

    2013-01-29

    required for maximum performance of electrochemical flow reactors . A reactant stream will favor the path of least resistance, potentially starving re...gions of the electrode assembly and lowering reactor efficiency. Array fuel cells are ideal for evaluation of catalytic layers, gas diffusion...layers, solid electrolytes , electrode fabrica- tion methods and flow uniformity. The coupling of Array fuel cell analysis with a modular flow-field

  9. Ageing management program for the Spanish low and intermediate level waste disposal and spent fuel and high-level waste centralised storage facilities

    Directory of Open Access Journals (Sweden)

    Andrade C.

    2011-04-01

    Full Text Available The generic design of the centralised spent fuel storage facility was approved by the Spanish Safety Authority in 2006. The planned operational life is 60 years, while the design service life is 100 years. Durability studies and surveillance of the behaviour have been considered from the initial design steps, taking into account the accessibility limitations and temperatures involved. The paper presents an overview of the ageing management program set in support of the Performance Assessment and Safety Review of El Cabril low and intermediate level waste (LILW disposal facility. Based on the experience gained for LILW, ENRESA has developed a preliminary definition of the Ageing Management Plan for the Centralised Interim Storage Facility of spent Fuel and High Level Waste (HLW, which addresses the behaviour of spent fuel, its retrievability, the confinement system and the reinforced concrete structure. It includes tests plans and surveillance design considerations, based on the El Cabril LILW disposal facility.

  10. Preliminary Experimental Results of Integrated Gasification Fuel Cell Operation Using Hardware Simulation

    Energy Technology Data Exchange (ETDEWEB)

    Traverso, Alberto; Tucker, David; Haynes, Comas L.

    2012-07-01

    A newly developed integrated gasification fuel cell (IGFC) hybrid system concept has been tested using the Hybrid Performance (Hyper) project hardware-based simulation facility at the U.S. Department of Energy, National Energy Technology Laboratory. The cathode-loop hardware facility, previously connected to the real-time fuel cell model, was integrated with a real-time model of a gasifier of solid (biomass and fossil) fuel. The fuel cells are operated at the compressor delivery pressure, and they are fueled by an updraft atmospheric gasifier, through the syngas conditioning train for tar removal and syngas compression. The system was brought to steady state; then several perturbations in open loop (variable speed) and closed loop (constant speed) were performed in order to characterize the IGFC behavior. Coupled experiments and computations have shown the feasibility of relatively fast control of the plant as well as a possible mitigation strategy to reduce the thermal stress on the fuel cells as a consequence of load variation and change in gasifier operating conditions. Results also provided an insight into the different features of variable versus constant speed operation of the gas turbine section.

  11. Alternative-fueled truck demonstration natural gas program: Caterpillar G3406LE development and demonstration

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    In 1990, the California Energy Commission, the South Coast Air Quality Management District, and the Southern California Gas Company joined together to sponsor the development and demonstration of compressed natural gas engines for Class 8 heavy-duty line-haul trucking applications. This program became part of an overall Alternative-Fueled Truck Demonstration Program, with the goal of advancing the technological development of alternative-fueled engines. The demonstration showed natural gas to be a technically viable fuel for Class 8 truck engines.

  12. 75 FR 16833 - Preliminary Revised 5-Year Outer Continental Shelf (OCS) Oil and Gas Leasing Program for 2007-2012

    Science.gov (United States)

    2010-04-02

    ... Minerals Management Service Preliminary Revised 5-Year Outer Continental Shelf (OCS) Oil and Gas Leasing... Revised 5-Year OCS Oil and Gas Leasing Program for 2007- 2012. This is the Preliminary Revised Program... relative environmental sensitivity analysis and the Secretary's revisions to the leasing schedule...

  13. Examining the Preliminary Efficacy of a Dating Violence Prevention Program for Hispanic Adolescents

    Science.gov (United States)

    Gonzalez-Guarda, Rosa Maria; Guerra, Jessica E.; Cummings, Amanda A.; Pino, Karen; Becerra, Maria M.

    2015-01-01

    The purpose of this study is to evaluate the preliminary efficacy of a dating violence (DV) prevention program for Cuban American adolescents ("JOVEN"/YOUTH: "Juntos Opuestos a la Violence Entre Novios"/Together Against Dating Violence). A randomized-controlled experimental design with a delayed condition was used to evaluate…

  14. Preliminary assessment of Malaysian micro-algae strains for the production of bio jet fuel

    Science.gov (United States)

    Chen, J. T.; Mustafa, E. M.; Vello, V.; Lim, P.; Nik Sulaiman, N. M.; Majid, N. Abdul; Phang, S.; Tahir, P. Md.; Liew, K.

    2016-10-01

    Malaysia is the main hub in South-East Asia and has one of the highest air traffic movements in the region. Being rich in biodiversity, Malaysia has long been touted as country rich in biodiversity and therefore, attracts great interests as a place to setup bio-refineries and produce bio-fuels such as biodiesel, bio-petrol, green diesel, and bio-jet fuel Kerosene Jet A-1. Micro-algae is poised to alleviate certain disadvantages seen in first generation and second generation feedstock. In this study, the objective is to seek out potential micro-algae species in Malaysia to determine which are suitable to be used as the feedstock to enable bio-jet fuel production in Malaysia. From 79 samples collected over 30 sites throughout Malaysia, six species were isolated and compared for their biomass productivity and lipid content. Their lipid contents were then used to derived the require amount of micro-algae biomass to yield 1 kg of certifiable jet fuel via the HEFA process, and to meet a scenario where Malaysia implements a 2% alternative (bio-) jet fuel requirement.

  15. Preliminary Investigation for Engine Performance by Using Tire-Derived Pyrolysis Oil-Diesel Blended Fuels

    Science.gov (United States)

    Rofiqul, Islam M.; Haniu, Hiroyuki; Alam, Beg R.; Takai, Kazunori

    In the first phase of the present study, the pyrolysis oil derived from light automotive tire waste has been characterized including fuel properties, elemental analyses, FT-IR, 1H-NMR, GC-MS and distillation. The studies on the oil show that it can be used as liquid fuel with a gross calorific value (GCV) of 42.00 MJ/kg and empirical formula of CH1.27O0.025N0.006. In the second phase of the investigation, the performance of a diesel engine was studied blending the pyrolysis oil with diesel fuel in different ratios. The experimental results show that the bsfc of pyrolysis oil-diesel blended fuels slightly increases and hence the brake thermal efficiency decreases compared to those of neat diesel. The pyrolysis oil-diesel blends show lower carbon monoxide (CO) emission but higher oxides of nitrogen (NOx) emissions than those of neat diesel. However, NOx emissions with pyrolysis oil-diesel blended fuels reduced when EGR was applied.

  16. F-35 Joint Strike Fighter: Preliminary Observations on Program Progress

    Science.gov (United States)

    2016-03-23

    operations, mission planning, supply - chain management , maintenance, and other processes. In the past, we have reported that ALIS software has not been... supply chain and is managing supplier quality initiatives to address shortfalls, according to officials. Our ongoing work shows that although the...analyzed total program funding requirements. GAO also collected and analyzed production and supply chain performance data, and interviewed DOD

  17. Preliminary Design of the Ada Programming Support Environment Configuration Manager.

    Science.gov (United States)

    1984-06-01

    October 1980. 62 ............................................... 10. Buxton , J. and V. H. Stenning, eds. "Stoneman," Requirements for Ada Programming...18. Stoner, Bill . Logicon. Course EE 5.45, "Software Acquisition," School of Engineering, Air Force Institute of Technology, Wright-Patterson AFB OH

  18. Spanish R and D programs on hydrogen and fuel cells

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Garcia-Conde, A.; Ben Pendones, R. [Instituto Nacional de Tecnica Aeroespacial (INTA), Departamento de Aerodinamica y Propulsion, Madrid (Spain)

    2003-09-01

    Since 1988 INTA (the National Institute for Aerospace Technology in Spain) has been running hydrogen and fuel cells activities supported by own funds. Up to 1996, subsidies from the regional government of Andalucia (south of Spain), were provided for building a solar hydrogen production pilot plant based on photovoltaic powered water electrolysis. At present there is not a specific programme devoted to hydrogen energy and fuel cells in Spain, however, the Spanish Plan for Scientific Research, Technological Development and Innovation (2004-2007) in the energy area, will consider these topics as separate items included in the priority devoted to renewable energies and emerging technologies. This means that part of the R and D budget will be allocated for hydrogen and fuel cells projects but competing with the rest of renewable energies projects. Nevertheless the possibilities to approve projects for national funding are considered in a very wide and detailed way in the rationale of the national R and D programme, as mentioned in the following paragraphs: Hydrogen, by means of fuel cells technological evolution, presents a potential to become in the long term an energy carrier that changes the energetic sector configuration, making it safer, more efficient and more respectful with environment. For achieving this goal, a number of technological barriers must be overcome within production, storage, distribution and final supply, both for its utilization in transport and stationary applications. Fuel Cells are gaining in Spain increasing importance both for stationary and transport utilization, as a consequence of its different types, modular characteristics and the possibility for utilization in different applications, as domestic use, distributed and centralized generation. Due to its wide variety of possibilities and its characteristics of low environmental impact and reduced noise production, fuel cells become themselves a energetic objective. (O.M.)

  19. Preliminary Study on the Fabrication of Particulate Fuel through Pressureless Sintering Process

    Directory of Open Access Journals (Sweden)

    Jong-Hwan Kim

    2016-01-01

    Full Text Available U-10wt%Zr spherical particles for use as particulate fuel were prepared by centrifugal atomization and subjected to pressureless sintering, which is one of the simplest powder processing techniques. At sintering temperature of 1100°C for 30 or 60 min, all samples ranging from +50 to −325 mesh showed no apparent bonding between the particles. However, at 1150°C (80 min, all samples formed a bulk body and the microstructures showed apparent sintering stages. Particularly, sample B (50–70 mesh and sample C (70–100 mesh showed pore characteristics suitable for a particulate fuel. The results suggest that pressureless sinterability for U-10Zr particulate fuel can be improved by adding small-size (–325 mesh particles.

  20. Preliminary Mathematical Model for Jet Fuel Exacerbated Noise-Induced Hearing Loss

    Science.gov (United States)

    2013-01-01

    hearing loss . Noise alone induces hearing loss due to loss of hair cells in the cochlea, associated with oxidative stress. Jet fuel toxicity in association with noise may be at least partially explained by increased free radical production and oxidative stress at the cellular level, resulting in hair cell dysfunction and loss. This project combines a physiologically-based pharmacokinetic (PBPK) model to describe jet fuel component concentrations in the cochlea with pharmacodynamic (PD) models of free radical formation in the cochlea by both noise and

  1. Preliminary study on interaction of water mist with diffusion flame of liquid fuels

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    The chemical and physical interaction mechanisms of the water mist with diffusion flame of liquid fuels are investigated.The difference of the thermograms and the thermal field isograms between ethanol flame and kerosene flame with the water mist application is explained. With the water mist application, the differences between ethanol and kerosene in heat release rate, O2 and CO concentrations of their combustion products, and the temperature of their smoke are analyzed. At the same time, the interaction mechanism of the water mist with diffusion flame is presented and their relationship to the fuel species and to the concentration of water mist is described.

  2. Bachelor of Science-Engineering Technology Program and Fuel Cell Education Program Concentration

    Energy Technology Data Exchange (ETDEWEB)

    Block, David L. [Florida Solar Energy Center, Cocoa, FL (United States); Sleiti, Ahmad [Univ. of North Carolina, Charlotte, NC (United States)

    2011-09-19

    The Hydrogen and Fuel Cell Technology education project has addressed DOE goals by supplying readily available, objective, technical, and accurate information that is available to students, industry and the public. In addition, the program has supplied educated trainers and training opportunities for the next generation workforce needed for research, development, and demonstration activities in government, industry, and academia. The project has successfully developed courses and associated laboratories, taught the new courses and labs and integrated the HFCT option into the accredited engineering technology and mechanical engineering programs at the University of North Carolina at Charlotte (UNCC). The project has also established ongoing collaborations with the UNCC energy related centers of the Energy Production & Infrastructure Center (EPIC), the NC Motorsports and Automotive Research Center (NCMARC) and the Infrastructure, Design, Environment and Sustainability Center (IDEAS). The results of the project activities are presented as two major areas – (1) course and laboratory development, offerings and delivery, and (2) program recruitment, promotions and collaborations. Over the project period, the primary activity has been the development and offering of 11 HFCT courses and accompanying laboratories. This process has taken three years with the courses first being developed and then offered each year over the timeframe.

  3. Turbine Fuels from Tar Sands Bitumen and Heavy Oil. Phase I. Preliminary Process Analysis.

    Science.gov (United States)

    1985-04-09

    Process Analysis A. F. Talbot. V. Elanchenny, L. H. Finkel, A. Macris and 3. P. Schwedock Sun Tech, Inc., A Subsidiary of Sun Co. P. 0. Box 1135 Marcus Hook...investigation be carried out in three discrete phases, as described below: Phase I - Preliminary process analysis includes an eval- uation of the potential of

  4. Parsing Combinatory Categorial Grammar with Answer Set Programming: Preliminary Report

    CERN Document Server

    Lierler, Yuliya

    2011-01-01

    Combinatory categorial grammar (CCG) is a grammar formalism used for natural language parsing. CCG assigns structured lexical categories to words and uses a small set of combinatory rules to combine these categories to parse a sentence. In this work we propose and implement a new approach to CCG parsing that relies on a prominent knowledge representation formalism, answer set programming (ASP) - a declarative programming paradigm. We formulate the task of CCG parsing as a planning problem and use an ASP computational tool to compute solutions that correspond to valid parses. Compared to other approaches, there is no need to implement a specific parsing algorithm using such a declarative method. Our approach aims at producing all semantically distinct parse trees for a given sentence. From this goal, normalization and efficiency issues arise, and we deal with them by combining and extending existing strategies. We have implemented a CCG parsing tool kit - AspCcgTk - that uses ASP as its main computational mean...

  5. Spent fuel sabotage aerosol ratio program : FY 2004 test and data summary.

    Energy Technology Data Exchange (ETDEWEB)

    Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Mo, Tin (U.S. Nuclear Regulatory Commission, Washington, DC); Billone, Michael C. (Argonne National Laboratory, Argonne, IL); Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Young, F. I. (U.S. Nuclear Regulatory Commission, Washington, DC); Coats, Richard Lee; Burtseva, Tatiana (Argonne National Laboratory, Argonne, IL); Luna, Robert Earl; Dickey, Roy R.; Sorenson, Ken Bryce; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Thompson, Nancy Slater (U.S. Department of Energy, Washington, DC); Hibbs, Russell S. (U.S. Department of Energy, Washington, DC); Gregson, Michael Warren; Lange, Florentin (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Molecke, Martin Alan; Tsai, Han-Chung (Argonne National Laboratory, Argonne, IL)

    2005-07-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. The program also provides significant technical and political benefits in international cooperation. We are quantifying the Spent Fuel Ratio (SFR), the ratio of the aerosol particles released from HEDD-impacted actual spent fuel to the aerosol particles produced from surrogate materials, measured under closely matched test conditions, in a contained test chamber. In addition, we are measuring the amounts, nuclide content, size distribution of the released aerosol materials, and enhanced sorption of volatile fission product nuclides onto specific aerosol particle size fractions. These data are the input for follow-on modeling studies to quantify respirable hazards, associated radiological risk assessments, vulnerability assessments, and potential cask physical protection design modifications. This document includes an updated description of the test program and test components for all work and plans made, or revised, during FY 2004. It also serves as a program status report as of the end of FY 2004. All available test results, observations, and aerosol analyses plus interpretations--primarily for surrogate material Phase 2 tests, series 2/5A through 2/9B, using cerium oxide sintered ceramic pellets are included. Advanced plans and progress are described for upcoming tests with unirradiated, depleted uranium oxide and actual spent fuel test rodlets. This spent fuel sabotage--aerosol test program is coordinated with the international Working Group for Sabotage Concerns of

  6. Surrogate/spent fuel sabotage : aerosol ratio test program and Phase 2 test results.

    Energy Technology Data Exchange (ETDEWEB)

    Borek, Theodore Thaddeus III; Thompson, N. Slater (U.S. Department of Energy); Sorenson, Ken Bryce; Hibbs, R.S. (U.S. Department of Energy); Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Molecke, Martin Alan; Autrusson, Bruno (Institut de Radioprotection et de Surete Nucleaire, France); Young, F. I. (U.S. Nuclear Regulatory Commission); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Brochard, Didier (Institut de Radioprotection et de Surete Nucleaire, France); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Lange, Florentin (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany)

    2004-05-01

    A multinational test program is in progress to quantify the aerosol particulates produced when a high energy density device, HEDD, impacts surrogate material and actual spent fuel test rodlets. This program provides needed data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments; the program also provides significant political benefits in international cooperation. We are quantifying the spent fuel ratio, SFR, the ratio of the aerosol particles released from HEDD-impacted actual spent fuel to the aerosol particles produced from surrogate materials, measured under closely matched test conditions. In addition, we are measuring the amounts, nuclide content, size distribution of the released aerosol materials, and enhanced sorption of volatile fission product nuclides onto specific aerosol particle size fractions. These data are crucial for predicting radiological impacts. This document includes a thorough description of the test program, including the current, detailed test plan, concept and design, plus a description of all test components, and requirements for future components and related nuclear facility needs. It also serves as a program status report as of the end of FY 2003. All available test results, observations, and analyses - primarily for surrogate material Phase 2 tests using cerium oxide sintered ceramic pellets are included. This spent fuel sabotage - aerosol test program is coordinated with the international Working Group for Sabotage Concerns of Transport and Storage Casks, WGSTSC, and supported by both the U.S. Department of Energy and Nuclear Regulatory Commission.

  7. Synthetic Fuel Blend Demonstration Program at Fort Bliss, Texas

    Science.gov (United States)

    2010-05-01

    Iso -Paraffinic Kerosene JP-8 Aviation Turbine Fuel LMTV Light Medium Tactical Vehicle MPG Miles per Gallon MTV Medium Tactical Vehicle POL...12508 12559 12667 12677 689 212 TRK CGO LMTV TON M1078 B70T 13421 0 0 13459 13485 13560 0 139 36 TRK CGO LMTV TON M1078 B72 T 11743 11880 11919 11937

  8. Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report. Appendix C: preliminary design data package. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Piccolo, R.

    1979-07-31

    The assumptions made, analysis methods used, and preliminary results of research to determine the design specifications for a hybrid electric-powered and internal combustion engine-powered vehicle that would optimize the fuel economy of passenger automobiles are described. Information is included on body and component design, selection of spark-ignition engine and Ni-Zn batteries, life-cycle costs and life-cycle fuel consumption. (LCL)

  9. Alternative fuels for vehicles fleet demonstration program final report. Volume 1: Summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    The Alternative Fuels for Vehicles Fleet Demonstration Program (AFV-FDP) was a multiyear effort to collect technical data for use in determining the costs and benefits of alternative-fuel vehicles in typical applications in New York State. During 3 years of collecting data, 7.3 million miles of driving were accumulated, 1,003 chassis-dynamometer emissions tests were performed, 862,000 gallons of conventional fuel were saved, and unique information was developed about garage safety recommendations, vehicle performance, and other topics. Findings are organized by vehicle and fuel type. For light-duty compressed natural gas (CNG) vehicles, technology has evolved rapidly and closed-loop, electronically-controlled fuel systems provide performance and emissions advantages over open-loop, mechanical systems. The best CNG technology produces consistently low tailpipe emissions versus gasoline, and can eliminate evaporative emissions. Reduced driving range remains the largest physical drawback. Fuel cost is low ($/Btu) but capital costs are high, indicating that economics are best with vehicles that are used intensively. Propane produces impacts similar to CNG and is less expensive to implement, but fuel cost is higher than gasoline and safety codes limit use in urban areas. Light-duty methanol/ethanol vehicles provide performance and emissions benefits over gasoline with little impact on capital costs, but fuel costs are high. Heavy-duty CNG engines are evolving rapidly and provide large reductions in emissions versus diesel. Capital costs are high for CNG buses and fuel efficiency is reduced, but the fuel is less expensive and overall operating costs are about equal to those of diesel buses. Methanol buses provide performance and emissions benefits versus diesel, but fuel costs are high. Other emerging technologies were also evaluated, including electric vehicles, hybrid-electric vehicles, and fuel cells.

  10. Spent fuel acceptance scenarios devoted to shutdown reactors: A preliminary analysis

    Energy Technology Data Exchange (ETDEWEB)

    Wood, T.W.; Plummer, A.M.; Dippold, D.G.; Short, S.M. (Pacific Northwest Lab., Richland, WA (USA); Battelle Memorial Inst., Columbus, OH (USA). Office of Transportation Systems and Planning; Pacific Northwest Lab., Richland, WA (USA))

    1989-10-01

    Spent fuel acceptance schedules and the allocation of federal acceptance capacity among commercial nuclear power reactors have important operational and cost consequences for reactor operators. Alternative allocation schemes were investigated to some extent in DOE's MRS Systems Study. The current study supplements these analyses for a class of acceptance schemes in which the acceptance capacity of the federal radioactive waste management system is allocated principally to shutdown commercial power reactors, and extends the scope of analysis to include considerations of at-reactor cask loading rates. The operational consequences of these schemes for power reactors, as measured in terms of quantity of spent fuel storage requirement above storage pool capacities and number of years of pool operations after last discharge, are estimated, as are the associated utility costs. This study does not attempt to examine the inter-utility equity considerations involved in departures from the current oldest-fuel-first (OFF) allocation rule as specified in the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste.'' In the sense that the alternative allocations are more economically efficient than OFF, however, they approximate the allocations that could result from free exchange of acceptance rights among utilities. Such a process would result in the preservation of inter-utility equity. 13 refs., 9 figs., 9 tabs.

  11. Hydrogen energy and fuel cells: a recent R and D program in Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Sebastian, P.J.; Martinez, M. [Universidad Nacional Autonoma de Mexico, Mexico City (Mexico). Inst. de Investigaciones en Materiales; Eapen, D. [UNAM, Morelos (Mexico). Inst. de Biotecnologia; Solorza, O. [CINVESTAV-IPN, Mexico (Mexico). Dept. de Quimica; Savadogo, O. [Ecole Polytechnique, Montreal, PQ (Canada). Dept. of Metallurgy and Materials Engineering

    1996-12-31

    A recent R and D program on hydrogen production, storage and application in fuel cells by employing various physicochemical and biological routes was initiated among the three institutions in Mexico in collaboration with Ecole Polytechnique, Canada. The major theme of this R and D program is hydrogen production using various physicochemical and biological methods, development of high efficiency storage materials and applications of hydrogen in fuel cells for production of electricity. The future of the hydrogen energy program in Mexico is reviewed in the light of the high pollution level in several large cities and the energy scenario from 1962 onwards. (Author)

  12. National Aviation Fuel Scenario Analysis Program (NAFSAP). Volume I. Model Description. Volume II. User Manual.

    Science.gov (United States)

    1980-03-01

    TESI CHART NATIONAI RUREAt (F ANDA[)Rt 1V4 A NATIONAL. AVIATION ~ FUEL SCENARIO.. ANALYSIS PROGRAM 49!! VOLUM I: MODEL DESCRIA~v 4<C VOLUME II: tr)ER...executes post processor which translates results of the graphics program to machine readable code used by the pen plotter) cr (depressing the carriage

  13. Market impacts of a multiyear mechanical fuel treatment program in the U.S.

    Science.gov (United States)

    Jeffrey P. Prestemon; Karen L. Abt; Robert J. Jr. Huggett

    2008-01-01

    We describe a two-stage model of global log and chip markets that evaluates the spatial and temporal economic effects of government- subsidized fire-related mechanical fuel treatment programs in the U.S.West and South. The first stage is a goal program that allocates subsidies according to fire risk and location priorities, given a budget and a feasible, market-...

  14. Pathways to Commercial Success. Technologies and Products Supported by the Fuel Cell Technologies Program - 2012

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2012-09-01

    This FY 2012 report updates the results of an effort to identify and characterize commercial and near-commercial (emerging) technologies and products that benefited from the support of the Fuel Cell Technologies Program and its predecessor programs within DOE's Office of Energy Efficiency and Renewable Energy.

  15. Pathways to Commercial Success. Technologies and Products Supported by the Fuel Cell Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-09-01

    This FY 2011 report updates the results of an effort to identify and characterize commercial and near-commercial (emerging) technologies and products that benefited from the support of the Fuel Cell Technologies Program and its predecessor programs within DOE's Office of Energy Efficiency and Renewable Energy.

  16. Preliminary study of mechanical behavior for Cr coated Zr-4 Fuel Cladding

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do-Hyoung; Kim, Hak-Sung [Hanyang Univ., Seoul (Korea, Republic of); Kim, Hyo-Chan; Yang, Yong-Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    To decrease the oxidation rate of Zr-based alloy components, many concepts of accident tolerant fuel (ATF) such as Mo-Zr cladding, SiC/SiCf cladding and iron-based alloy cladding are under development. One of the promised concept is the coated cladding which can remarkably increase the corrosion and wear resistance. Recently, KAERI is developing the Cr coated Zircaloy cladding as accident tolerance cladding. To coat the Cr powder on the Zircaloy, 3D laser coating technology has been employed because it is possible to make a coated layer on the tubular cladding surface by controlling the 3-diminational axis. Therefore, for this work, the mechanical integrity of Cr coated Zircaloy should be evaluated to predict the safety of fuel cladding during the operating or accident of nuclear reactor. In this work, the mechanical behavior of the Cr coated Zircaloy cladding has been studied by using finite element analysis (FEA). The ring compression test (RCT) of fuel cladding was simulated to evaluate the validity of mechanical properties of Zr-4 and Cr, which were referred from the literatures and experimental reports. In this work, the mechanical behavior of the Cr coated Zircaloy cladding has been studied by using finite element analysis (FEA). The ring compression test (RCT) of fuel cladding was simulated to evaluate the validity of mechanical properties of Zr-4 and Cr. The pellet-clad mechanical interaction (PCMI) properties of Cr coated Zr-4 cladding were investigated by thermo-mechanical finite element analysis (FEA) simulation. The mechanical properties of Zr-4 and Cr was validated by simulation of ring compression test (RCT) of fuel cladding.

  17. NASA's PEM Fuel Cell Power Plant Development Program for Space Applications

    Science.gov (United States)

    Hoberecht, Mark A.

    2008-01-01

    A three-center NASA team led by the Glenn Research Center in Cleveland, Ohio is completing a five-year PEM fuel cell power plant development program for future space applications. The focus of the program has been to adapt commercial PEM fuel cell technology for space applications by addressing the key mission requirements of using pure oxygen as an oxidant and operating in a multi-gravity environment. Competing vendors developed breadboard units in the 1 to 5 kW power range during the first phase of the program, and a single vendor developed a nominal 10-kW engineering model power pant during the second phase of the program. Successful performance and environmental tests conducted by NASA established confidence that PEM fuel cell technology will be ready to meet the electrical power needs of future space missions.

  18. Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program

    Energy Technology Data Exchange (ETDEWEB)

    Adrian Miron; Joshua Valentine; John Christenson; Majd Hawwari; Santosh Bhatt; Mary Lou Dunzik-Gougar: Michael Lineberry

    2009-10-01

    The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), Unviery of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

  19. Update from the NREL Alternative Fuel Transit Bus Evaluation Program

    Energy Technology Data Exchange (ETDEWEB)

    Chandler, K. (Battelle); Norton, P. (National Renewable Energy Laboratory); Clark, N. (West Virginia University)

    1999-05-01

    The object of this project, which is supported by the U.S. Department of Energy (DOE) through the National Renewable Energy Laboratory (NREL), is to provide a comprehensive comparison of heavy-duty urban transit buses operating on alternative fuels and diesel fuel. Final reports from this project were produced in 1996 from data collection and evaluation of 11 transit buses from eight transit sites. With the publication of these final reports, three issues were raised that needed further investigation: (1) the natural gas engines studied were older, open-loop control engines; (2) propane was not included in the original study; and (3) liquefied natural gas (LNG) was found to be in the early stages of deployment in transit applications. In response to these three issues, the project has continued by emissions testing newer natural gas engines and adding two new data collection sites to study the newer natural gas technology and specifically to measure new technology LNG buses.

  20. Tuberous legumes: preliminary evaluation of tropical Australian and introduced species as fuel crops

    Energy Technology Data Exchange (ETDEWEB)

    Saxon, E.C.

    1981-04-01

    The evaluation of native and introduced legumes with starch-storing roots or tubers was undertaken to test whether plants traditionally collected as food by Australian aborigines might have a role in the development of crops for liquid fuel production (by fermentation of carbohydrates to ethanol). Tuberous-rooted legumes from overseas were planted at the Commonwealth Scientific and Industrial Research Organization, division of Tropical Crops and Pastures, Kimberley Research Station, Western Australia (15/sup 0/39'S, 128/sup 0/42'E) in December 1974, March 1978 and February 1979. Roots from the latter plantings were harvested in June 1979. Native plant material was collected during visits to aboriginal communities in the Kimberleys between April and June 1979. The native and introduced specimens were analyzed for fermentable carbohydrate and protein content. Several native plants appear more promising than introduced species as liquid fuel crops.

  1. Analysis of preliminary design concept of stainless steel container for disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Chun, K.S.; Ku, J.H.; Park, J.H.; Choi, J.W. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    This report represents the structural, thermal and radiation shielding analysis of the basic concepts of the disposal container, that could accommodate PWR and CANDU fuels of which physical dimensions and shapes are quite different each other, with respect to the emplacement modes. Basic concepts of the disposal containers for the vertical horehole and the drift emplacement modes are proposed with their maximum allowable thermal loading. Appropriate thickness of the container to withstand the expected external pressure in the underground repository system was delivered by the structural analyses. The thermal analysis of the container containing spent fuels showed that the internal maximum temperatures of all container concepts did not reach the constraint values. Radiation dose rate from the container with 10cm thickness wall were also less than the established constraint value. (author). 9 refs., 33 figs., 12 tabs.

  2. Advanced Coal-Fueled Gas Turbine Program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Horner, M.W.; Ekstedt, E.E.; Gal, E.; Jackson, M.R.; Kimura, S.G.; Lavigne, R.G.; Lucas, C.; Rairden, J.R.; Sabla, P.E.; Savelli, J.F.; Slaughter, D.M.; Spiro, C.L.; Staub, F.W.

    1989-02-01

    The objective of the original Request for Proposal was to establish the technological bases necessary for the subsequent commercial development and deployment of advanced coal-fueled gas turbine power systems by the private sector. The offeror was to identify the specific application or applications, toward which his development efforts would be directed; define and substantiate the technical, economic, and environmental criteria for the selected application; and conduct such component design, development, integration, and tests as deemed necessary to fulfill this objective. Specifically, the offeror was to choose a system through which ingenious methods of grouping subcomponents into integrated systems accomplishes the following: (1) Preserve the inherent power density and performance advantages of gas turbine systems. (2) System must be capable of meeting or exceeding existing and expected environmental regulations for the proposed application. (3) System must offer a considerable improvement over coal-fueled systems which are commercial, have been demonstrated, or are being demonstrated. (4) System proposed must be an integrated gas turbine concept, i.e., all fuel conditioning, all expansion gas conditioning, or post-expansion gas cleaning, must be integrated into the gas turbine system.

  3. Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program

    Energy Technology Data Exchange (ETDEWEB)

    David Petti

    2014-06-01

    Modular HTGR designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior US manufactured TRISO fuel, by a few orders of magnitude. The improved performance level is about a factor of three better than qualified for German TRISO fuel in the 1980’s. At the start of the AGR program, without a reactor design concept selected, the AGR fuel program selected to qualify fuel to an operating envelope that would bound both pebble bed and prismatic options. This resulted in needing a fuel form that could survive at peak fuel temperatures of 1250°C on a time-averaged basis and high burnups in the range of 150 to 200 GWd/MTHM (metric tons of heavy metal) or 16.4 to 21.8% fissions per initial metal atom (FIMA). Although Germany has demonstrated excellent performance of TRISO-coated UO

  4. Clean, Efficient, and Reliable Heat and Power for the 21st Century, Fuel Cell Technologies Program (FCTP) (Fact Sheet)

    Energy Technology Data Exchange (ETDEWEB)

    2010-05-01

    This overview of the U.S. Department of Energy's Fuel Cell Technologies Program describes the program's focus and goals, along with current fuel cell applications and future potential. The program focuses on research and development of fuel cell systems for diverse applications in the stationary power, portable power, and transportation sectors. It works to reduce costs and improve technologies to advance fuel cell uses in areas such as combined heat and power, auxiliary power units, portable power systems, and stationary and backup power. To help ensure that fuel cell advances are realized, the program rigorously analyzes energy efficiency, economic, and environmental benefits of fuel cells and seeks to optimize synergies among fuel cell applications and other renewable technologies.

  5. Preliminary evaluation of fungicidal and termiticidal activities of filtrates from biomass slurry fuel production.

    Science.gov (United States)

    Kartal, S N; Imamura, Y; Tsuchiya, F; Ohsato, K

    2004-10-01

    Biomass slurry fuel (BSF) production has recently been developed as a natural energy for the conversion of solid biomass into fuel. In addition to using fuel, filtrates from BSF production may also serve a chemical source with several organic compounds. There is an increasing interest in the research and application of biomass-based filtrates. In this study, fungicidal and termiticidal properties of filtrates from BSF production using sugi (Cryptomeria japonica) and acacia (Acacia mangium) wood were evaluated in laboratory decay and termite resistance tests. Wood blocks treated with the filtrates showed increased resistance against brown-rot fungus, Fomitopsis palustris. However the filtrates from sugi wood processed at 270 degrees C which contained less phenolic compounds than the other filtrates were effective against white-rot fungus, Trametes versicolor. Phenolic compounds of filtrates seemed to play a role in the decay resistance tests however the filtrates did not increase the durability of the wood blocks against subterranean termites Coptotermes formosanus. Despite high acetic and lactic acid content of the filtrates, vanillin content of the filtrates may have served as an additional food source and promoted termite attack. It can be concluded that filtrates with phenolic compounds from lignin degradation during BSF production can be considered for targeted inhibition of brown-rot.

  6. Preliminary evaluation of fungicidal and termiticidal activities of filtrates from biomass slurry fuel production

    Energy Technology Data Exchange (ETDEWEB)

    Kartal, S.N. [Istanbul University (Turkey). Forestry Faculty; Imamura, Y. [Kyoto University (Japan). Wood Research Institute; Tsuchiya, F.; Ohsato, K. [JGC Corporation, Yokohama (Japan)

    2004-10-01

    Biomass slurry fuel (BSF) production has recently been developed as a natural energy for the conversion of solid biomass into fuel. In addition to using fuel, filtrates from BSF production may also serve a chemical source with several organic compounds. There is an increasing interest in the research and application of biomass-based filtrates. In this study, fungicidal and termiticidal properties of filtrates from BSF production using sugi (Cryptomeria japonica) and acacia (Acacia mangium) wood were evaluated in laboratory decay and termite resistance tests. Wood blocks treated with the filtrates showed increased resistance against brown-rot fungus, Formitopsis palustris. However the filtrates from sugi wood processed at 270{sup o}C which contained less phenolic compounds than the other filtrates were effective against white-rot fungus, Trametes versicolor. Phenolic compounds of filtrates seemed to play a role in the decay resistance tests however the filtrates did not increase the durability of the wood blocks against subterranean termites Coptotermes formosanus. Despite high acetic and lactic acid content of the filtrates, vanillin content of the filtrates may have served as an additional food source and promoted termite attack. It can be concluded that filtrates with phenolic compounds from lignin degradation during BSF production can be considered for targeted inhibition of brown-rot. (author)

  7. Preliminary study of impact of fuel options on performance of Nuclear Thermal Propulsion (NTP) concepts

    Science.gov (United States)

    Ludewig, H.; Todosow, M.; Montanez, P.; Bezler, P.

    2002-01-01

    A study of the sensitivity to fuel type and composition on the performance of two Nuclear Thermal Rocket (NTR) concepts is presented. The performance measures are the specific impulse and the thrust/weight (T/W) ratio, and the concepts considered are based on the NERVA and ESCORT reactors. For the NERVA concept use of alternative fissile materials showed significant reductions in core mass which improves the values of T/W. However, launch safety considerations may be the dominant factor in selection of fissile material. The use of ternary carbide based fuels allows higher exhaust temperatures, but due to their higher density reduces T/W. The use of molybdenum based cermets, and cermets which use UN or UC2 fuel allow for significant reductions in the reactor mass, and thus an increase in T/W. However, the use of molybdenum reduces the exhaust temperature. Both these results for the NERVA and ESCORT based systems indicate the need to axially zone the core. The lower temperature but lighter material should be used in the cooler (<2500 K) parts of the core, and the heavier, higher temperature material should be used in the outlet end of the core. In addition, the thermal response, and implied stress is estimated for the NERVA concept. .

  8. Spent fuel sabotage aerosol test program :FY 2005-06 testing and aerosol data summary.

    Energy Technology Data Exchange (ETDEWEB)

    Gregson, Michael Warren; Brockmann, John E.; Nolte, O. (Fraunhofer institut fur toxikologie und experimentelle Medizin, Germany); Loiseau, O. (Institut de radioprotection et de Surete Nucleaire, France); Koch, W. (Fraunhofer institut fur toxikologie und experimentelle Medizin, Germany); Molecke, Martin Alan; Autrusson, Bruno (Institut de radioprotection et de Surete Nucleaire, France); Pretzsch, Gunter Guido (Gesellschaft fur anlagen- und Reaktorsicherheit, Germany); Billone, M. C. (Argonne National Laboratory, USA); Lucero, Daniel A.; Burtseva, T. (Argonne National Laboratory, USA); Brucher, W (Gesellschaft fur anlagen- und Reaktorsicherheit, Germany); Steyskal, Michele D.

    2006-10-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides source-term data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. This document focuses on an updated description of the test program and test components for all work and plans made, or revised, primarily during FY 2005 and about the first two-thirds of FY 2006. It also serves as a program status report as of the end of May 2006. We provide details on the significant findings on aerosol results and observations from the recently completed Phase 2 surrogate material tests using cerium oxide ceramic pellets in test rodlets plus non-radioactive fission product dopants. Results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; status on determination of the spent fuel ratio, SFR (the ratio of respirable particles from real spent fuel/respirables from surrogate spent fuel, measured under closely matched test conditions, in a contained test chamber); and, measurements of enhanced volatile fission product species sorption onto respirable particles. We discuss progress and results for the first three, recently performed Phase 3 tests using depleted uranium oxide, DUO{sub 2}, test rodlets. We will also review the status of preparations and the final Phase 4 tests in this program, using short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. These data plus testing results and design are tailored to support and guide, follow-on computer modeling of aerosol dispersal hazards and radiological consequence

  9. National fuel cell seminar. Program and abstracts. [Abstracts of 40 papers

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-01

    Abstracts of 40 papers are presented. Topics include fuel cell systems, phosphoric acid fuel cells, molten carbonate fuel cells, solid fuel and solid electrolyte fuel cells, low temperature fuel cells, and fuel utilization. (WHK)

  10. Cracow clean fossil fuels and energy efficiency program. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-10-01

    Since 1990 the US Department of Energy has been involved in a program aimed at reducing air pollution caused by small, coal-fired sources in Poland. The program focuses on the city of Cracow and is designed so that results will be applicable and extendable to the entire region. This report serves both as a review of the progress which has been made to date in achieving the program objectives and a summary of work still in progress.

  11. Low NO/sub x/ Heavy Fuel Combustor Concept Program. Phase I. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Cutrone, M B

    1981-10-01

    Six combustor concepts were designed, fabricated, and underwent a series of combustion tests with the objective of evaluating and developing a combustor capable of meeting US New Source Performance Standards (NSPS), dry, for high-nitrogen liquid fuels. Three rich/lean and three lean/lean two-stage combustors were tested with ERBS distillate, petroleum residual, and SRC-II coal derived liquid (CDL) fuels with fuel-bound nitrogen contents of 0.0054, 0.23, and 0.87 weight percent, respectively. A lean/lean concept was demonstrated with ultralow NO/sub x/ emissions, dry, of 5 gm NO/sub x/kg fuel on ERBS, and NO/sub x/ emissions meeting the NSPS NO/sub x/ standard on residual fuel. This combustor concept met operational goals for pressure drop, smoke, exhaust pattern factor, and combustion efficiency. A rich/lean concept was identified and developed which demonstrated NO/sub x/ emissions approaching the NSPS standards, dry, for all liquid fuels including the 0.87 weight percent nitrogen SRC-II coal-derived liquid. Exhaust pattern factor and pressure drop met or approached goals. Smoke emissions were higher than the program goal. However, a significant improvement was made with only a minor modification of the fuel injector/air swirler system, and further development should result in meeting smoke goals for all fuels. Liner metal temperatures were higher than allowable for commercial application. Conceptual designs for further development of these two rich/lean and lean/lean concepts have been completed which address smoke and metal temperature concerns, and are available for the next phase of this NASA-sponsored, DOE-funded program. Tests of a rich/lean concept, and a catalytic combustor concept using low- and intermediate-Btu simulated coal-derived gases will be completed during the ongoing Phase IA extension of this program.

  12. Impacts of the Weatherization Assistance Program in fuel-oil heated houses

    Energy Technology Data Exchange (ETDEWEB)

    Levins, W.P.; Ternes, M.P.

    1994-10-01

    In 1990, the US Department of Energy (DOE) initiated a national evaluation of its lowincome Weatherization Assistance Program. This report, which is one of five parts of that evaluation, evaluates the energy savings and cost-effectiveness of the Program as it had been applied to single-family houses heated primarily by fuel-oil. The study was based upon a representative sample (41 local weatherization agencies, 222 weatherized and 115 control houses) from the nine northeastern states during 1991 and 1992 program years. Dwelling-specific and agency-level data on measures installed, costs, and service delivery procedures were collected from the sampled agencies. Space-heating fuel-oil consumption, indoor temperature, and outdoor temperature were monitored at each house. Dwelling characteristics, air-leakage measurements, space-heating system steady-state efficiency measurements, safety inspections, and occupant questionnaires were also collected or performed at each monitored house. We estimate that the Program weatherized a total of 23,400 single-family fuel-oil heated houses in the nine northeastern states during program years 1991 and 1992. Annual fuel-oil savings were calculated using regression techniques to normalize the savings to standard weather conditions. For the northeast region, annual net fuel-oil savings averaged 160 gallons per house, or 17.7% of pre-weatherization consumption. Although indoor temperatures changed in individual houses following weatherization, there was no average change and no significant difference as compared to the control houses; thus, there was no overall indoor temperature takeback effect influencing fuel-oil savings. The weatherization work was performed cost effectively in these houses from the Program perspective, which included both installation costs and overhead and management costs but did not include non-energy benefits (such as employment and environmental).

  13. Preliminary Compatibility Assessment of Metallic Dispenser Materials for Service in Ethanol Fuel Blends

    Energy Technology Data Exchange (ETDEWEB)

    Pawel, Steven J [ORNL; Kass, Michael D [ORNL; Janke, Christopher James [ORNL

    2009-11-01

    The compatibility of selected metals representative of those commonly used in dispensing systems was evaluated in an aggressive E20 formulation (CE20a) and in synthetic gasoline (Reference Fuel C) in identical testing to facilitate comparison of results. The testing was performed at modestly elevated temperature (nominally 60 C) and with constant fluid flow in an effort to accelerate potential interactions in the screening test. Based on weight change, the general corrosion of all individual coupons exposed in the vapor phase above Reference Fuel C and CE20a as well as all coupons immersed in Reference Fuel C was essentially nil (<0.3 {micro}m/y), with no evidence of localized corrosion such as pitting/crevice corrosion or selective leaching at any location. Modest discoloration was observed on the copper-based alloys (cartridge brass and phosphor bronze), but the associated corrosion films were quite thin and apparently protective. For coupons immersed in CE20a, four different materials exhibited net weight loss over the entire course of the experiment: cartridge brass, phosphor bronze, galvanized steel, and terne-plated steel. None of these exhibited substantial incompatibility with the test fluid, with the largest general corrosion rate calculated from coupon weight loss to be approximately 4 {micro}m/y for the cartridge brass specimens. Selective leaching of zinc (from brass) and tin (from bronze) was observed, as well as the presence of sulfide surface films rich in these elements, suggesting the importance of the role of sulfuric acid in the CE20a formulation. Analysis of weight loss data for the slightly corroded metals indicated that the corrosivity of the test environment decreased with exposure time for brass and bronze and increased for galvanized and terne-plated steel. Other materials immersed in CE20a - type 1020 mild steel, type 1100 aluminum, type 201 nickel, and type 304 stainless steel - each appeared essentially immune to corrosion at the test

  14. EPAct Alternative Fuel Transportation Program: State and Alternative Fuel Provider Fleet Compliance Annual Report, Fleet Compliance Results for MY 2014/ FY 2015

    Energy Technology Data Exchange (ETDEWEB)

    2016-04-01

    This annual report of the Alternative Fuel Transportation Program, which ensures compliance with DOE regulations covering state government and alternative fuel provider fleets pursuant to the Energy Policy Act of 1992 (EPAct), as amended, provides fleet compliance results for manufacturing year 2014 / fiscal year 2015.

  15. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    Energy Technology Data Exchange (ETDEWEB)

    ELGIN, J.C.

    2000-10-02

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  16. Near-term hybrid vehicle program, phase 1. Appendix C: Preliminary design data package

    Science.gov (United States)

    1979-01-01

    The design methodology, the design decision rationale, the vehicle preliminary design summary, and the advanced technology developments are presented. The detailed vehicle design, the vehicle ride and handling and front structural crashworthiness analysis, the microcomputer control of the propulsion system, the design study of the battery switching circuit, the field chopper, and the battery charger, and the recent program refinements and computer results are presented.

  17. CERCA LEU fuel assemblies testing in Maria Reactor - safety analysis summary and testing program scope.

    Energy Technology Data Exchange (ETDEWEB)

    Pytel, K.; Mieleszczenko, W.; Lechniak, J.; Moldysz, A.; Andrzejewski, K.; Kulikowska, T.; Marcinkowska, A.; Garner, P. L.; Hanan, N. A.; Nuclear Engineering Division; Institute of Atomic Energy (Poland)

    2010-03-01

    The presented paper contains neutronic and thermal-hydraulic (for steady and unsteady states) calculation results prepared to support annex to Safety Analysis Report for MARIA reactor in order to obtain approval for program of testing low-enriched uranium (LEU) lead test fuel assemblies (LTFA) manufactured by CERCA. This includes presentation of the limits and operational constraints to be in effect during the fuel testing investigations. Also, the scope of testing program (which began in August 2009), including additional measurements and monitoring procedures, is described.

  18. Study of operational parameters impacting helicopter fuel consumption. [using computer techniques (computer programs)

    Science.gov (United States)

    Cross, J. L.; Stevens, D. D.

    1976-01-01

    A computerized study of operational parameters affecting helicopter fuel consumption was conducted as an integral part of the NASA Civil Helicopter Technology Program. The study utilized the Helicopter Sizing and Performance Computer Program (HESCOMP) developed by the Boeing-Vertol Company and NASA Ames Research Center. An introduction to HESCOMP is incorporated in this report. The results presented were calculated using the NASA CH-53 civil helicopter research aircraft specifications. Plots from which optimum flight conditions for minimum fuel use that can be obtained are presented for this aircraft. The results of the study are considered to be generally indicative of trends for all helicopters.

  19. Chemical Reactivity Testing for the National Spent Nuclear Fuel Program. Quality Assurance Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    Newsom, H.C.

    1999-01-24

    This quality assurance project plan (QAPjP) summarizes requirements used by Lockheed Martin Energy Systems, Incorporated (LMES) Development Division at Y-12 for conducting chemical reactivity testing of Department of Energy (DOE) owned spent nuclear fuel, sponsored by the National Spent Nuclear Fuel Program (NSNFP). The requirements are based on the NSNFP Statement of Work PRO-007 (Statement of Work for Laboratory Determination of Uranium Hydride Oxidation Reaction Kinetics.) This QAPjP will utilize the quality assurance program at Y-12, QA-101PD, revision 1, and existing implementing procedures for the most part in meeting the NSNFP Statement of Work PRO-007 requirements, exceptions will be noted.

  20. Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report.

    Energy Technology Data Exchange (ETDEWEB)

    Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Klennert, Lindsay A.; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Molecke, Martin Alan; Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Steyskal, Michele D.

    2008-03-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO{sub 2}, CeO{sub 2}, plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively

  1. Preliminary Assessment of Non-Fuel Mineral Resources of Afghanistan, 2007

    Science.gov (United States)

    ,

    2007-01-01

    Introduction Afghanistan has abundant mineral resources, including known deposits of copper, iron, barite, sulfur, talc, chromium, magnesium, salt, mica, marble, rubies, emeralds, lapis lazuli, asbestos, nickel, mercury, gold and silver, lead, zinc, fluorspar, bauxite, beryllium, and lithium (fig. 1). Between 2005 and 2007, the U.S. Agency for International Development (USAID) funded a cooperative study by the U.S. Geological Survey (USGS) and the Afghanistan Geological Survey (AGS) to assess the non-fuel mineral resources of Afghanistan as part of the effort to aid in the reconstruction of that country. An assessment is an estimation or evaluation, in this instance of undiscovered non-fuel mineral resources. Mineral resources are materials that are in such form that economic extraction of a commodity is currently or potentially feasible. In this assessment, teams of scientists from the USGS and the AGS compiled information about known mineral deposits and then evaluated the possible occurrence of undiscovered deposits of all types. Quantitative probabilistic estimates were made for undiscovered deposits of copper, mercury, rare-earth elements, sulfur, chromite, asbestos, potash, graphite, and sand and gravel. These estimates were made for undiscovered deposits at depths less than a kilometer. Other deposit types were considered and discussed in the assessment, but quantitative estimates of numbers of undiscovered deposits were not made. In addition, the assessment resulted in the delineation of 20 mineralized areas for further study, of which several may contain resources amenable to rapid development.

  2. Preliminary model and validation of molten carbonate fuel cell kinetics under sulphur poisoning

    Science.gov (United States)

    Audasso, E.; Nam, S.; Arato, E.; Bosio, B.

    2017-06-01

    MCFC represents an effective technology to deal with CO2 capture and relative applications. If used for these purposes, due to the working conditions and the possible feeding, MCFC must cope with a different number of poisoning gases such as sulphur compounds. In literature, different works deal with the development of kinetic models to describe MCFC performance to help both industrial applications and laboratory simulations. However, in literature attempts to realize a proper model able to consider the effects of poisoning compounds are scarce. The first aim of the present work is to provide a semi-empirical kinetic formulation capable to take into account the effects that sulphur compounds (in particular SO2) have on the MCFC performance. The second aim is to provide a practical example of how to effectively include the poisoning effects in kinetic models to simulate fuel cells performances. To test the reliability of the proposed approach, the obtained formulation is implemented in the kinetic core of the SIMFC (SIMulation of Fuel Cells) code, an MCFC 3D model realized by the Process Engineering Research Team (PERT) of the University of Genova. Validation is performed through data collected at the Korea Institute of Science and Technology in Seoul.

  3. Fuel Cell Development for NASA's Human Exploration Program: Benchmarking with "The Hydrogen Economy"

    Science.gov (United States)

    Scott, John H.

    2007-01-01

    The theoretically high efficiency and low temperature operation of hydrogen-oxygen fuel cells has motivated them to be the subject of much study since their invention in the 19th Century, but their relatively high life cycle costs kept them as a "solution in search of a problem" for many years. The first problem for which fuel cells presented a truly cost effective solution was that of providing a power source for NASA's human spaceflight vehicles in the 1960 s. NASA thus invested, and continues to invest, in the development of fuel cell power plants for this application. This development program continues to place its highest priorities on requirements for minimum system mass and maximum durability and reliability. These priorities drive fuel cell power plant design decisions at all levels, even that of catalyst support. However, since the mid-1990's, prospective environmental regulations have driven increased governmental and industrial interest in "green power" and the "Hydrogen Economy." This has in turn stimulated greatly increased investment in fuel cell development for a variety of commercial applications. This investment is bringing about notable advances in fuel cell technology, but, as these development efforts place their highest priority on requirements for minimum life cycle cost and field safety, these advances are yielding design solutions quite different at almost every level from those needed for spacecraft applications. This environment thus presents both opportunities and challenges for NASA's Human Exploration Program

  4. Fuel cell programs in the United States for stationary power applications

    Energy Technology Data Exchange (ETDEWEB)

    Singer, M.

    1996-04-01

    The Department of Energy (DOE), Office of Fossil Energy, is participating with the private sector in sponsoring the development of molten carbonate fuel cell (MCFC) and solid oxide fuel cell (SOFC) technologies for application in the utility, commercial and industrial sectors. Phosphoric acid fuel cell (PAFC) development was sponsored by the Office of Fossil Energy in previous years and is now being commercialized by the private sector. Private sector participants with the Department of Energy include the Electric Power Research Institute (EPRI), the Gas Research institute (GRI), electric and gas utilities, universities, manufacturing companies and their suppliers. through continued government and private sector support, fuel cell systems are emerging power generation technologies which are expected to have significant worldwide impacts. An industry with annual sales of over a billion dollars is envisioned early in the 21st century. PAFC power plants have begun to enter the marketplace and MCFC and SOFC power plants are expected to be ready to enter the marketplace in the late 1990s. In support of the efficient and effective use of our natural resources, the fuel cell program seeks to increase energy efficiency and economic effectiveness of power generation. This is to be accomplished through effectiveness of power generation. This is accomplished through the development and commercialization of cost-effective, efficient and environmentally desirable fuel cell systems which will operate on fossil fuels in multiple and end use sectors.

  5. Coated Particle Fuel and Deep Burn Program Monthly Highlights March 2011

    Energy Technology Data Exchange (ETDEWEB)

    Snead, Lance Lewis [ORNL; Bell, Gary L [ORNL; Besmann, Theodore M [ORNL

    2011-04-01

    During FY 2011 the CP & DB Program will report Highlights on a monthly basis, but will no longer produce Quarterly Progress Reports. Technical details that were previously included in the quarterly reports will be included in the appropriate Milestone Reports that are submitted to FCRD Program Management. These reports will also be uploaded to the Deep Burn website. The Monthly Highlights report for February 2011, ORNL/TM-2011/71, was distributed to program participants on March 8, 2011. As reported previously, the final Quarterly for FY 2010, Deep Burn Program Quarterly Report for July - September 2010, ORNL/TM-2010/301, was announced to program participants and posted to the website on December 28, 2010. This report discusses the following: (1) Thermochemical Data and Model Development - (a) Thermochemical Modeling, (b) Thermomechanical Behavior, (c) Actinide and Fission Product Transport, (d) Radiation Damage and Properties; (2) TRU (transuranic elements) TRISO (tri-structural isotropic) Development - (a) TRU Kernel Development, (b) Coating Development; (3) Advanced TRISO Applications - Metal Matrix Fuels for LWR; (4) LWR Fully Ceramic Fuel - (a) FCM Fabrication Development, (b) FCM Irradiation Testing; and (5) Fuel Performance and Analytical Analysis - Fuel Performance Modeling.

  6. Coated Particle Fuel and Deep Burn Program Monthly Highlights February 2011

    Energy Technology Data Exchange (ETDEWEB)

    Snead, Lance Lewis [ORNL; Bell, Gary L [ORNL; Besmann, Theodore M [ORNL

    2011-03-01

    During FY 2011 the CP & DB Program will report Highlights on a monthly basis, but will no longer produce Quarterly Progress Reports. Technical details that were previously included in the quarterly reports will be included in the appropriate Milestone Reports that are submitted to FCRD Program Management. These reports will also be uploaded to the Deep Burn website. The Monthly Highlights report for January 2010, ORNL/TM-2011/30, was distributed to program participants on February 8, 2011. As reported previously, the final Quarterly for FY 2010, Deep Burn Program Quarterly Report for July - September 2010, ORNL/TM-2010/301, was announced to program participants and posted to the website on December 28, 2010. This report discusses the following: (1) Thermochemical Data and Model Development - (a) Thermochemical Modeling, (b) Actinide and Fission Product Transport, (c) Radiation Damage and Properties; (2) TRU (transuranic elements) TRISO (tri-structural isotropic) Development - (a) TRU Kernel Development, (b) Coating Development; (3) Advanced TRISO Applications - Metal Matrix Fuels for LWR; (4) LWR Fully Ceramic Fuel - (a) FCM Fabrication Development, (b) FCM Irradiation Testing; and (5) Fuel Performance and Analytical Analysis - Fuel Performance Modeling.

  7. Coated Particle Fuel and Deep Burn Program Monthly Highlights January 2011

    Energy Technology Data Exchange (ETDEWEB)

    Snead, Lance Lewis [ORNL; Bell, Gary L [ORNL; Besmann, Theodore M [ORNL

    2011-02-01

    During FY 2011 the CP & DB Program will report Highlights on a monthly basis, but will no longer produce Quarterly Progress Reports. Technical details that were previously included in the quarterly reports will be included in the appropriate Milestone Reports that are submitted to FCRD Program Management. These reports will also be uploaded to the Deep Burn website. The Monthly Highlights report for December 2010, ORNL/TM-2011/10, was distributed to program participants on January 12, 2011. As reported last month, the final Quarterly for FY 2010, Deep Burn Program Quarterly Report for July - September 2010, ORNL/TM-2010/301, was announced to program participants and posted to the website on December 28, 2010. This report discusses the following: (1) Thermochemical Data and Model Development - (a) Thermochemical Modeling, (b) Actinide and Fission Product Transport, (c) Radiation Damage and Properties; (2) TRU (transuranic elements) TRISO (tri-structural isotropic) Development - (a) TRU Kernel Development, (b) Coating Development; (3) Advanced TRISO Applications - Metal Matrix Fuels for LWR; (4) LWR Fully Ceramic Fuel - (a) FCM Fabrication Development, (b) FCM Irradiation Testing; (5) Fuel Performance and Analytical Analysis - Fuel Performance Modeling.

  8. CANDU advanced fuel R and D programs for 1997 - 2006 in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Suk, H.C.; Yang, M.S.; Sim, K-S.; Yoo, K.J. [Korea Atomic Energy Research Inst., Yusong, Taejon (Korea, Republic of)

    1997-07-01

    KAERI has a comprehensive product development program of CANFLEX and DUPIC fuels to introduce them into CANDU reactors in Korea and a clear vision of how the product will evolve over the next 10 years. CANDU reactors are not the majority of nuclear power plants in Korea, but they produce significant electricity to contribute Korea's economic growth as well as to satisfy the need for energy. The key targets of the development program are safety enhancement, reduction of spent fuel volume, and economic improvements, using the inherent characteristics and advantages of CANDU technology The CANFLEX and DUPIC R and D programs are conducted currently under the second stage of Korea's Nuclear Energy R and D Project as a national mid- and long-term program over the next 10 years from 1997 to 2006. The specific activities of the programs have taken account of the domestic and international environment concerning on non-proliferation in the Peninsula of Korea. As the first of the development products in the short-term, the CANFLEX-NU fuel will be completely developed jointly by KAERI/AECL and will be useful for the older CANDU-6 Wolsong unit 1. As the second product, the CANFLEX-0.9 % equivalent SEU fuel is expected to be completely developed within the next decade. It will be used in CANDU-6 reactors in Korea immediately after the development, if the existing RU in the world is price competitive with natural uranium. The DUPIC R and D program, as a long term program, is expected to demonstrate the possibility of use of used PWR fuel in CANDU reactors in Korea during the next 10 years. The pilot scale fabrication facility would be completed around 2010. (author)

  9. SOLID STATE ENERGY CONVERSION ALLIANCE (SECA) SOLID OXIDE FUEL CELL PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen Minh; Jim Powers

    2003-10-01

    This report summarizes the work performed for April 2003--September 2003 reporting period under Cooperative Agreement DE-FC26-01NT41245 for the U.S. Department of Energy, National Energy Technology Laboratory (DOE/NETL) entitled ''Solid State Energy Conversion Alliance (SECA) Solid oxide Fuel Cell Program''. During this reporting period, the conceptual system design activity was completed. The system design, including strategies for startup, normal operation and shutdown, was defined. Sealant and stack materials for the solid oxide fuel cell (SOFC) stack were identified which are capable of meeting the thermal cycling and degradation requirements. A cell module was tested which achieved a stable performance of 0.238 W/cm{sup 2} at 95% fuel utilization. The external fuel processor design was completed and fabrication begun. Several other advances were made on various aspects of the SOFC system, which are detailed in this report.

  10. Fuel cell program - Overview reports 2007; Programm Brennstoffzellen inkl. Wasserstoff - Ueberblicksberichte der BFE-Programmleiter 2007

    Energy Technology Data Exchange (ETDEWEB)

    Luzzi, A.; Spirig, M.

    2008-07-01

    This report for the Swiss Federal Office of Energy (SFOE) presents the overview reports made by SFOE Heads of Program on work done in 2007. Projects reported on in the natural gas-fired fuel cell area include the EU-project REAL-SFOC, the long-term testing of anode-supported SOFC stacks, intermediate-temperature fuel cells based on proton conducting electrolytes, the interdisciplinary ONEBAT project and lifetime-enhancement of SOFC stacks for CHP applications. In the polymer-electrolyte fuel cell (PEFC) area, projects concerning proton-conducting polymer membranes, factors limiting the lifetime of fuel cell membranes, a new highly active oxygen reduction electrode for PEM fuel cell and zinc/air battery applications, the enhancement of PEFC durability and reliability, model-based investigation of PEFC performance, and local gas analysis of PE fuel cells are briefly reported on. Long-term research activities in the hydrogen technology area reported on include those concerning the photo-chemical conversion and storage of solar energy and the storage of hydrogen in metallic and complex hydrides. Further projects reported on include those concerning the physical aspects of hydrides for system integration and safety and new, complex metal hydrides. Swiss national and international co-ordination is reviewed in the areas of fuel cell technology and hydrogen technology. Work done in several projects run within the framework of the IEA's Advanced Fuel Cells Program is reviewed. Several pilot and demonstration (P and D) projects are also reported on in the natural-gas SOFC and PEFC areas. Comments on the 2007 results and a review of work to be done in 2008, along with a list of R, D, P and D projects, complete the report.

  11. Preliminary Thermohydraulic Analysis of a New Moderated Reactor Utilizing an LEU-Fuel for Space Nuclear Thermal Propulsion

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Seung Hyun; Choi, Jae Young; Venneria, Paolo F.; Jeong, Yong Hoon; Chang, Soon Heung [KAIST, Daejeon (Korea, Republic of)

    2015-10-15

    The Korea Advanced NUclear Thermal Engine Rocket utilizing an LEU fuel (KANUTER-LEU) is a non-proliferative and comparably efficient NTR engine with relatively low thrust levels of 40 - 50 kN for in-space transportation. The small modular engine can expand mission versatility, when flexibly used in a clustered engine arrangement, so that it can perform various scale missions from low-thrust robotic science missions to high-thrust manned missions. In addition, the clustered engine system can enhance engine redundancy and ensuing crew safety as well as the thrust. The propulsion system is an energy conversion system to transform the thermal energy of the reactor into the kinetic energy of the propellant to produce the powers for thrust, propellant feeding and electricity. It is mainly made up of a propellant Feeding System (PFS) comprising a Turbo-Pump Assembly (TPA), a Regenerative Nozzle Assembly (RNA), etc. For this core design study, an expander cycle is assumed to be the propulsion system. The EGS converts the thermal energy of the EHTGR in the idle operation (only 350 kW{sub th} power) to electric power during the electric power mode. This paper presents a preliminary thermohydraulic design analysis to explore the design space for the new reactor and to estimate the referential engine performance. The new non-proliferative NTR engine concept, KANUTER-LEU, is under designing to surmount the nuclear proliferation obstacles on allR and Dactivities and eventual commercialization for future generations. To efficiently implement a heavy LEU fuel for the NTR engine, its reactor design innovatively possesses the key characteristics of the high U density fuel with high heating and H{sub 2} corrosion resistances, the thermal neutron spectrum core and also minimizing non-fission neutron loss, and the compact reactor design with protectively cooling capability. To investigate feasible design space for the moderated EHTGR-LEU and resultant engine performance, the

  12. Preliminary assessment of the prospects for use of refuse-derived fuel in Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Metz, W.C.; Shyer, J.; Edgecomb, K.

    1979-02-01

    The deployment problems of refuse derived fuel (RDF) production in Maryland are examined. Problems experienced by the pyrolysis plant in Baltimore City and the resource recovery plant in Baltimore County are cited. Maryland's municipal solid waste problems are discussed with emphasis on the major components of the municipal solid waste stream, e.g., volume, composition, and location; collection methods used; present and long-range disposal methods; and regulations and ordinances. The generic social and legal constraints to RDF production are described. The problems of RDF technology deployment in Maryland, i.e., county and state RDF energy potential, institutional barriers to RDF production and use, remitting requirements for new RDF production and use facilities, water quality issues of RDF production and use, air quality issues of RDF production and use, and recommendations for initiating RDF production and use are discussed.

  13. A preliminary approach to the extension of the Transuranus code to the fuel rod performance analysis of HLM-cooled nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Luzzi, L.; Botazzoli, P.; Devita, M.; Di Marcello, V.; Pastore, G. [Department of Energy, Politecnico di Milano, Enrico Fermi Center for Nuclear Studies - CeSNEF, via Ponzio 34/3, 20133 Milano (Italy)

    2010-07-01

    This paper briefly presents a preliminary modelling approach, aimed at the extension of the TRANSURANUS code to the fuel rod performance analysis of Heavy Liquid Metal (HLM) cooled nuclear reactors, with specific reference to the employment of the T91 steel as cladding material and of the liquid Lead-Bismuth Eutectic (LBE) as coolant. On the basis of literature indications, correlations for heat transfer to LBE, corrosion behaviour and thermo-mechanical properties of T91 are proposed, and some open issues are discussed in prospect of more reliable fuel rod performance analysis of HLM-cooled nuclear reactors. (authors)

  14. Enhancing instruction in Fuels and Combustion Laboratory via a developed computer-assisted program for establishing efficient coal-diesel oil mixture (CDOM) fuel proportions

    Energy Technology Data Exchange (ETDEWEB)

    Maglaya, A.B. [La Salle University, Manila (Philippines). Dept. of Mechanical Engineering

    2004-07-01

    This paper discusses the relevance of digital computation in Fuels and Combustion Laboratory experiments used by the senior students of the Department of Mechanical Engineering, De La Salle University-Manila, Philippines. One of the students' experiments involved the determination of the most efficient CDOM fuel proportion as alternative fuel to diesel oil for steam generators and other industrial applications. Theoretical calculations show that it requires tedious and repetitive computations. A computer-assisted program was developed to lessen the time-consuming activities. The formulation of algorithms were based on the system of equations of the heat interaction between the CDOM fuel, combustion air and products of combustion and by applying the principles of mass and energy equations (or the First Law of Thermodynamics) for reacting systems were utilized. The developed computer-assisted program output verified alternative fuel selected through actual experimentation.

  15. Spent Fuel and Waste Management Technology Development Program. Annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Bryant, J.W.

    1994-01-01

    This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

  16. A Preliminary Study on the Conceptual Design of Thorium/Uranium Mixed Nuclear Fuel for the Alternative of Burnable Poison in Commercial Pressurized Water Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong Hwan; Kim, Song Hyun; Kim, Jong Kyung [Hanyang Univ., Seoul (Korea, Republic of)

    2013-10-15

    Thorium has higher neutron absorption cross section than that of U-238. Thus, the thorium mixed uranium oxide nuclear fuel can reduce the initial excessive reactivity and the long-live radio-wastes with increasing the fuel utilization efficiency. In this study, a preliminary study on the application of the thorium/uranium mixed fuel is performed for the alternative of the PLUS7 fuel assembly which includes burnable poison. A conceptual design without geometrical change is proposed and the reactor characteristics are analyzed. In this study, a fuel assembly using the uranium/thorium mixed fuel was designed to substitute the assembly which includes burnable poison. The reactor characteristics, which are k{sub inf}, power distribution and plutonium production rate, were evaluated and the results are compared with the E1 assembly which is used in the OPR1000 reactor. The results show that the proposed design can efficiently reduce the excessive reactivity, peak power, and plutonium production with increasing the fuel utilization period.

  17. The program cyberdiesel for mathematical modeling of fuel supply and local intracylinder processes in a diesel engine with volumetric carburetion

    OpenAIRE

    Maschenko, V. Yu.

    2007-01-01

    The program CyberDiesel is developed on the basis of complex mathematical model of fuel supply and local intracylinder processes in a diesel engine with volumetric carburetion. The program is intended for solving practical problems of coordinating constructive and adjusting parameters of fuel equipment and combustion chamber of a diesel engine by mathematical modeling methods.

  18. 78 FR 11903 - Acceptability of Corrective Action Programs for Fuel Cycle Facilities

    Science.gov (United States)

    2013-02-20

    ... Commission. ACTION: Draft NUREG; request for public comment. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG-2154 ``Acceptability of Corrective Action Programs for Fuel Cycle Facilities.'' The draft NUREG provides guidance to the NRC staff on how to determine...

  19. Aerothermal modeling program, Phase 2, Element C: Fuel injector-air swirl characterization

    Science.gov (United States)

    Mostafa, A. A.; Mongia, H. C.; Mcdonnel, V. G.; Samuelsen, G. S.

    1987-01-01

    The main objectives of the NASA sponsored Aerothermal Modeling Program, Phase 2, Element C, are to collect benchmark quality data to quantify the fuel spray interaction with the turbulent swirling flows and to validate current and advanced two phase flow models. The technical tasks involved in this effort are discussed.

  20. Pathways to Commercial Success: Technologies and Products Supported by the Fuel Cell Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    Weakley, Steven A.

    2012-09-28

    The purpose of the project described in this report is to identify and document the commercial and emerging (projected to be commercialized within the next 3 years) hydrogen and fuel cell technologies and products that resulted from Department of Energy support through the Fuel Cell Technologies (FCT) Program in the Office of Energy Efficiency and Renewable Energy (EERE). Pacific Northwest National Laboratory (PNNL) undertook two efforts simultaneously to accomplish this project. The first effort was a patent search and analysis to identify patents related to hydrogen and fuel cells that are associated with FCT-funded projects (or projects conducted by DOE-EERE predecessor programs) and to ascertain the patents’ current status, as well as any commercial products that may have used the technology documented in the patent. The second effort was a series of interviews with current and past FCT personnel, a review of relevant program annual reports, and an examination of grants made under the Small Business Innovation Research and Small Business Technology Transfer Programs that are related to hydrogen and fuel cells.

  1. Pathways to Commercial Success: Technologies and Products Supported by the Fuel Cell Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    Weakley, Steven A.; Brown, Scott A.

    2011-09-29

    The purpose of the project described in this report is to identify and document the commercial and emerging (projected to be commercialized within the next 3 years) hydrogen and fuel cell technologies and products that resulted from Department of Energy support through the Fuel Cell Technologies (FCT) Program in the Office of Energy Efficiency and Renewable Energy (EERE). To do this, Pacific Northwest National Laboratory (PNNL) undertook two efforts simultaneously to accomplish this project. The first effort was a patent search and analysis to identify hydrogen- and fuel-cell-related patents that are associated with FCT-funded projects (or projects conducted by DOE-EERE predecessor programs) and to ascertain the patents current status, as well as any commercial products that may have used the technology documented in the patent. The second effort was a series of interviews with current and past FCT personnel, a review of relevant program annual reports, and an examination of hydrogen- and fuel-cell-related grants made under the Small Business Innovation Research and Small Business Technology Transfer Programs, and within the FCT portfolio.

  2. Instrumentation program for rock mechanics and spent fuel tests at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Pratt, H.R.; Hustrulid, W.H.; Simonson, R.

    1978-08-01

    This report contains a discussion of an instrumentation and rock mechanics program recommended for consideration as part of the overall Lawrence Livermore nuclear waste storage program at NTS. It includes a discussion of (1) rationale for the heater tests, spent fuel facility evaluation, heated room tests, (2) recommended instrumentation types together with estimated delivery schedules, (3) recommended instrumentation layouts, (4) other proposed rock mechanics tests both laboratory and in situ, and (5) data acquisition and reduction requirements.

  3. Measuring Success in Your Fuels Program: From the Report Card to Valuable Learning

    Science.gov (United States)

    Paula Nasiatka; David Christenson

    2006-01-01

    How can a unit learn in everyday fuels programs and from program reviews? How can a unit move from living in the “report card” culture to discovering more effective ways to improve what it knows and how it learns? Six specific tasks are critical to organizational learning according to David A. Garvin of Harvard Business School. By engaging in these tasks a unit can...

  4. Industrial Fuel Gas Demonstration Plant Program: environmental permit compliance plan

    Energy Technology Data Exchange (ETDEWEB)

    Bodamer, Jr., James W.; Bocchino, Robert M.

    1979-11-01

    This Environmental Permit Compliance Plan is intended to assist the Memphis Light, Gas and Water Division in acquiring the necessary environmental permits for their proposed Industrial Fuel Gas Demonstration Plant in a time frame consistent with the construction schedule. Permits included are those required for installation and/or operation of gaseous, liquid and solid waste sources and disposal areas. Only those permits presently established by final regulations are described. The compliance plan describes procedures for obtaining each permit from identified federal, state and local agencies. The information needed for the permit application is presented, and the stepwise procedure to follow when filing the permit application is described. Information given in this plan was obtained by reviewing applicable laws and regulations and from telephone conversations with agency personnel on the federal, state and local levels. This Plan also presents a recommended schedule for beginning the work necessary to obtain the required environmental permits in order to begin dredging operations in October, 1980 and construction of the plant in September, 1981. Activity for several key permits should begin as soon as possible.

  5. Hydropyrolysis of biomass to produce liquid hydrocarbon fuels. Final report. Biomass Alternative-Fuels Program

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, R K; Bodle, W W; Yuen, P C

    1982-10-01

    The ojective of the study is to provide a process design and cost estimates for a biomass hydropyrolysis plant and to establish its economic viability for commercial applications. A plant site, size, product slate, and the most probable feedstock or combination of feedstocks were determined. A base case design was made by adapting IGT's HYFLEX process to Hawaiian biomass feedstocks. The HYFLEX process was developed by IGT to produce liquid and/or gaseous fuels from carbonaceous materials. The essence of the process is the simultaneous extraction of valuable oil and gaseous products from cellulosic biomass feedstocks without forming a heavy hard-to-handle tar. By controlling rection time and temperature, the product slate can be varied according to feedstock and market demand. An optimum design and a final assessment of the applicability of the HYFLEX process to the conversion of Hawaiian biomass was made. In order to determine what feedstocks could be available in Hawaii to meet the demands of the proposed hydropyrolysis plant, various biomass sources were studied. These included sugarcane and pineapple wastes, indigenous and cultivated trees and indigenous and cultivated shrubs and grasses.

  6. Microbial fuel cell with an algae-assisted cathode: A preliminary assessment

    Science.gov (United States)

    González del Campo, Araceli; Cañizares, Pablo; Rodrigo, Manuel A.; Fernández, Francisco J.; Lobato, Justo

    2013-11-01

    A microbial fuel cell (MFC) with an algae-assisted cathode, i.e., a system where the oxygen required by the cathode is not provided by aeration but by the photosynthetic process of the algae (Chlorella vulgaris), has been studied. The cathode was illuminated for 12 h each day (from 8:00 h to 20:00 h). 25 days was necessary to achieve steady state conditions. The time evolution of dissolved oxygen and cell voltage were assessed over the course of each day. As expected, the dissolved oxygen values were not constant throughout the day, reaching maximum values between 14:00 h and 20:00 h when dark phase reactions began and the algae started to consume oxygen. Cell voltage (Rext 120 Ω) followed the same trend as the oxygen profile. The supply of CO2 in the cathode was also studied, and half an hour was enough time to get the system working properly. During the acclimation stage, power density increased up to 13.5 mW m-2 at steady state conditions. However, impedance analysis showed that polarization resistance was higher at the cathode than at the anode. Nevertheless, it can be concluded that the studied system is a feasible method to treat wastewater in a self-sustainable way.

  7. Preliminary results of post-irradiation examination of the AGR-1 TRISO fuel compacts

    Energy Technology Data Exchange (ETDEWEB)

    Paul Demkowicz; John Hunn; Robert Morris; Jason Harp; Philip Winston; Charles Baldwin; Fred Montgomery; Scott Ploger; Isabella van Rooyen

    2012-10-01

    Five irradiated fuel compacts from the AGR-1 experiment have been examined in detail in order to assess in-pile fission product release behavior. Compacts were electrolytically deconsolidated and analyzed using the leach-burn-leach technique to measure fission product inventory in the compact matrix and identify any particles with a defective SiC layer. Loose particles were then gamma counted to measure the fission product inventory. One particle with a defective SiC layer was found in the five compacts examined. The fractional release of Ag 110m from the particles was significant. The total fraction of silver released from all the particles within a compact ranged from 0-0.63 and individual particles within a single compact often exhibited a very wide range of silver release. The average fractional release of Eu-154 from all particles in a compact was 2.4×10-4—1.3×10-2, which is indicative of release through intact coatings. The fractional Cs-134 inventory in the compact matrix was <2×10-5 when all coatings remained intact, indicating good cesium retention. Approximately 1% of the palladium inventory was found in the compact matrix for two of the compacts, indicating significant release through intact coatings.

  8. Preliminary assessment report for Waiawa Gulch, Installation 15080, Pearl City, Oahu, Hawaii. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Hawaii Army National Guard (HIARNG) property near Pearl City, Oahu, Hawaii. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the Waiawa Gulch property, phase I of the Department of Defense Installation Restoration Program (IRP).

  9. The U.S. Department of Energy, Office of Fossil Energy Stationary Fuel Cell Program

    Science.gov (United States)

    Williams, Mark C.; Strakey, Joseph P.; Surdoval, Wayne A.

    The U.S. Department of Energy (DOE) Office of Fossil Energy's (FE) National Energy Technology Laboratory (NETL), in partnership with private industries, is leading a program for the development and demonstration of high efficiency solid oxide fuel cells (SOFCs) and fuel cell/turbine hybrid power generation systems for near-term distributed generation markets, with emphasis on premium power and high reliability. NETL is partnering with Pacific Northwest National Laboratory (PNNL) in developing new directions for research under the Solid State Energy Conversion Alliance (SECA) initiative to develop and commercialize modular, low cost, and fuel flexible SOFC systems. Through advanced materials, processing and system integration research and development (R&D), the SECA initiative will reduce the fuel cell cost to $400 kW -1 for stationary and auxiliary power unit markets. The SECA industry teams and core program have made significant progress in scale-up and performance. Presidential initiatives are focusing research toward a new hydrogen economy. The movement to a hydrogen economy would accomplish several strategic goals, namely that SOFCs have no emissions, and hence figure significantly in DOE strategies. The SOFC hybrid is a key part of the FutureGen plant, a major new DOE FE initiative to produce hydrogen from coal. The highly efficient SOFC hybrid plant will produce electric power while other parts of the plant could produce hydrogen and sequester CO 2. The produced hydrogen can be used in fuel cell cars and for SOFC distributed generation applications.

  10. The Krakow clean fossil fuels and energy efficiency program

    Energy Technology Data Exchange (ETDEWEB)

    Feibus, H.

    1995-12-31

    The joint effort by Polish and American organizations in Krakow has accomplished a great deal in just a few years. In particular, the low emission sources program has had major successes. Poland and America have a lot to learn from each other in the clean and economical use of coal. Both our countries are major producers and users of coal. Both have had to deal with the emissions of particulate and organics from coal combustion. We were fortunate, since our free market economy and democratic government helped us deal with a lot of these problems in the 1950s. In Poland, the freedom to solve these problems has evolved only in the last few years. In the first phase of the program, Polish and American engineers ran combustion tests on boilers and stoves in Krakow. They also performed analyses on the cost and feasibility of various equipment changes. The results of the first phase were used in refining the spreadsheet model to give better estimates of costs emissions. The first phase also included analyses of incentives for proceeding with needed changes. These analyses identified actions needed to create a market for the goods and services which control pollution. Such actions could include privatization, regulation, or financial incentives. The second phase of the program consisted of public meetings in Chicago, Washington, and Krakow. The purpose of the meetings was to inform U.S. and Polish firms about the results of phase 1 and to encourage them to compete to take part in phase 3. The third phase currently underway consists of the commercial ventures that were competitively selected. These ventures were consistent with recommendations unanimously made by the BSC. The three phases of the Polish-American program are discussed.

  11. Preliminary evaluation of a microbial fuel cell treating artificial dialysis wastewater using graphene oxide

    Science.gov (United States)

    Goto, Yuko; Yoshida, Naoko

    2016-02-01

    Artificial dialysis wastewater (ADWW) generally contains 800-2,200 mg L-1 of organic matter. Prior to its discharge to the sewage system, ADWW must be treated in order to reduce organic matter to less than 600 mg L-1. This study assesses the applicability of a microbial fuel cell (MFC) to the reduction of organic matter in ADWW as an alternative pre-treatment system to aeration. In the MFC, conductive floccular aggregates microbially produced from graphene oxide (GO-flocs) were applied as an anode material in the MFC. The GO-flocs were obtained by anaerobic incubation of graphene oxide (GO) with microorganisms in ADWW at 28 °C for a minimum of 10 days. During incubation, GO in the mixture was transformed into black conductive floccular aggregates having 0.12 mS cm-1, suggesting the microbial reduction of GO to the reduced form. The produced GO-flocs were then used as the anode material in a cylindrical MFC, which was filled with ADWW and covered with a floating, platinum (Pt)-coated carbon cathode. The MFC was polarized via an external resistance of 10 Ω and applied for 120 days by replacing half of the supernatant of the MFC with fresh ADWW, every 6-9 days. As a result, the MFC achieved a 128 mg L-1 d-1 chemical oxygen demand (CODCr) removal rate. For example, the MFC contained 1,500 mg-CODCr L-1 just after replacement, with this concentration being reduced to 1,000 mg-CODCr L-1 after 6-9 days of incubation. At the same time, the MFC showed an average power density of 28 mW m-2 and a maximum power density of 291 mW m-2. These results suggest that a MFC packed with GO-flocs can be used as an alternative biotreatment system, replacing the energy-intensive aeration process.

  12. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Volume 1, Appendix B: Idaho National Engineering Laboratory Spent Nuclear Fuel Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.

  13. Liquefied Gaseous Fuels Safety and Environmental Control Assessment Program: second status report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-10-01

    This document is arranged in three volumes and reports on progress in the Liquefied Gaseous Fuels (LGF) Safety and Environmental Control Assessment Program made in fiscal Year (FY)-1979 and early FY-1980. Volume 3 contains reports from 6 government contractors on LPG, anhydrous ammonia, and hydrogen energy systems. Report subjects include: simultaneous boiling and spreading of liquefied petroleum gas (LPG) on water; LPG safety research; state-of-the-art of release prevention and control technology in the LPG industry; ammonia: an introductory assessment of safety and environmental control information; ammonia as a fuel, and hydrogen safety and environmental control assessment.

  14. Nerva Fuel Element Development Program Summary Report - July 1966 through June 1972 Extrusion Studies

    Energy Technology Data Exchange (ETDEWEB)

    Napier, J. M.

    1973-09-21

    This part of the completion report pertaining to the NERVA graphite fuel element program covers data collected during the extrusion studies. The physical properties of the fuel element reached the following values: coefficient of thermal expansion (CTE) - 7.0 x 10-6/o C (25 - l,OOOo C); modulus of elasticity - 1.5 x lo6 psi; flexural strength - - 8,000 psi; ultimate strain to failure - 5,500 pidin; good thermal stress resistance. Matrices were produced which could be vapor coated with crack-free films of zirconium carbide. The CTE of the matrix was almost equal to the CTE of the zirconium carbide coating.

  15. Coated Particle Fuel and Deep Burn Program Monthly Highlights June 2011

    Energy Technology Data Exchange (ETDEWEB)

    Snead, Lance Lewis [ORNL; Bell, Gary L [ORNL; Besmann, Theodore M [ORNL

    2011-07-01

    During FY 2011 the CP & DB Program will report Highlights on a monthly basis, but will no longer produce Quarterly Progress Reports. Technical details that were previously included in the quarterly reports will be included in the appropriate Milestone Reports that are submitted to FCRD Program Management. These reports will also be uploaded to the Deep Burn website. The Monthly Highlights report for May 2011, ORNL/TM-2011/126, was distributed to program participants on June 9, 2011. As reported previously, the final Quarterly for FY 2010, Deep Burn Program Quarterly Report for July - September 2010, ORNL/TM-2010/301, was announced to program participants and posted to the website on December 28, 2010. This report discusses the following: (1) Fuel Performance Modeling - Fuel Performance Analysis; (2) Thermochemical Data and Model Development - (a) Thermochemical Behavior, (b) Thermomechanical Modeling, (c) Actinide and Fission Product Transport; (3) TRU (transuranic elements) TRISO (tri-structural isotropic) Development - (a) TRU Kernel Development, (b) Coating Development; and (4) LWR Fully Ceramic Fuel - (a) FCM Fabrication Development, (b) FCM Irradiation Testing.

  16. SOLID STATE ENERGY CONVERSION ALLIANCE (SECA) SOLID OXIDE FUEL CELL PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    Unknown

    2003-06-01

    This report summarizes the progress made during the September 2001-March 2002 reporting period under Cooperative Agreement DE-FC26-01NT41245 for the U. S. Department of Energy, National Energy Technology Laboratory (DOE/NETL) entitled ''Solid State Energy Conversion Alliance (SECA) Solid Oxide Fuel Cell Program''. The program focuses on the development of a low-cost, high-performance 3-to-10-kW solid oxide fuel cell (SOFC) system suitable for a broad spectrum of power-generation applications. The overall objective of the program is to demonstrate a modular SOFC system that can be configured to create highly efficient, cost-competitive, and environmentally benign power plants tailored to specific markets. When fully developed, the system will meet the efficiency, performance, life, and cost goals for future commercial power plants.

  17. Summary of national and international fuel cycle and radioactive waste management programs, 1984

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-07-01

    Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

  18. PRELIMINARY STUDY OF CERAMICS FOR IMMOBILIZATION OF ADVANCED FUEL CYCLE REPROCESSING WASTES

    Energy Technology Data Exchange (ETDEWEB)

    Fox, K.; Billings, A.; Brinkman, K.; Marra, J.

    2010-09-22

    The Savannah River National Laboratory (SRNL) developed a series of ceramic waste forms for the immobilization of Cesium/Lanthanide (CS/LN) and Cesium/Lanthanide/Transition Metal (CS/LN/TM) waste streams anticipated to result from nuclear fuel reprocessing. Simple raw materials, including Al{sub 2}O{sub 3}, CaO, and TiO{sub 2} were combined with simulated waste components to produce multiphase ceramics containing hollandite-type phases, perovskites (particularly BaTiO{sub 3}), pyrochlores, zirconolite, and other minor metal titanate phases. Identification of excess Al{sub 2}O{sub 3} via X-ray Diffraction (XRD) and Scanning Electron Microscopy with Energy Dispersive Spectroscopy (SEM/EDS) in the first series of compositions led to a Phase II study, with significantly reduced Al{sub 2}O{sub 3} concentrations and increased waste loadings. Three fabrication methodologies were used, including melting and crystallizing, pressing and sintering, and Spark Plasma Sintering (SPS), with the intent of studying phase evolution under various sintering conditions. XRD and SEM/EDS results showed that the partitioning of the waste elements in the sintered materials was very similar, despite varying stoichiometry of the phases formed. The Phase II compositions generally contained a reduced amount of unreacted Al{sub 2}O{sub 3} as identified by XRD, and had phase assemblages that were closer to the initial targets. Chemical composition measurements showed no significant issues with meeting the target compositions. However, volatilization of Cs and Mo was identified, particularly during melting, since sintering of the pressed pellets and SPS were performed at lower temperatures. Partitioning of some of the waste components was difficult to determine via XRD. SEM/EDS mapping showed that those elements, which were generally present in small concentrations, were well distributed throughout the waste forms. Initial studies of radiation damage tolerance using ion beam irradiation at Los

  19. Fuels planning: science synthesis and integration; social issues fact sheet 01: Developing personal responsibility for fuels reduction: Building a successful program to engage property owners

    Science.gov (United States)

    Rocky Mountain Research Station USDA Forest Service

    2004-01-01

    In the course of work as a land manager, you will no doubt be involved in developing programs to achieve various objectives, including the improvement of fuels management on private lands. This fact sheet describes six steps that will help you plan and conduct a successful program.

  20. The development and preliminary effectiveness of a nursing case management e-learning program.

    Science.gov (United States)

    Liu, Wen-I; Chu, Kuo-Chung; Chen, Shing-Chia

    2014-07-01

    The purpose of this article was to describe the development and preliminary effectiveness of a digital case management education program. The e-learning program was built through the collaboration of a nurse educator and an informatics professor. The program was then developed according to the following steps: (1) building a visual interface, (2) scripting each unit, (3) preparing the course material and assessment tests, (4) using teaching software to record audio and video courses, (5) editing the audio recordings, (6) using instructional media or hyperlinks to finalize the interactions, (7) creating the assessment and obtaining feedback, and (8) testing the overall operation. The digital program consisted of five learning modules, self-assessment questions, learning cases, sharing experiences, and learning resources. Forty nurses participated in this study and fully completed the questionnaires both before and after the program. The knowledge and confidence levels in the experimental group were significantly higher over time than those of the comparison group. The results supported the use of educational technology to provide a more flexible and effective presentation method for continuing education programs.

  1. Cognitive Vocal Program applied to individuals with signals presbylarynx: preliminary results.

    Science.gov (United States)

    Nemr, Katia; Souza, Glaucia Verena Sampaio de; Simões-Zenari, Marcia; Tsuji, Domingos Hiroshi; Hachiya, Adriana; Cordeiro, Gislaine Ferro; Nunes, Guilherme Pecoraro; Dajer, María Eugenia

    2014-01-01

    To propose and verify the feasibility of a vocal program intervention in patients with presbylarynx signs with or without vocal complaints. Among 20 elder participants of the current research, 3 female patients with median age of 67 years were chosen for the pilot study. Laryngological examination, vocal recording with CAPE-V (Consensus Auditory-Perceptual Evaluation of Voice) protocol, and Screening Protocol of Risk of Dysphonia (SPRD) were conducted before and after the program intervention. They joined the Cognitive Vocal Program for presbyphonia based on the genetic epistemology by Jean Piaget associated with vocal techniques based on scientific literature. This program is structured with six sessions and each one of them is focused in different aspects of vocal production. After the program intervention, some aspects such as loudness, coordination between breathing and speaking, accuracy in articulatory movements, jitter, and harmonics-to-noise ratio improved with parameters within the expected range for the age group. Three female participants were observed for better vocal quality, higher fundamental frequency, and better maximum phonation time. In two cases, tension related to loudness elevation and better scores on SPRD was observed. Using by high-speed laryngeal image, we also observed reduction of presbylarynx signs, and remarkable improvement in glottis closure competence and mucosal wave movement of the patients with and without vocal complaints. The preliminary results suggest encouraging prospects for the proposal with improvement in the aspects analyzed. This program was well designed and did not require any further adjustments.

  2. Solid State Energy Conversion Alliance (SECA) Solid Oxide Fuel Cell Program

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen Minh

    2006-07-31

    This report summarizes the work performed for Phase I (October 2001 - August 2006) under Cooperative Agreement DE-FC26-01NT41245 for the U. S. Department of Energy, National Energy Technology Laboratory (DOE/NETL) entitled 'Solid State Energy Conversion Alliance (SECA) Solid Oxide Fuel Cell Program'. The program focuses on the development of a low-cost, high-performance 3-to-10-kW solid oxide fuel cell (SOFC) system suitable for a broad spectrum of power-generation applications. During Phase I of the program significant progress has been made in the area of SOFC technology. A high-efficiency low-cost system was designed and supporting technology developed such as fuel processing, controls, thermal management, and power electronics. Phase I culminated in the successful demonstration of a prototype system that achieved a peak efficiency of 41%, a high-volume cost of $724/kW, a peak power of 5.4 kW, and a degradation rate of 1.8% per 500 hours. . An improved prototype system was designed, assembled, and delivered to DOE/NETL at the end of the program. This prototype achieved an extraordinary peak efficiency of 49.6%.

  3. Synthesis and Characterization of Oxide Feedstock Powders for the Fuel Cycle R&D Program

    Energy Technology Data Exchange (ETDEWEB)

    Voit, Stewart L [ORNL; Vedder, Raymond James [ORNL; Johnson, Jared A [ORNL

    2010-09-01

    Nuclear fuel feedstock properties, such as physical, chemical, and isotopic characteristics, have a significant impact on the fuel fabrication process and, by extension, the in-reactor fuel performance. This has been demonstrated through studies with UO{sub 2} spanning greater than 50 years. The Fuel Cycle R&D Program with The Department of Energy Office of Nuclear Energy has initiated an effort to develop a better understanding of the relationships between oxide feedstock, fresh fuel properties, and in-reactor fuel performance for advanced mixed oxide compositions. Powder conditioning studies to enable the use of less than ideal powders for ceramic fuel pellet processing are ongoing at Los Alamos National Laboratory (LANL) and an understanding of methods to increase the green density and homogeneity of pressed pellets has been gained for certain powders. Furthermore, Oak Ridge National Laboratory (ORNL) is developing methods for the co-conversion of mixed oxides along with techniques to analyze the degree of mixing. Experience with the fabrication of fuel pellets using co-synthesized multi-constituent materials is limited. In instances where atomically mixed solid solutions of two or more species are needed, traditional ceramic processing methods have been employed. Solution-based processes may be considered viable synthesis options, including co-precipitation (AUPuC), direct precipitation, direct-conversion (Modified Direct Denitration or MDD) and internal/external gelation (sol-gel). Each of these techniques has various advantages and disadvantages. The Fiscal Year 2010 feedstock development work at ORNL focused on the synthesis and characterization of one batch of UO{sub x} and one batch of U{sub 80}Ce{sub 20}O{sub x}. Oxide material synthesized at ORNL is being shipped to LANL for fuel fabrication process development studies. The feedstock preparation was performed using the MDD process which utilizes a rotary kiln to continuously thermally denitrate double

  4. Coated Particle Fuel and Deep Burn Program Monthly Highlights April 2011

    Energy Technology Data Exchange (ETDEWEB)

    Snead, Lance Lewis [ORNL; Bell, Gary L [ORNL; Besmann, Theodore M [ORNL

    2011-05-01

    The baseline change proposal BCP-FCRD-11026 submitted to change the due date for M21AF080202 'Demonstrate fabrication of Transuranic kernels of Plutonium-239/3.5at%Neptunium-237 using newly installed glove box facilities in ORNL 7930 hot cell complex' from 4/25/11 to 3/30/12 was approved this month. During FY 2011 the CP & DB Program will report Highlights on a monthly basis, but will no longer produce Quarterly Progress Reports. Technical details that were previously included in the quarterly reports will be included in the appropriate Milestone Reports that are submitted to FCRD Program Management. These reports will also be uploaded to the Deep Burn website. The Monthly Highlights report for March 2011, ORNL/TM-2011/96, was distributed to program participants on April 8, 2011. As reported previously, the final Quarterly for FY 2010, Deep Burn Program Quarterly Report for July - September 2010, ORNL/TM-2010/301, was announced to program participants and posted to the website on December 28, 2010. This report discusses the following: (1) Thermochemical Data and Model Development - (a) Thermochemical Modeling, (b) Thermomechanical Behavior, (c) Actinide and Fission Product Transport, (d) Radiation Damage and Properties; (2) TRU (transuranic elements) TRISO (tri-structural isotropic) Development - (a) TRU Kernel Development, (b) Coating Development; (3) Advanced TRISO Applications - Metal Matrix Fuels for LWR; (4) LWR Fully Ceramic Fuel - (a) FCM Fabrication Development, (b) FCM Irradiation Testing; (5) Fuel Performance and Analytical Analysis - Fuel Performance Modeling; and (6) ZrC Properties and Handbook - Properties of ZrC.

  5. Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, October--December 1977

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M. J.; Ader, M.; Barletta, R. E.

    1978-01-01

    Fuel cycle studies reported for this period include studies of advanced solvent extraction techniques focussed on the development of centrifugal contactors for use in Purex processes. Miniature single-stage and eight-stage centrifugal contactors are being employed in performance studies applicable to larger units. In other work, literature on the dispersion of reagents as a result of explosions is being reviewed to develop systematic data applicable to fuel reprocessing and useful in identifying source terms. In yet other work, scouting studies were performed to obtain criteria for identifying organic solutions suitable for the separation of actinides from fission products. A program has been initiated on pyrochemical and dry processing of nuclear fuel. Literature reviews have been initiated on material development, carbide fuel reprocessing, and thorium-uranium reprocessing in fused salts. A review and evaluation of the encapsulation of high-level waste in a metal matrix is under way. Corrosion and leach rates of simulated waste forms are being measured and a model has been proposed to describe the reaction between solidified high-level waste and metals. In other work, criteria for the handling of fuel assembly hulls are being developed on the basis of past work on the pyrophoricity of zirconium alloys and related criteria from several sources. Experimental work is underway to determine whether nuclear wastes can be safely confined in geologic formations. Information is being obtained on the migration of radionuclides in aqueous solution-rock systems. 17 figures, 27 tables.

  6. Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, Sharon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Patton, Bradley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-09-01

    The Mk-18A Target Material Recovery Program (MTMRP) was established in 2015 to preserve the unique materials, e.g. 244Pu, in 65 previously irradiated Mk-18A targets for future use. This program utilizes existing capabilities at SRS and Savannah River National Laboratory (SRNL) to process targets, recover materials from them, and to package the recovered materials for shipping to ORNL. It also utilizes existing capabilities at ORNL to receive and store the recovered materials, and to provide any additional processing of the recovered materials or residuals required to prepare them for future beneficial use. The MTMRP is presently preparing for the processing of these valuable targets which is expected to begin in ~2019. As part of the preparations for operations, this report documents the preliminary acceptance criteria for the plutonium and heavy curium materials to be recovered from the Mk-18A targets at SRNL for transport and storage at ORNL. These acceptance criteria were developed based on preliminary concepts developed for processing, transporting, and storing the recovered Mk-18A materials. They will need to be refined as these concepts are developed in more detail.

  7. Preliminary nuclear safety assessment of the NEPST (Topaz 2) space reactor program

    Science.gov (United States)

    Marshall, A. C.

    The United States (US) Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz 2 space nuclear power system. A preliminary nuclear safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safety assessment and future Topaz 2 activities. A review of the Russian flight safety program was conducted and documented. Our preliminary nuclear safety assessment included a number of deterministic analyses, such as the following: neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, an analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment to date, it appears that it will be possible to safely launch the Topaz 2 system in the US with a modification to preclude water flooded criticality. A full scale safety program is now underway.

  8. ROBOT3: a computer program to calculate the in-pile three-dimensional bowing of cylindrical fuel rods (AWBA Development Program)

    Energy Technology Data Exchange (ETDEWEB)

    Kovscek, S.E.; Martin, S.E.

    1982-10-01

    ROBOT3 is a FORTRAN computer program which is used in conjunction with the CYGRO5 computer program to calculate the time-dependent inelastic bowing of a fuel rod using an incremental finite element method. The fuel rod is modeled as a viscoelastic beam whose material properties are derived as perturbations of the CYGRO5 axisymmetric model. Fuel rod supports are modeled as displacement, force, or spring-type nodal boundary conditions. The program input is described and a sample problem is given.

  9. Impacts of the Weatherization Assistance Program in Fuel-Oil Heated Houses

    Energy Technology Data Exchange (ETDEWEB)

    Levins, W.P.

    1994-01-01

    In 1990, the U.S. Department of Energy (DOE) initiated a national evaluation of its low-income Weatherization Assistance Program. This report, which is one of five parts of that evaluation, evaluates the energy savings and cost-effectiveness of the Program as it had been applied to single-family houses heated primarily by fuel-oil. The study was based upon a representative sample (41 local weatherization agencies, 222 weatherized and 115 control houses) from the nine northeastern states during 1991 and 1992 program years. Dwelling-specific and agency-level data on measures installed, costs, and service delivery procedures were collected from the sampled agencies. Space-heating fuel-oil consumption, indoor temperature, and outdoor temperature were monitored at each house. Dwelling characteristics, air-leakage measurements, space-heating system steady-state efficiency measurements, safety inspections, and occupant questionnaires were also collected or performed at each monitored house. We estimate that the Program weatherized a total of 23,400 single-family fuel-oil heated houses in the nine northeastern states during program years 1991 and 1992. Annual fuel-oil savings were calculated using regression techniques to normalize the savings to standard weather conditions. For the northeast region, annual net fuel-oil savings averaged 160 gallons per house, or 17.7% of pre-weatherization consumption. Although indoor temperatures changed in individual houses following weatherization, there was no average change and no significant difference as compared to the control houses; thus, there was no overall indoor temperature takeback effect influencing fuel-oil savings. The weatherization work was performed cost effectively in these houses from the Program perspective, which included both installation costs and overhead and management costs but did not include non-energy benefits (such as employment and environmental). Total average costs were $1819 per house ($1192 for

  10. Effectiveness of Chronic Disease Self-management Program in Japan: preliminary report of a longitudinal study.

    Science.gov (United States)

    Yukawa, Keiko; Yamazaki, Yoshihiko; Yonekura, Yuki; Togari, Taisuke; Abbott, Fusae K; Homma, Mieko; Park, Minjeong; Kagawa, Yumi

    2010-12-01

    This is the preliminary report of a study to evaluate the effectiveness of the Chronic Disease Self-management Program in Japan by comparing changes in health outcomes at the baseline and 3-month and 6-month follow-ups. The program is a patient-centered educational program for the self-management of chronic conditions. The study's participants were recruited from among the attendees of the program workshops. During the study period (August 2006 to May 2007), 18 workshops were held and 128 attendees agreed to participate in the study. The health outcomes that were measured included health status, self-management behaviors, utilization of health services, self-efficacy, satisfaction with daily living, and clinical indicators. These indicators were further analyzed by disease type: diabetes, rheumatic disease, and cardiovascular disease/dyslipidemia. The findings indicated statistically significant positive changes in health distress, coping with symptoms, stretching exercises, communication with the physician, and satisfaction with daily living. The positive changes were especially remarkable among the groups with diabetes and rheumatic disease. These findings suggest that the Chronic Disease Self-management Program can be effective for Japanese people with chronic conditions.

  11. On-Off Minimum-Time Control With Limited Fuel Usage: Global Optima Via Linear Programming

    Energy Technology Data Exchange (ETDEWEB)

    DRIESSEN,BRIAN

    1999-09-01

    A method for finding a global optimum to the on-off minimum-time control problem with limited fuel usage is presented. Each control can take on only three possible values: maximum, zero, or minimum. The simplex method for linear systems naturally yields such a solution for the re-formulation presented herein because it always produces an extreme point solution to the linear program. Numerical examples for the benchmark linear flexible system are presented.

  12. Evaluation of computer programs used for structural analyses of impact response of spent fuel shipping casks

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, B A; Gwinn, K W

    1984-05-01

    This report presents the results of a study of impact analyses of a generic spent-fuel cask. The study compares the use and results of three different finite element computer codes. Seven different cask-like model analyses are considered. The models encompass both linear and nonlinear geometric and material behavior. On the basis of the analyses results, this report recommends what parameters are useful in the comparison of different structural finite element computer programs. 5 references, 36 figures, 11 tables.

  13. Manual of phosphoric acid fuel cell stack three-dimensional model and computer program

    Science.gov (United States)

    Lu, C. Y.; Alkasab, K. A.

    1984-01-01

    A detailed distributed mathematical model of phosphoric acid fuel cell stack have been developed, with the FORTRAN computer program, for analyzing the temperature distribution in the stack and the associated current density distribution on the cell plates. Energy, mass, and electrochemical analyses in the stack were combined to develop the model. Several reasonable assumptions were made to solve this mathematical model by means of the finite differences numerical method.

  14. Deployment of advanced MACSTOR dry spent fuel storage technology in Korea - A joint development program

    Energy Technology Data Exchange (ETDEWEB)

    Cobanoglu, M. M.; Pattantyus, P. [Atomic Energy Canada Limited, Ottawa (Canada); Song, M. J.; Lee, H. Y. [KHNP/NETEC, Daejeon (Korea, Republic of)

    2002-04-15

    KHNP/NETEC's (K/N) and Atomic Energy of Canada Limited (AECL) are undertaking to jointly develop a high capacity dry storage structure made of reinforced concrete that uses the MACSTOR storage module concept. This effort is based on AECL's experience and on the successful deployment of concrete canisters at Wolsong and on the deployment of air-cooled MACSTOR modules at the Gentilly 2 reactor in Canada. The proposed approach addresses the conditions specific to the Wolsong site: large yearly fuel throughput, space limitations and the need for an economical dry storage structure that can store lifetime spent fuel inventories expected from the four CANDU units. The selected configuration is a 4-row MACSTOR module with a capacity of 24,000 bundles stored in 400 baskets, each holding 60 spent fuel bundles. The module is thus termed MACSTOR/KN-400 and is expected to offer a repetitive storage density increase by a factor of approximately 3, compared to concrete canisters presently used. The four Wolsong units generate spent fuel bundles that, with the high capacity factors achieved, are in the order of 20,000 bundles or more per year. At all Korean nuclear facilities, space limitations dictate the need for storage structures having high storage density. Storage density increases have to be accomplished while maintaining safety parameters during the full term storage of nuclear fuel. During the early 1990's AECL has proceeded with the development of a 2-row MACSTOR storage module that offered a higher storage density and a more economical solution compared to the stand alone concrete canister used at Wolsong 1. These modules are in use at Gentilly since the mid 1990's and operate at a capacity of 200 baskets. The selection of a MACSTOR module with 4 rows of storage cylinders is the natural evolution of the already deployed configuration. It can be developed without additional thermal testing as the fuel is maintained within the existing licensing

  15. Information on the evolution of severe LWR fuel element damage obtained in the CORA program

    Science.gov (United States)

    Schanz, G.; Hagen, S.; Hofmann, P.; Schumacher, G.; Sepold, L.

    1992-06-01

    In the CORA program a series of out-of-pile experiments on LWR severe accidental situations is being performed, in which test bundles of LWR typical components and arrangements (PWR, BWR) are exposed to temperature transients up to about 2400°C under flowing steam. The individual features of the facility, the test conduct, and the evaluation will be presented. In the frame of the international cooperation in severe fuel damage (SFD) programs the CORA tests are contributing confirmatory and complementary informations to the results from the limited number of in-pile tests. The identification of basic phenomena of the fuel element destruction, observed as a function of temperature, is supported by separate-effects test results. Most important mechanisms are the steam oxidation of the Zircaloy cladding, which determines the temperature escalation, the chemical interaction between UO 2 fuel and cladding, which dominates fuel liquefaction, relocation and resulting blockage formation, as well as chemical interactions with Inconel spacer grids and absorber units ((Ag, In, Cd) alloy or B 4C), which are leading to extensive low-temperature melt formation around 1200°C. Interrelations between those basic phenomena, resulting for example in cladding deformation ("flowering") and the dramatic hydrogen formation in response to the fast cooling of a hot bundle by cold water ("quenching") are determining the evolution paths of fuel element destruction, which are to be identified. A further important task is the abstraction from mechanistic and microstructural details in order to get a rough classification of damage regimes (temperature and extent), a practicable analytical treatment of the materials behaviour, and a basis for decisions in accident mitigation and management procedures.

  16. Material specification and quality control program for ductile iron spent fuel casks

    Energy Technology Data Exchange (ETDEWEB)

    Rehmer, B.; Frenz, H.; Weidlich, S.; Kuehn, H.D.

    1995-12-31

    In the process of testing spent fuel casks, BAM is gaining a lot of relevant data regarding the quality level of Ductile Cast Iron (DCI). This paper discusses the basic parameters governing the material behavior of ferritic and ferritic-pearlitic DCI and reviews the development of cask quality over the last years. The effect of microstructure and sample size on the fracture toughness of DCI is discussed. The results of a test program show the prominent effect of pearlite content and graphite nodule structure in the mechanical and fracture toughness characteristics of DCI. This observation is important for quality assurance programs for shipping and storage casks of radioactive materials.

  17. Literature Review for the Baseline Knowledge Assessment of the Hydrogen, Fuel Cells, and Infrastructure Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    Truett, L.F.

    2003-12-10

    The purpose of the Hydrogen, Fuel Cells, and Infrastructure Technologies (HFCIT) Program Baseline Knowledge Assessment is to measure the current level of awareness and understanding of hydrogen and fuel cell technologies and the hydrogen economy. This information will be an asset to the HFCIT program in formulating an overall education plan. It will also provide a baseline for comparison with future knowledge and opinion surveys. To assess the current understanding and establish the baseline, the HFCIT program plans to conduct scientific surveys of four target audience groups--the general public, the educational community, governmental agencies, and potential large users. The purpose of the literature review is to examine the literature and summarize the results of surveys that have been conducted in the recent past concerning the existing knowledge and attitudes toward hydrogen. This literature review covers both scientific and, to a lesser extent, non-scientific polls. Seven primary data sources were reviewed, two of which were studies based in Europe. Studies involved both closed-end and open-end questions; surveys varied in length from three questions to multi-page interviews. Populations involved in the studies were primarily adults, although one study involved students. The number of participants ranged from 13 to over 16,000 per study. In addition to the primary surveys, additional related studies were mined for pertinent information. The primary conclusions of the surveys reviewed are that the public knows very little about hydrogen and fuel cell technologies but is generally accepting of the potential for hydrogen use. In general, respondents consider themselves as environmentally conscious. The public considers safety as the primary issue surrounding hydrogen as a fuel. Price, performance, and convenience are also considerations that will have major impacts on purchase decisions.

  18. Development of a program for the analysis on the free vibration of a fuel rod and its application

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Dong Seung; Yim, Jeong Sik [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-12-01

    Commercial Nuclear fuel burns more than 2 or three years in a core and it is essential that the fuels have a integrity without any failures during the burnup period. The factors that influence on the fuel integrity are classified as nuclear, mechanical, thermal and material factors and they are inter-related with complexity. Since the final integrity should be assured mechanically, the evaluation of the fuel rod mechanical integrity is important in a fuel design. The fuel rod for PWR is supported by spring of spacer grids to maintain its axial location and lateral space between fuel rods to get proper functions during the residence in a reactor. The long exposure duration makes the spring to be relax and loss the spring force that results in a fuel rod rattling which may cause fuel rod failure. The design criteria of the spring forces for various fuel vendors are similar each other but they are slightly different: require minimal spring force to prevent the spring from rattling at the end of life or the minimal gap between fuel rod and spring. However the spring force is relaxed due to the neutron irradiation and stress relaxation that suddenly decrease exponentially and the spring behave nonlinear by the initial spring deflection and the relaxation phenomenon. The objective of this study is to develop a finite element program to support the mechanical evaluation in view of the interaction between fuel rod and spacer spring. Here considering the spring behaviour as a function of burnup, the reaction forces of the springs are calculated by the finite element program, BEVIRA developed herein to aid the evaluation of the integrity of the fuel rod from fretting. A fuel rod is modelled as a beam to get natural frequencies and mode shapes supported by a rotational spring at each spacer spring. The results from the program are compared with previous data and those from ANSYS for the validation of the program and procedures. For the example calculation, the characteristics

  19. Assessment of Mexico's program to use ethanol as transportation fuel: impact of 6% ethanol-blended fuel on emissions of light-duty gasoline vehicles.

    Science.gov (United States)

    Schifter, Isaac; Díaz, Luis; Rodríguez, Rene; Salazar, Lucia

    2011-02-01

    Recently, the Mexican government launched a national program encouraging the blending of renewable fuels in engine fuel. To aid the assessment of the environmental consequences of this move, the effect of gasoline fuel additives, ethanol and methyl tert-butyl ether, on the tailpipe and the evaporative emissions of Mexico sold cars was investigated. Regulated exhaust and evaporative emissions, such as carbon monoxide, non-methane hydrocarbons, and nitrogen oxides, and 15 unregulated emissions were measured under various conditions on a set of 2005-2008 model light-duty vehicles selected based on sales statistics for the Mexico City metropolitan area provided by car manufacturers. The selected car brands are also frequent in Canada, the USA, and other parts of the world. This paper provides details and results of the experiment that are essential for evaluation of changes in the emission inventory, originating in the low-blend ethanol addition in light vehicle fuel.

  20. Preliminary assessment report for Redmond Army National Guard Facility, Installation 53120, Redmond, Washington. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Ketels, P.; Aggarwal, P.

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Washington Army National Guard (WAARNG) property in Redmond, Washington. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the Redmond ARNG property, Phase I of the Department of Defense Installation Restoration Program. The environmentally significant operations (ESOs) associated with the property are (1) supply/storage of hazardous materials, (2) weapons cleaning, (3) the underground storage tanks (USTs), and (4) the use of herbicides. These ESOs are no longer active because of the closure of OMS 10 activities in 1988.

  1. Euler Technology Assessment program for preliminary aircraft design employing SPLITFLOW code with Cartesian unstructured grid method

    Science.gov (United States)

    Finley, Dennis B.

    1995-01-01

    This report documents results from the Euler Technology Assessment program. The objective was to evaluate the efficacy of Euler computational fluid dynamics (CFD) codes for use in preliminary aircraft design. Both the accuracy of the predictions and the rapidity of calculations were to be assessed. This portion of the study was conducted by Lockheed Fort Worth Company, using a recently developed in-house Cartesian-grid code called SPLITFLOW. The Cartesian grid technique offers several advantages for this study, including ease of volume grid generation and reduced number of cells compared to other grid schemes. SPLITFLOW also includes grid adaptation of the volume grid during the solution convergence to resolve high-gradient flow regions. This proved beneficial in resolving the large vortical structures in the flow for several configurations examined in the present study. The SPLITFLOW code predictions of the configuration forces and moments are shown to be adequate for preliminary design analysis, including predictions of sideslip effects and the effects of geometry variations at low and high angles of attack. The time required to generate the results from initial surface definition is on the order of several hours, including grid generation, which is compatible with the needs of the design environment.

  2. Cancer Prevention Interdisciplinary Education Program at Purdue University: Overview and Preliminary Results

    Science.gov (United States)

    Teegarden, Dorothy; Lee, Ji-Yeon; Adedokun, Omolola; Childress, Amy; Parker, Loran Carleton; Burgess, Wilella; Nagel, Julie; Knapp, Deborah W.; Lelievre, Sophie; Agnew, Christopher R.; Shields, Cleveland; Leary, James; Adams, Robin; Jensen, Jakob D.

    2012-01-01

    Cancer prevention is a broad field that crosses many disciplines; therefore, educational efforts to enhance cancer prevention research focused on interdisciplinary approaches to the field are greatly needed. In order to hasten progress in cancer prevention research, the Cancer Prevention Internship Program (CPIP) at Purdue University was designed to develop and test an interdisciplinary curriculum for undergraduate and graduate students. The hypothesis was that course curriculum specific to introducing interdisciplinary concepts in cancer prevention would increase student interest in and ability to pursue advanced educational opportunities (e.g., graduate school, medical school). Preliminary results from the evaluation of the first year which included 10 undergraduate and 5 graduate students suggested that participation in CPIP is a positive professional development experience, leading to a significant increase in understanding of interdisciplinary research in cancer prevention. In its first year, the CPIP project has created a successful model for interdisciplinary education in cancer prevention research. PMID:21533583

  3. Effects of an aquatic exercise program on inhibitory control in children with ADHD: a preliminary study.

    Science.gov (United States)

    Chang, Yu-Kai; Hung, Chiao-Ling; Huang, Chung-Ju; Hatfield, Bradley D; Hung, Tsung-Min

    2014-05-01

    The purpose of this preliminary study was to examine whether an aquatic exercise intervention that involves both aerobic and coordinative exercises influences restraint inhibition in children with ADHD. Thirty participants were assigned to either an aquatic exercise or a wait-list control group. Participants were assessed by Go/Nogo Task and motor ability prior to and after an 8-week exercise intervention (twice per week, 90 min per session) or a control intervention. Significant improvements in accuracy associated with the Nogo stimulus and the coordination of motor skills were observed over time in the exercise group compared with the control group. Only main effects of group were found for reaction time and accuracy associated with the Go stimulus. These findings suggest that an exercise program that involves both quantitative and qualitative exercise characteristics facilitates the restraint inhibition component of behavioral inhibition in children with ADHD.

  4. Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions

    Science.gov (United States)

    Ott, L. J.; Robb, K. R.; Wang, D.

    2014-05-01

    Following the severe accidents at the Japanese Fukushima Daiichi Nuclear Power Station in 2011, the US Department of Energy initiated research and development on the enhancement of the accident tolerance of light water reactors by the development of fuels/cladding that, in comparison with the standard UO2/Zircaloy (Zr) system, can tolerate loss of active cooling in the core for a considerably longer time period while maintaining or improving the fuel performance during normal operations. Analyses are presented that illustrate the impact of these new candidate fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions.

  5. Development of Education Program Applying Internal Combustion Engine with Bioethanol as Fuel

    Science.gov (United States)

    Utsumi, Noah; Yoshida, Masashi; Inada, Yuji

    One of the ways to mitigate global warming is to reduce carbon dioxide emissions. In Japan, carbon dioxide emissions from vehicles, which run on fossil fuels, account for about 1/4 of the total carbon dioxide emissions. In this study, we applied a commercial engine, and remodeled the engine which could work using bioethanol as a fuel. We subsequently examined the influence of exhaust emission of the engine with the bioethanol and documented the entire study as teaching materials, including the remodeling method. Next, we began our mechanical engineering courses at the university by using the teaching materials in this study as introductory education, with the aim of stimulating the interest of the students. We then developed an education program for the students.

  6. Fuel performance improvement program. Quarterly/annual progress report, October 1978-September 1979

    Energy Technology Data Exchange (ETDEWEB)

    Crouthamel, C.E. (comp.)

    1979-10-01

    The objective of the Fuel Performance Improvement Program is to develop, test, and demonstrate basically two advanced fuel designs with the capability for improved power ramping performance and thus increase the capability of achieving extended burnup levels to better utilize uranium resources. The irradiations are being supported by out-of-reactor experiments to evaluate the effect of graphite coatings to inhibit stress-corrosion-cracking type cladding failures that are related to pellet-cladding interaction. Instrumented test irradiations in the Halden Boiling Water Reactor (HBWR) have achieved peak burnups of 697 GJ/kgM (8.1 MWd/kgM) with reference, annular-coated-pressurized, and sphere-pac rods.

  7. Preliminary assessment report for Bee Caves Armory (former Nike BG-80 Fire Control Facility), Installation 48055, Austin, Texas. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Dennis, C.

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Texas Army National Guard (ARNG) property in Austin, Texas. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing, preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining, site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the Bee Caves Armory property, the requirements of the Department of Defense Installation Restoration Program. Of concern is the potential for hazardous waste to be present on the property as a result of the former Nike Missile Base operations or in the form of original construction materials. Environmentally sensitive operations associated with the property from that period include (1) underground fuel storage, (2) hazardous materials storage/use, (3) disposal of hazardous waste and (4) release of hazardous waste water.

  8. Liquefied gaseous fuels safety and environmental control assessment program: third status report

    Energy Technology Data Exchange (ETDEWEB)

    1982-03-01

    This Status Report contains contributions from all contractors currently participating in the DOE Liquefied Gaseous Fuels (LG) Safety and Environmental Control Assessment Program and is presented in two principal sections. Section I is an Executive Summary of work done by all program participants. Section II is a presentation of fourteen individual reports (A through N) on specific LGF Program activities. The emphasis of Section II is on research conducted by Lawrence Livermore National Laboratory (Reports A through M). Report N, an annotated bibliography of literature related to LNG safety and environmental control, was prepared by Pacific Northwest Laboratory (PNL) as part of its LGF Safety Studies Project. Other organizations who contributed to this Status Report are Aerojet Energy Conversion Company; Applied Technology Corporation; Arthur D. Little, Incorporated; C/sub v/ International, Incorporated; Institute of Gas Technology; and Massachusetts Institute of Technology. Separate abstracts have been prepared for Reports A through N for inclusion in the Energy Data Base.

  9. Experimental plan for the fuel-oil study. Weatherization Assistance Program: Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Ternes, M.P.; Levins, W.P.; Brown, M.A.

    1992-01-01

    An up-to-date assessment of the Weatherization Assistance Program (WAP) is being performed by the US Department of Energy WAP Division and the Oak Ridge National Laboratory. Five studies form the evaluation. Major goals of the Fuel-Oil Study are to estimate the fuel oil saved by the WAP in the Northeast during the 1990 and 1991 program years, identify and quantify non-energy impacts of the WAP, assess the cost effectiveness of the WAP within this submarket, and assess factors which may cause savings and cost effectiveness to vary. The study will only analyze single-family houses in the nine states in the Northeast census region and will be carried out over two heating seasons (1990 and 1991 WAP program years). A split-winter, pre- and post-weatherization experimental design with a control group will be used. Houses will be monitored over one winter. Energy conservation measures will be installed in the weatherized houses in January of each winter by the local WAP subgrantee. One hundred twenty five weatherized houses and 75 control houses will be monitored over the 1990--1991 winter; a different set of 200 houses will be monitored over the 1991--1992 winter. The houses will be evenly distributed among 25 subgrantees. Space-heating fuel-oil consumption, indoor temperature, and outdoor temperature data will be collected for all houses. Fuel-oil delivery data will be collected for each house monitored over the 1990--1991 winter for at least a year before weatherization. The delivery data will be analyzed to determine if the accuracy of the study can be improved by collecting fuel-oil delivery data on a larger sample of houses over the 1991--1992 winter. Detailed survey information will be obtained on all the houses. This information includes descriptive details of the house and its mechanical systems, details on household size and other demographics, and occupant answers to questions regarding comfort, safety, and operation of their space-heating system and house.

  10. Development of Methodology for Spent Fuel Pool Severe Accident Analysis Using MELCOR Program

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won-Tae; Shin, Jae-Uk [RETech. Co. LTD., Yongin (Korea, Republic of); Ahn, Kwang-Il [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    The general reason why SFP severe accident analysis has to be considered is that there is a potential great risk due to the huge number of fuel assemblies and no containment in a SFP building. In most cases, the SFP building is vulnerable to external damage or attack. In contrary, low decay heat of fuel assemblies may make the accident processes slow compared to the accident in reactor core because of a great deal of water. In short, its severity of consequence cannot exclude the consideration of SFP risk management. The U.S. Nuclear Regulatory Commission has performed the consequence studies of postulated spent fuel pool accident. The Fukushima-Daiichi accident has accelerated the needs for the consequence studies of postulated spent fuel pool accidents, causing the nuclear industry and regulatory bodies to reexamine several assumptions concerning beyond-design basis events such as a station blackout. The tsunami brought about the loss of coolant accident, leading to the explosion of hydrogen in the SFP building. Analyses of SFP accident processes in the case of a loss of coolant with no heat removal have studied. Few studies however have focused on a long term process of SFP severe accident under no mitigation action such as a water makeup to SFP. USNRC and OECD have co-worked to examine the behavior of PWR fuel assemblies under severe accident conditions in a spent fuel rack. In support of the investigation, several new features of MELCOR model have been added to simulate both BWR fuel assembly and PWR 17 x 17 assembly in a spent fuel pool rack undergoing severe accident conditions. The purpose of the study in this paper is to develop a methodology of the long-term analysis for the plant level SFP severe accident by using the new-featured MELCOR program in the OPR-1000 Nuclear Power Plant. The study is to investigate the ability of MELCOR in predicting an entire process of SFP severe accident phenomena including the molten corium and concrete reaction. The

  11. Chemical reactivity testing for the National Spent Nuclear Fuel Program. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Koester, L.W.

    2000-02-08

    This quality assurance project plan (QAPjP) summarizes requirements used by Lockheed Martin Energy Systems, Incorporated (LMES) Development Division at Y-12 for conducting chemical reactivity testing of Department of Energy (DOE) owned spent nuclear fuel, sponsored by the National Spent Nuclear Fuel Program (NSNFP). The requirements are based on the NSNFP Statement of work PRO-007 (Statement of Work for Laboratory Determination of Uranium Hydride Oxidation Reaction Kinetics.) This QAPjP will utilize the quality assurance program at Y-12, Y60-101PD, Quality Program Description, and existing implementing procedures for the most part in meeting the NSNFP Statement of Work PRO-007 requirements, exceptions will be noted. The project consists of conducting three separate series of related experiments, ''Passivation of Uranium Hydride Powder With Oxygen and Water'', '''Passivation of Uranium Hydride Powder with Surface Characterization'', and ''Electrochemical Measure of Uranium Hydride Corrosion Rate''.

  12. A Preliminary Study: Do Alternative Certification Route Programs Develop the Necessary Skills and Knowledge in Assistive Technology?

    Science.gov (United States)

    Bell, Sherry Mee; Cihak, David F.; Judge, Sharon

    2010-01-01

    A large number of special education teachers in the United States are prepared in alternative certification programs and insufficient empirical information exists regarding their knowledge of assistive technology. The purpose of this study was to conduct a preliminary investigation of alternatively licensed special education teachers' knowledge,…

  13. 76 FR 148 - Medicaid Program; Final FY 2009 and Preliminary FY 2011 Disproportionate Share Hospital...

    Science.gov (United States)

    2011-01-03

    ... and Preliminary FY 2011 Disproportionate Share Hospital Allotments, and Final FY 2009 and Preliminary FY 2011 Institutions for Mental Diseases Disproportionate Share Hospital Limits AGENCY: Centers for... share disproportionate share hospital (DSH) allotments for Federal FY (FY) 2009 and the preliminary...

  14. Twelfth symposium on biotechnology for fuels and chemicals: Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Scheitlin, F.M. (ed.)

    1990-01-01

    This report is the program and abstracts of the twelfth symposium on biotechnology for fuels and chemicals, held on May 7--11, 1990, at Gatlinburg, Tennessee. The symposium, sponsored by the Department of Energy, Oak Ridge National Laboratory, Solar Energy Research Institute, Badger Engineers, Inc., Gas Research Institute, and American Chemical Society, consists of five sessions: Session 1, thermal, chemical, and biological processing; Session 2 and 3, applied biological research; Session 4, bioengineering research; and Session 5, biotechnology, bioengineering, and the solution of environmental problems. It also consists of a poster session of the same five subject categories.

  15. Thirteenth annual report of the Technical Advisory Committee on the Nuclear Fuel Waste Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-15

    This report details activities since the last reporting period by the Technical Advisory Committee (TAC). The emphasis of the work in the Canadian Nuclear Fuel Waste Management Program (CNFWMP) has been on the writing of the Environmental Impact Statement (EIS) and the associated set of the primary reference document as well as supporting documents. These are in preparation for submission to the Environmental Assessment Review Panel who will lead the national evaluation of the disposal concept under the auspices of the Federal Environmental Assessment Review Office (FEARO).

  16. Manual of phosphoric acid fuel cell power plant optimization model and computer program

    Science.gov (United States)

    Lu, C. Y.; Alkasab, K. A.

    1984-01-01

    An optimized cost and performance model for a phosphoric acid fuel cell power plant system was derived and developed into a modular FORTRAN computer code. Cost, energy, mass, and electrochemical analyses were combined to develop a mathematical model for optimizing the steam to methane ratio in the reformer, hydrogen utilization in the PAFC plates per stack. The nonlinear programming code, COMPUTE, was used to solve this model, in which the method of mixed penalty function combined with Hooke and Jeeves pattern search was chosen to evaluate this specific optimization problem.

  17. Development of a Computer Program for the Integrated Control of the Fuel Homogeneity Measurement System

    Energy Technology Data Exchange (ETDEWEB)

    Shin, H. S.; Jang, J. W.; Lee, Y. H.; Oh, S. J.; Park, H. D.; Kim, C. K

    2005-11-15

    The computer program is developed based on Visual C++, which is equipped with a user-friendly interface of the input/output(I/O) and a display function for the measuring conditions. This program consists of three parts which are the port communication, PLC(Programmable Logic Controller) and the MCA(Multi Channel Analyzer) control parts. The communication type between the CPU of the PLC module box and the computer is selected as be the Rs-232 asynchronous type and the thread method is adapted in the development of the first part of the program. The PLC-related program has been developed so that the data communication between the PLC CPU and the computer could be harmonized with the unique commands which have already been defined in the PLC. The measuring space and time intervals, the start and end ROI(region of interest) values, and the allowable error limitation are input at each measurement in this program. Finally the controlling MCA program has been developed by using Canberra's programming library which contains several files including the head files in which the variable and the function of C++ are declared according to the MCA function. The performance test has been carried out through an application of the developed computer program to the homogeneity measurement system. The gamma counts at 28 measuring points of a fuel rod of 700 mm in length are measured for 50 sec at each point. It was revealed that the measurement results are better than the previous ones in respects of the measurement accuracy and a measurement time saving could be achieved. It was concluded that the gamma measurement system can be improved through equipping it with the developed control program.

  18. U.S. Department of Energy Hydrogen and Fuel Cells Program 2011 Annual Merit Review and Peer Evaluation Report

    Energy Technology Data Exchange (ETDEWEB)

    Satypal, S.

    2011-09-01

    This document summarizes the comments provided by peer reviewers on hydrogen and fuel cell projects presented at the FY 2011 U.S. Department of Energy (DOE) Hydrogen Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting (AMR), held May 9-13, 2011 in Arlington, Virginia

  19. Pathways to Commercial Success: Technologies and Products Supported by the Hydrogen, Fuel Cells and Infrastructure Technologies Program

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2009-08-01

    This report documents the results of an effort to identify and characterize commercial and near-commercial (emerging) technologies and products that benefited from the support of the Hydrogen, Fuel Cells and Infrastructure Technologies Program and its predecessor programs within DOE's Office of Energy Efficiency and Renewable Energy.

  20. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix C, Savannah River Site Spent Nuclear Fuel Mangement Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  1. Updated NGNP Fuel Acquisition Strategy

    Energy Technology Data Exchange (ETDEWEB)

    David Petti; Tim Abram; Richard Hobbins; Jim Kendall

    2010-12-01

    A Next Generation Nuclear Plant (NGNP) fuel acquisition strategy was first established in 2007. In that report, a detailed technical assessment of potential fuel vendors for the first core of NGNP was conducted by an independent group of international experts based on input from the three major reactor vendor teams. Part of the assessment included an evaluation of the credibility of each option, along with a cost and schedule to implement each strategy compared with the schedule and throughput needs of the NGNP project. While credible options were identified based on the conditions in place at the time, many changes in the assumptions underlying the strategy and in externalities that have occurred in the interim requiring that the options be re-evaluated. This document presents an update to that strategy based on current capabilities for fuel fabrication as well as fuel performance and qualification testing worldwide. In light of the recent Pebble Bed Modular Reactor (PBMR) project closure, the Advanced Gas Reactor (AGR) fuel development and qualification program needs to support both pebble and prismatic options under the NGNP project. A number of assumptions were established that formed a context for the evaluation. Of these, the most important are: • Based on logistics associated with the on-going engineering design activities, vendor teams would start preliminary design in October 2012 and complete in May 2014. A decision on reactor type will be made following preliminary design, with the decision process assumed to be completed in January 2015. Thus, no fuel decision (pebble or prismatic) will be made in the near term. • Activities necessary for both pebble and prismatic fuel qualification will be conducted in parallel until a fuel form selection is made. As such, process development, fuel fabrication, irradiation, and testing for pebble and prismatic options should not negatively influence each other during the period prior to a decision on reactor type

  2. Gas-Cooled Reactor Programs annual progress report for period ending December 31, 1973. [HTGR fuel reprocessing, fuel fabrication, fuel irradiation, core materials, and fission product distribution; GCFR fuel irradiation and steam generator modeling

    Energy Technology Data Exchange (ETDEWEB)

    Kasten, P.R.; Coobs, J.H.; Lotts, A.L.

    1976-04-01

    Progress is summarized in studies relating to HTGR fuel reprocessing, refabrication, and recycle; HTGR fuel materials development and performance testing; HTGR PCRV development; HTGR materials investigations; HTGR fuel chemistry; HTGR safety studies; and GCFR irradiation experiments and steam generator modeling.

  3. The Advanced Petroleum-Based Fuels Program DECSE and APBF Overview

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-04-11

    The following topics are summarized: Role of fuel blends in controlling engine-out emissions; Effect of fuels and lubricants on emission control devices; and Effect of fuels and lubricants on vehicle emissions and operations.

  4. Breeding performance of carbide and nitride fuels in 2000 MWe LMFBRs: a preliminary report. Part I. Assumptions, constraints and methodology

    Energy Technology Data Exchange (ETDEWEB)

    Barthold, W P

    1976-09-01

    The assumptions, constraints, and methodology used in the design and analysis of 2000 MWe LMFBRs using carbide and nitride fuel are presented. The assumptions used in the nuclear, thermal and mechanical designs are discussed together with geometry constraints, operational constraints, performance constraints, constraints coming from fabrication consideration and fuel bundle-duct interaction constraints. The basic calculational flow for system design studies is described, and the computer codes used in the analyses are briefly reviewed.

  5. Program for in-pile qualification of high density silicide dispersion fuel at IPEN/CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Jose E.R. da; Silva, Antonio T. e; Terremoto, Luis A.A.; Durazzo, Michelangelo [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: jersilva@ipen.br

    2009-07-01

    The development of high density nuclear fuel (U{sub 3}Si{sub 2}-Al) with 4,8 gU/cm{sup 3} is on going at IPEN, at this time. This fuel has been considered to be utilized at the new Brazilian Multipurpose Reactor (RMB), planned to be constructed up to 2014. As Brazil does not have hot-cell facilities available for post-irradiation analysis, an alternative qualifying program for this fuel is proposed based on the same procedures used at IPEN since 1988 for qualifying its own U{sub 3}O{sub 8}-Al (1,9 and 2,3 gU/cm{sup 3}) and U{sub 3}Si{sub 2}-Al (3,0 gU/cm{sup 3}) dispersion fuels. The fuel miniplates and full-size fuel elements irradiations should be tested at IEA-R1 core. The fuel characterization along the irradiation time should be made by means of non-destructive methods, including periodical visual inspections with an underwater video camera system, sipping tests for fuel elements suspected of leakage, and underwater dimensional measurements for swelling evaluation, performed inside the reactor pool. This work presents the program description for the qualification of the high density nuclear fuel (U{sub 3}Si{sub 2}-Al) with 4,8 gU/cm{sup 3}, and describes the IPEN fuel fabrication infrastructure and some basic features of the available systems for non-destructive tests at IEA-R1 research reactor. (author)

  6. Preliminary study : optimization of pH and salinity for biosurfactant production from Pseudomonas aeruginosa in diesel fuel and crude oil medium

    Science.gov (United States)

    Ikhwani, A. Z. N.; Nurlaila, H. S.; Ferdinand, F. D. K.; Fachria, R.; Hasan, A. E. Z.; Yani, M.; Setyawati, I.; Suryani

    2017-03-01

    Biosurfactant is secondary metabolite surface active compound produced by microorganisms which is nontoxic and eco-friendly. Microorganism producing biosurfactant that is quite potential to use in many applications is from Pseudomonas aeruginosa strains. Good quality of biosurfactant production from microbes is supported by the suitable nutrients and environmental factors. The aim of this research was to obtain preliminary o data upon the optimum pH and salinity for the production of biosurfactant from Pseudomonas aeruginosa ATCC 15442 in diesel fuel and crude oil medium. P. aeruginosa ATCC 15442 cultured in diesel fuel and crude oil as carbon source showed biosurfactant activity. P.aeruginosa-derived biosurfactant was capable to form stable emulsion for 24 hours (EI24) in hydrocarbons n-hexane solutions. The particular biosurfactant showed EI24 highest value at pH 7 (31.02%) and 1% NaCl (24.00%) when P. aeruginosa was grown in 10% diesel fuel medium in mineral salt solution. As for the media crude oil, the highest EI24 value was at pH 6 (52.16%) and 1% NaCl (33.30%).

  7. Liquefied Gaseous Fuels Safety and Environmental Control Assessment Program: second status report

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    The Assistant Secretary for Environment has responsibility for identifying, characterizing, and ameliorating the environmental, health, and safety issues and public concerns associated with commercial operation of specific energy systems. The need for developing a safety and environmental control assessment for liquefied gaseous fuels was identified by the Environmental and Safety Engineering Division as a result of discussions with various governmental, industry, and academic persons having expertise with respect to the particular materials involved: liquefied natural gas, liquefied petroleum gas, hydrogen, and anhydrous ammonia. This document is arranged in three volumes and reports on progress in the Liquefied Gaseous Fuels (LGF) Safety and Environmental Control Assessment Program made in Fiscal Year (FY)-1979 and early FY-1980. Volume 1 (Executive Summary) describes the background, purpose and organization of the LGF Program and contains summaries of the 25 reports presented in Volumes 2 and 3. Annotated bibliographies on Liquefied Natural Gas (LNG) Safety and Environmental Control Research and on Fire Safety and Hazards of Liquefied Petroleum Gas (LPG) are included in Volume 1.

  8. Fuzzy linear programming based optimal fuel scheduling incorporating blending/transloading facilities

    Energy Technology Data Exchange (ETDEWEB)

    Djukanovic, M.; Babic, B.; Milosevic, B. [Electrical Engineering Inst. Nikola Tesla, Belgrade (Yugoslavia); Sobajic, D.J. [EPRI, Palo Alto, CA (United States). Power System Control; Pao, Y.H. [Case Western Reserve Univ., Cleveland, OH (United States)]|[AI WARE, Inc., Cleveland, OH (United States)

    1996-05-01

    In this paper the blending/transloading facilities are modeled using an interactive fuzzy linear programming (FLP), in order to allow the decision-maker to solve the problem of uncertainty of input information within the fuel scheduling optimization. An interactive decision-making process is formulated in which decision-maker can learn to recognize good solutions by considering all possibilities of fuzziness. The application of the fuzzy formulation is accompanied by a careful examination of the definition of fuzziness, appropriateness of the membership function and interpretation of results. The proposed concept provides a decision support system with integration-oriented features, whereby the decision-maker can learn to recognize the relative importance of factors in the specific domain of optimal fuel scheduling (OFS) problem. The formulation of a fuzzy linear programming problem to obtain a reasonable nonfuzzy solution under consideration of the ambiguity of parameters, represented by fuzzy numbers, is introduced. An additional advantage of the FLP formulation is its ability to deal with multi-objective problems.

  9. The OSU Hydro-Mechanical Fuel Test Facility: Standard Fuel Element Testing

    Energy Technology Data Exchange (ETDEWEB)

    Wade R. Marcum; Brian G. Woods; Ann Marie Phillips; Richard G. Ambrosek; James D. Wiest; Daniel M. Wachs

    2001-10-01

    Oregon State University (OSU) and the Idaho National Laboratory (INL) are currently collaborating on a test program which entails hydro-mechanical testing of a generic plate type fuel element, or standard fuel element (SFE), for the purpose of qualitatively demonstrating mechanical integrity of uranium-molybdenum monolithic plates as compared to that of uranium aluminum dispersion, and aluminum fuel plates due to hydraulic forces. This test program supports ongoing work conducted for/by the fuel development program and will take place at OSU in the Hydro-Mechanical Fuel Test Facility (HMFTF). Discussion of a preliminary test matrix, SFE design, measurement and instrumentation techniques, and facility description are detailed in this paper.

  10. Reaching mothers in Swaziland: preliminary findings of a child survival program.

    Science.gov (United States)

    Hornik, R; Sankar, P

    1985-01-01

    The Swaziland Diarrheal Disease Control campaign, a collaboration of the Ministry of Health of Swaziland, the Combatting Childhood Communicable Diseases project, and the Agency for International Development (AID) Communication for Child Survival (HEALTHCOM) Project, was based on earlier work in Swaziland as well as the previous health communications programs in Honduras and Gambia. As in the other programs, it relied on a combination of mass media and face-to-face channels in an effort to change practices related to the treatment of diarrheal disease. The preparatory phase of the campaign was initiated in April 1984; the formal campaign ran from September 1984 through March 1985. The campaign involved 3 components: radio programs to be developed in an intensive radio workshop and broadcast on current development programs carried on the national radio system; printed materials including a flyer with mixing instructions and posters for display at health clinics and elsewhere; and workshops to train the health staff, other extension personnel, and local volunteers in treatment of diarrheal diseases, including use of oral rehydration therapy (ORT) for dehydration. The campaign focused on a few objectives, specifically: acceptance of a home-mixed water/sugar/salt (WSS) solution as a treatment for diarrheal dehydration; continued feeding during episodes of diarrhea; and feeding with special foods after diarrheal episodes. The campaign particularly emphasized the introduction of a new formula for mixing the solution -- 1 liter of water, 8 soda bottlecapfuls of sugar, and 1/2 capful of salt. The evaluation reveals preliminary results suggesting that the campaign achieved noteworthy success, particularly in rates of adoption of recommended practices. Data sources included before and after campaign surveys, each with 450 rural mothers chosen through national random sampling procedures, and a diarrheal disease registry kept by 20 clinics which listed more than 10,000 children

  11. ASBLT: a system of DATATRAN MODULES which process core fuel loading for use in as-built calculations (LWBR Development Program)

    Energy Technology Data Exchange (ETDEWEB)

    Beaudoin, B.R.; Beggs, W.J.; Case, C.R.; Wilczynski, R.

    1979-02-01

    ASBLT is a computer program consisting of DATATRAN MODULES which was used during the manufacturing phase of LWBR to collect and evaluate as-built data. The program was part of the LWBR fuel rod inspection process and produced sections of module assembly certification reports. ASBLT used fuel pellet, fuel rod and module assembly data to compute core inventories and to supply input to nuclear design programs for as-built core calculations.

  12. Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input

    Science.gov (United States)

    Meriyanti, Su'ud, Zaki; Rijal, K.; Zuhair, Ferhat, A.; Sekimoto, H.

    2010-06-01

    In this study a fesibility design study of medium sized (1000 MWt) gas cooled fast reactors which can utilize natural uranium as fuel cycle input has been conducted. Gas Cooled Fast Reactor (GFR) is among six types of Generation IV Nuclear Power Plants. GFR with its hard neuron spectrum is superior for closed fuel cycle, and its ability to be operated in high temperature (850° C) makes various options of utilizations become possible. To obtain the capability of consuming natural uranium as fuel cycle input, modified CANDLE burn-up scheme[1-6] is adopted this GFR system by dividing the core into 10 parts of equal volume axially. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 70 W/cc. As an optimization results, a design of 1000 MWt reactors which can be operated 10 years without refueling and fuel shuffling and just need natural uranium as fuel cycle input is discussed. The average discharge burn-up is about 280 GWd/ton HM. Enough margin for criticallity was obtained for this reactor.

  13. Facial emotional recognition in schizophrenia: preliminary results of the virtual reality program for facial emotional recognition

    Directory of Open Access Journals (Sweden)

    Teresa Souto

    2013-01-01

    Full Text Available BACKGROUND: Significant deficits in emotional recognition and social perception characterize patients with schizophrenia and have direct negative impact both in inter-personal relationships and in social functioning. Virtual reality, as a methodological resource, might have a high potential for assessment and training skills in people suffering from mental illness. OBJECTIVES: To present preliminary results of a facial emotional recognition assessment designed for patients with schizophrenia, using 3D avatars and virtual reality. METHODS: Presentation of 3D avatars which reproduce images developed with the FaceGen® software and integrated in a three-dimensional virtual environment. Each avatar was presented to a group of 12 patients with schizophrenia and a reference group of 12 subjects without psychiatric pathology. RESULTS: The results show that the facial emotions of happiness and anger are better recognized by both groups and that the major difficulties arise in fear and disgust recognition. Frontal alpha electroencephalography variations were found during the presentation of anger and disgust stimuli among patients with schizophrenia. DISCUSSION: The developed program evaluation module can be of surplus value both for patient and therapist, providing the task execution in a non anxiogenic environment, however similar to the actual experience.

  14. Examining the Preliminary Efficacy of a Dating Violence Prevention Program for Hispanic Adolescents

    Science.gov (United States)

    Gonzalez-Guarda, Rosa Maria; Guerra, Jessica E.; Cummings, Amanda A.; Pino, Karen; Becerra, Maria M.

    2017-01-01

    The purpose of this study is to evaluate the preliminary efficacy of a dating violence (DV) prevention program for Cuban American adolescents (JOVEN/YOUTH: Juntos Opuestos a la Violence Entre Novios/Together Against Dating Violence). A randomized-controlled experimental design with a delayed condition was used to evaluate the effects on DV victimization and perpetration (N = 82). Self-administrated assessments were completed at baseline, 1 week, 3 months, and 12 months after the intervention to assess for psychological victimization and perpetration and physical and sexual victimization and perpetration. Effect sizes were estimated, and generalized estimating equations were generated to test intervention effects over time and potential gender interactions. The intervention had medium to strong effects on DV victimization and perpetration for male participants but not for females. However, intervention effects were not statistically significant over time. More research is needed to enhance intervention effects of JOVEN on DV outcomes and to evaluate these effects among a larger and more diverse sample. PMID:26260135

  15. An 8-week reactive balance training program in older healthy adults:A preliminary investigation

    Institute of Scientific and Technical Information of China (English)

    Max R. Paquette; Yuhua Li; Joseph Hoekstra; Joshua Bravo

    2015-01-01

    Background:This preliminary study examined the effects of an 8-week supervised reactive balance training program on reaction time (RT) and foot speed, static balance and balance confidence in healthy older adults compared to an exercise control group. Methods:Twenty-five older adults were randomly assigned to a reactive balance training group (QuickBoard;n=12;71.0 ± 8.6 years) or a stationary cycling group (control; n = 13; 70.2 ± 6.0 years). Both groups were tested for foot RT foot speed, static balance, and balance confidence at baseline, 4-week, 8-week, and 4-week follow-up. Results: Results indicated significant improvements in QuickBoard foot RT and speed in both groups with greater improvements in the QuickBoard group. However, no group difference was found in static balance performance. Conclusion: Although the improvements in RT and foot speed may be beneficial for fall and trip prevention, the implications of the current findings for trip avoidance and performance of daily tasks are unclear.

  16. Idaho Chemical Processing Plant spent fuel and waste management technology development program plan: 1994 Update

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Department of Energy has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until April 1992, the major activity of the ICPP was the reprocessing of SNF to recover fissile uranium and the management of the resulting high-level wastes (HLW). In 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the continued safe management and disposition of SNF and radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3,800 cubic meters of calcine waste, and 289 metric tons heavy metal of SNF are in inventory at the ICPP. Disposal of SNF and high-level waste (HLW) is planned for a repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP spent Fuel and Waste Management Technology Development Program (SF&WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will be properly stored and prepared for final disposal in accordance with regulatory drivers. This Plan presents a brief summary of each of the major elements of the SF&WMTDP; identifies key program assumptions and their bases; and outlines the key activities and decisions that must be completed to identify, develop, demonstrate, and implement a process(es) that will properly prepare the SNF and radioactive wastes stored at the ICPP for safe and efficient interim storage and final disposal.

  17. Preliminary Multirod Burst Test Program results and implications of interest to reactor safety evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, R.H. (comp.)

    1978-01-01

    The Multirod Burst Test (MRBT) Program, in progress at Oak Ridge National Laboratory, is investigating LWR cladding deformation in single- and multirod test arrays under conditions representative of reflood and refill phases of a LOCA. In these tests internally pressurized, unirradiated Zircaloy-4 tubes containing electrically heated fuel simulators are tested to failure in a low-pressure, superheated-steam environment. The tubes are ''uniformly'' heated over a 915-mm length; the simulator pressure, due to the small enclosed gas volume, also varies with temperature (and deformation) during the test. Two 4 x 4 multirod tests (B-1 and B-2), one with and one without the shroud being heated, have been conducted with a bundle heating rate of approx. 29/sup 0/C/sec; initial pressure conditions for these tests were selected to cause failure at about 860/sup 0/C. An additional 4 x 4 array (B-3) was tested using a bundle heating rate of approx. 10/sup 0/C/sec; the shroud was also heated in this test. Initial conditions were adjusted to cause failure at approx. 760/sup 0/C. Posttest examination (including flow tests) of the B-1 and B-2 test arrays, is essentially complete, and pertinent data are included in this summary.

  18. Preliminary Results From NASA's Space Solar Power Exploratory Research and Technology Program

    Science.gov (United States)

    Howell, Joe T.; Mankins, John C.

    2000-01-01

    Large solar power satellite (SPS) systems that might provide base load power into terrestrial markets were examined extensively in the 1970s by the US Department of Energy (DOE) and the National Aeronautics and Space Administration (NASA). Following a hiatus of about 15 years, the subject of space solar power (SSP) was reexamined by NASA from 1995-1997 in the "fresh look" study, and during 1998 in an SSP "concept definition study". As a result of these efforts, during 1999-2000, NASA has been conducting the SSP Exploratory Research and Technology (SERT) program. The goal of the SERT activity has been to conduct preliminary strategic technology research and development to enable large, multi-megawatt SSP systems and wireless power transmission (WPT) for government missions and commercial markets (in-space and terrestrial). In pursuing that goal, the SERT: (1) refined and modeled systems approaches for the utilization of SSP concepts and technologies, ranging from the near-term (e.g., for space science, exploration and commercial space applications) to the far-term (e.g., SSP for terrestrial markets), including systems concepts, architectures, technology, infrastructure (e.g. transportation), and economics; (2) conducted technology research, development and demonstration activities to produce "proof-of-concept" validation of critical SSP elements for both nearer and farther-term applications; and (3) engendered the beginnings of partnerships (nationally and internationally) that could be expanded, as appropriate, to pursue later SSP technology and applications. Through these efforts, the SERT should allow better informed future decisions regarding further SSP and related technology research and development investments by both NASA and prospective partners, and guide further definition of technology roadmaps - including performance objectives, resources and schedules, as well as "multi-purpose" applications (e.g., commerce, science, and government). This paper

  19. RAPID program to predict radial power and burnup distribution of UO{sub 2} fuel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chan Bock; Song, Jae Sung; Bang, Je Gun; Kim, Dae Ho [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    Due to the radial variation of the neutron flux and its energy spectrum inside UO{sub 2} fuel, the fission density and fissile isotope production rates are varied radially in the pellet, and it becomes necessary to know the accurate radial power and burnup variation to predict the high burnup fuel behavior such as rim effects. Therefore, to predict the radial distribution of power, burnup and fissionable nuclide densities in the pellet with the burnup and U-235 enrichment, RAPID(RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet) program was developed. It considers the specific radial variation of the neutron reaction of the nuclides while the constant radial variation of neutron reaction except neutron absorption of U-238 regardless of the nuclides, the burnup and U-235 enrichment is assumed in TUBRNP model which is recognized as the one of the most reliable models. Therefore, it is expected that RAPID may be more accurate than TUBRNP, specially at high burnup region. RAPID is based upon and validated by the detailed reactor physics code, HELIOS which is one of few codes that can calculates the radial variations of the nuclides inside the pellet. Comparison of RAPID prediction with the measured data of the irradiated fuels showed very good agreement. RAPID can be used to calculate the local variations of the fissionable nuclide concentrations as well as the local power and burnup inside that pellet as a function of the burnup up to 10 w/o U-235 enrichment and 150 MWD/kgU burnup under the LWR environment. (author). 8 refs., 50 figs., 1 tab.

  20. Consolidated Fuel-Reprocessing Program. Progress report, April 1 to June 30, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-08-01

    All research and development on fuel reprocessing in the United States is managed under the Consolidated Fuel Reprocessing Program. Technical progress is reported in overview fashion. Conceptual studies for the proposed Breeder Reprocessing Engineering Test (BRET) have continued. Studies to date have confirmed the feasibility of modifying an existing DOE facility at Hanford, Washington. A study to measure the extent of plutonium polymerization during steam-jet transfers of nitric acid solutions indicated polymer would appear only after several successive transfers at temperatures of 75/sup 0/C or higher. Fast-Flux Test Facility fuel was processed for the first time in the Solvent Extraction Test Facility. Studies of krypton release from pulverized sputter-deposited Ni-Y-Kr matrices have shown that the release rate is inversely proportional to the particle radius at 200/sup 0/C. Preparation of the initial 500-g batch of mixed oxide gel-spheres was completed. Fabrication processing at HEDL of mixed oxide gel-spheres (DIPRES process) was initiated. Operational testing of both 8 packs of the centrifugal contactor has been completed. Fabrication of both the prototypical disassembly system and the prototypical shear system has been initiated. Planning for FY 1984 installation and modification work in the integrated equipment list facility was completed. Acceptance tests of the original Integrated Process Demonstration system have been completed. Instrumentation and controls work with the prototype multiwavelength uranium photometer was successful and has been expanded to continuously and simultaneously monitor three process streams (raffinate, aqueous feed, and organic strip) in the secondary extraction cycle. Major efforts of the environmental, safeguards, and waste management areas were directed toward providing data for BRET.

  1. Chemical Engineering Division fuel cycle programs. Progress report, January--March 1978

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M.J.; Ader, M.; Barletta, R.E.

    1979-04-01

    Fuel cycle studies reported for this period include studies of advanced solvent extraction techniques focussed on the development of centrifugal contactors for use in Purex processes. Miniature single-stage and eight-stage centrifugal contactors are being employed in studies of contactor performance and the kinetics of extraction. A 9-cm-ID centrifugal contactor has been completed, and fabrication drawings are being prepared for a plant-scale contactor. In other work, tricaprylmethyl-ammonium nitrate and di-n-amyl n-amylphosphonate are being evaluated as extractants in the Thorex process. Literature on the dispersion of liquids by explosions is being reviewed. A process was developed for extracting TBP degradation products from TBP-Na/sub 2/CO/sub 3/ scrub solutions while the actinides remain with the raffinate. In the program on pyrochemical and dry processing of nuclear fuel, the literature is being reviewed for acceptable materials for containment vessels, decladding methods are being evaluated, salt transport processes are being studied, a candidate flow sheet (based upon the Dow Aluminum Pyrometallurgical process) for reprocessing spent uranium metal fuel was prepared, work was begun on the use of molten salts for reprocessing actinide oxides, and the reprocessing of (Th,U)O/sub 2/ solid solution in a KCl-LiCl salt containing ThCl/sub 4/ and thorium chips was studied. Work on the encapsulation of solidified radioactive waste in a metal matrix includes study of (1) chemical interactions between simulated waste forms and matrix metals, (2) the leach rates of simulated encapsulated waste forms, and (3) the corrosion of candidate matrix metals and canister materials in brine solutions.Work to establish criteria for the handling of waste cladding hulls is continuing. The transport properties of nuclear waste in geologic media are being studied to estimate leaching of radionuclides from deep repositories by groundwater.

  2. Low NO sub x heavy fuel combustor concept program. Phase 1A: Combustion technology generation coal gas fuels

    Science.gov (United States)

    Sherlock, T. P.

    1982-01-01

    Combustion tests of two scaled burners using actual coal gas from a 25 ton/day fluidized bed coal gasifier are described. The two combustor configurations studied were a ceramic lined, staged rich/lean burner and an integral, all metal multiannual swirl burner (MASB). The tests were conducted over a range of temperature and pressures representative of current industrial combustion turbine inlet conditions. Tests on the rich lean burner were conducted at three levels of product gas heating values: 104, 197 and 254 btu/scf. Corresponding levels of NOx emissions were 5, 20 and 70 ppmv. Nitrogen was added to the fuel in the form of ammonia, and conversion efficiencies of fuel nitrogen to NOx were on the order of 4 percent to 12 percent, which is somewhat lower than the 14 percent to 18 percent conversion efficiency when src-2 liquid fuel was used. The MASB was tested only on medium btu gas (220 to 270 btu/scf), and produced approximately 80 ppmv NOx at rated engine conditions. Both burners operated similarly on actual coal gas and erbs fuel, and all heating values tested can be successfully burned in current machines.

  3. Organic carbonyl compounds in Albuquerque, New Mexico, air: A preliminary study of the effects of oxygenated fuel use

    Energy Technology Data Exchange (ETDEWEB)

    Popp, C.J.; Zhang, Lin [New Mexico Inst. of Mining and Technology, Socorro, NM (United States). Dept. of Chemistry; Gaffney, J.S. [Argonne National Lab., IL (United States)

    1993-06-01

    A suite of inorganic and organic species were analyzed for four 2--4 day time periods over a year in Albuquerque, New Mexico to determine baseline conditions for organic pollutants under the current air pollution control parameters. Concentrations of low molecular weight carbonyl compounds were relatively high compared with areas such as Los Angeles. Formio acid concentrations in air samples were significant even in winter. In addition, ratios of peroxypropionyl nitrate to peroxyacyetyl nitrate are higher than expected and may be related to the use of oxygenated fuels which are used to mitigate CO concentrations. The number of CO violations in Albuquerque has decreased steadily since 1982 and the downward trend has continued since 1989 when oxygenated fuel use was mandated. It is, therefore, difficult to correlate the drop in CO violations directly to the use of oxygenated fuels when such factors as fleet turnover, woodburning controls, emissions testing and meteorological conditions also may be playing significant roles. More detailed studies are needed to determine the specific relationship between the use of oxygenated fuels and the air quality in Albuquerque, New Mexico and similar urban areas in the western United States.

  4. Uranium from Seawater Program Review; Fuel Resources Uranium from Seawater Program DOE Office of Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-07-01

    For nuclear energy to remain sustainable in the United States, economically viable sources of uranium beyond terrestrial ores must be developed. The goal of this program is to develop advanced adsorbents that can extract uranium from seawater at twice the capacity of the best adsorbent developed by researchers at the Japan Atomic Energy Agency (JAEA), 1.5 mg U/g adsorbent. A multidisciplinary team from Oak Ridge National Laboratory, Lawrence Berkeley National Laboratory, Pacific Northwest National Laboratory, and the University of Texas at Austin was assembled to address this challenging problem. Polymeric adsorbents, based on the radiation grafting of acrylonitrile and methacrylic acid onto high surface-area polyethylene fibers followed by conversion of the nitriles to amidoximes, have been developed. These poly(acrylamidoxime-co-methacrylic acid) fibers showed uranium adsorption capacities for the extraction of uranium from seawater that exceed 3 mg U/g adsorbent in testing at the Pacific Northwest National Laboratory Marine Sciences Laboratory. The essence of this novel technology lies in the unique high surface-area trunk material that considerably increases the grafting yield of functional groups without compromising its mechanical properties. This technology received an R&D100 Award in 2012. In addition, high surface area nanomaterial adsorbents are under development with the goal of increasing uranium adsorption capacity by taking advantage of the high surface areas and tunable porosity of carbon-based nanomaterials. Simultaneously, de novo structure-based computational design methods are being used to design more selective and stable ligands and the most promising candidates are being synthesized, tested and evaluated for incorporation onto a support matrix. Fundamental thermodynamic and kinetic studies are being carried out to improve the adsorption efficiency, the selectivity of uranium over other metals, and the stability of the adsorbents. Understanding

  5. Finite-element procedure for calculating the three-dimensional inelastic bowing of fuel rods (AWBA development program)

    Energy Technology Data Exchange (ETDEWEB)

    Martin, S E

    1982-05-01

    An incremental finite element procedure is developed for calculating the in-pile lateral bowing of nuclear fuel rods. The fuel rod is modeled as a viscoelastic beam whose material properties are derived as perturbations of the results of an axisymmetric stress analysis of the fuel rod. The effects which are taken into account in calculating the rod's lateral bowing include: (a) lateral, axial, and rotational motions and forces at the rod supports, (b) transverse gradients of temperature, fast-neutron flux, and fissioning rate, and (c) cladding circumferential wall thickness variation. The procedure developed in this report could be used to form the basis for a computer program to calculate the time-dependent bowing as a function of the fuel rod's operational and environmental history.

  6. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    Energy Technology Data Exchange (ETDEWEB)

    Ruokola, E. [ed.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  7. Bootstrapping a Sustainable North American PEM Fuel Cell Industry: Could a Federal Acquisition Program Make a Difference?

    Energy Technology Data Exchange (ETDEWEB)

    Greene, David L [ORNL; Duleep, Dr. K. G. [Energy and Environmental Analysis, Inc., an ICF Company

    2008-10-01

    The North American Proton Exchange Membrane (PEM) fuel cell industry may be at a critical juncture. A large-scale market for automotive fuel cells appears to be several years away and in any case will require a long-term, coordinated commitment by government and industry to insure the co-evolution of hydrogen infrastructure and fuel cell vehicles (Greene et al., 2008). The market for non-automotive PEM fuel cells, on the other hand, may be much closer to commercial viability (Stone, 2006). Cost targets are less demanding and manufacturers appear to be close, perhaps within a factor of two, of meeting them. Hydrogen supply is a significant obstacle to market acceptance but may not be as great a barrier as it is for hydrogen-powered vehicles due to the smaller quantities of hydrogen required. PEM fuel cells appear to be potentially competitive in two markets: (1) Backup power (BuP) supply, and (2) electrically-powered MHE (Mahadevan et al., 2007a, 2007b). There are several Original Equipment Manufacturers (OEMs) of PEM fuel cell systems for these applications but production levels have been quite low (on the order of 100-200 per year) and cumulative production experience is also limited (on the order of 1,000 units to date). As a consequence, costs remain above target levels and PEM fuel cell OEMs are not yet competitive in these markets. If cost targets can be reached and acceptable solutions to hydrogen supply found, a sustainable North American PEM fuel cell industry could be established. If not, the industry and its North American supply chain could disappear within a year or two. The Hydrogen Fuel Cell and Infrastructure Technologies (HFCIT) program of the U.S. Department of Energy (DOE) requested a rapid assessment of the potential for a government acquisition program to bootstrap the market for non-automotive PEM fuel cells by driving down costs via economies of scale and learning-by-doing. The six week study included in-depth interviews of three manufacturers

  8. Metallic fuel design development

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Woan; Kang, H. Y.; Lee, B. O. and others

    1999-04-01

    This report describes the R and D results of the ''Metallic Fuel Design Development'' project that performed as a part of 'Nuclear Research and Development Program' during the '97 - '98 project years. The objectives of this project are to perform the analysis of thermo-mechanical and irradiation behaviors, and preliminary conceptual design for the fuel system of the KALIMER liquid metal reactor. The following are the major results that obtained through the project. The preliminary design requirements and design criteria which are necessary in conceptual design stage, are set up. In the field of fuel pin design, the pin behavior analysis, failure probability prediction, and sensitivity analysis are performed under the operation conditions of steady-state and transient accidents. In the area of assembly duct analysis; 1) KAFACON-2D program is developed to calculate an array configuration of inner shape of assembly duct, 2) Stress-strain analysis are performed for the components of assembly such as, handling socket, mounting rail and wire wrap, 3) The BDI program is developed to analyze mechanical interaction between pin bundle and duct, 4) a vibration analysis is performed to understand flow-induced vibration of assembly duct, 5) The NUBOW-2D, which is bowing and deformation analysis code for assembly duct, is modified to be operated in KALIMER circumstance, and integrity evaluation of KALIMER core assembly is carried out using the modified NUBOW-2D and the CRAMP code in U.K., and 6) The KALIMER assembly duct is manufactured to be used in flow test. In the area of non-fuel assembly, such as control, reflector, shielding, GEM and USS, the states-of-the-arts and the major considerations in designing are evaluated, and the design concepts are derived. The preliminary design description and their design drawing of KALIMER fuel system are prepared based upon the above mentioned evaluation and analysis. The achievement of conceptual

  9. Implications of Results from the Advanced Gas Reactor Fuel Development and Qualification Program on Licensing of Modular HTGRs

    Energy Technology Data Exchange (ETDEWEB)

    David Petti

    2001-10-01

    The high level of safety of modular high temperature gas-cooled reactor (HTGR) designs is achieved by passively maintaining core temperatures below fission product release thresholds under all envisioned accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude relative to other reactor types but is predicated on exceptionally high coated-particle fuel fabrication quality and excellent fuel performance under normal operation and accident conditions. The Advanced Gas Reactor Fuel Development and Qualification (AGR) Program decided to qualify for uranium oxide/uranium carbide (UCO) TRISO coated-particle fuel in an operating envelope that would bound both pebble bed and prismatic modular HTGR options. By using a mixture of uranium oxide and uranium carbide, the kernel composition is engineered to minimize CO formation and fuel kernel migration, which is key to maintain to fuel integrity at the higher burnups, temperatures, and temperature gradients anticipated in prismatic HTGRs. Fuel fabrication conducted at both laboratory and engineering scale has demonstrated the ability to fabricate high quality UCO TRISO fuel with very low defects. The first irradiation (AGR 1) exposed about 300,000 TRISO fuel particles to a peak burnup of 19.6% FIMA, a peak fast-neutron fluence of about 4.3 × 1025 n/m2, and a maximum time-averaged fuel temperature of about 1,200°C without a single particle failure. The very low release of key metallic fission products (except silver) measured in post-irradiation examination (PIE) confirms the excellent performance measured under irradiation. Very low releases have been measured in accident simulation heatup testing (''safety testing'') after hundreds of hours at 1600 and 1700°C and no particle failures (no noble gas release measured) have been observed. Even after hundreds of hours at 1800°C, the releases are

  10. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Y.C. [Square Y, Orchard Park, NY (United States); Chen, S.Y.; LePoire, D.J. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Rothman, R. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

    1993-02-01

    This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors.

  11. Program ELM: A tool for rapid thermal-hydraulic analysis of solid-core nuclear rocket fuel elements

    Science.gov (United States)

    Walton, James T.

    1992-01-01

    This report reviews the state of the art of thermal-hydraulic analysis codes and presents a new code, Program ELM, for analysis of fuel elements. ELM is a concise computational tool for modeling the steady-state thermal-hydraulics of propellant flow through fuel element coolant channels in a nuclear thermal rocket reactor with axial coolant passages. The program was developed as a tool to swiftly evaluate various heat transfer coefficient and friction factor correlations generated for turbulent pipe flow with heat addition which have been used in previous programs. Thus, a consistent comparison of these correlations was performed, as well as a comparison with data from the NRX reactor experiments from the Nuclear Engine for Rocket Vehicle Applications (NERVA) project. This report describes the ELM Program algorithm, input/output, and validation efforts and provides a listing of the code.

  12. Installation Restoration Program. Preliminary Assessment: Gulfport Air National Guard Field Training Site Gulfport - Biloxi Regional Airport, Gulfport, Mississippi

    Science.gov (United States)

    1988-04-01

    Mississippi. The study was conducted under the Air National Guard’s iInstallation Restoration Program. 14. -UBJEC- 7 RMWS 115. NUMBER UF PAGES Installation...B-i APPNDIX C - USAF Hazard Assesinnt Rating Metodology . . . . . . . C-i APPENDIX D - Site Hazardous Assessent Rating Forms and Factor Rating...raemval of fuel sludge fran the storage tanks durir periodic tank cleaning activities. In both cases , wates were discarded within the benlmd areas of the

  13. Suitability of Haestholmen Loviisa for final disposal of spent fuel. Preliminary study; Loviisan Haestholmenin soveltuvuus kaeytetyn polttoaineen loppusijoitukseen. Esiselvitys

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    Based on the amendment of the Nuclear Energy Act the spent nuclear fuel of Imatran Voima Oy (IVO) will be disposed of in Finland instead of returning it to Russia. After Teollisuuden Voima Oy (TVO) and IVO had founded a joint company Posiva Oy the work IVO started in 1995 was brought together with the ongoing research programme for final disposal of spent fuel and extended to a feasibility study. The feasibility study was launched in the beginning of 1996. The geological evaluation was mainly based on the previous investigations at the island. For this study the complementary geological mapping has been carried out at the Haestholmen and on the surrounding area with a radius of 20 km. (49 refs.).

  14. U.S. Department of Energy Hydrogen and Fuel Cells Program 2012 Annual Merit Review and Peer Evaluation Report: May 14-18, 2012, Arlington, VA

    Energy Technology Data Exchange (ETDEWEB)

    2012-09-01

    This document summarizes the comments provided by peer reviewers on hydrogen and fuel cell projects presented at the fiscal year (FY) 2012 U.S. Department of Energy (DOE) Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting (AMR), held May 14-18, 2012, in Arlington, VA.

  15. AECL/U.S. INERI - Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in Power Reactors Fuel Requirements and Down-Select Report

    Energy Technology Data Exchange (ETDEWEB)

    William Carmack; Randy Fielding; Pavel Medvedev; Mitch Meyer

    2005-08-01

    This report documents the first milestone of the International Nuclear Energy Research Initiative (INERI) U.S./Euratom Joint Proposal 1.8 entitled “Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in Light-Water Reactors.” The milestone represents the assessment and preliminary study of a variety of fuels that hold promise as transmutation and minor actinide burning fuel compositions for light-water reactors. The most promising fuels of interest to the participants on this INERI program have been selected for further study. These fuel compositions are discussed in this report.

  16. 77 FR 74592 - Supplemental Determination for Renewable Fuels Produced Under the Final RFS2 Program From Grain...

    Science.gov (United States)

    2012-12-17

    ... Data Availability Concerning Renewable Fuels Produced From Palm Oil Under the RFS Program (77 FR 4300... use change GHG emissions related to grain sorghum ethanol by approximately 1.2 kilograms of carbon dioxide equivalent emissions per million British thermal units of grain sorghum ethanol (kgCO 2...

  17. Advanced fast reactor fuels program. Second annual progress report, July 1, 1975--September 30, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Baker, R.D. (comp.)

    1978-12-01

    Results of steady-state (EBR-II) irradiation testing, off-normal irradiation design and testing, fuel-cladding compatibility, and chemical stability of uranium--plutonium carbide and nitride fuels are presented.

  18. Ocean Thermal Energy Conversion power system development. Phase I: preliminary design. Final report. [ODSP-3 code; OTEC Steady-State Analysis Program

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-04

    The following appendices are included; Dynamic Simulation Program (ODSP-3); sample results of dynamic simulation; trip report - NH/sub 3/ safety precautions/accident records; trip report - US Coast Guard Headquarters; OTEC power system development, preliminary design test program report; medium turbine generator inspection point program; net energy analysis; bus bar cost of electricity; OTEC technical specifications; and engineer drawings. (WHK)

  19. Solid polymer electrolyte (SPE) fuel cell technology program, phase 1/1A. [design and fabrication

    Science.gov (United States)

    1975-01-01

    A solid polymer electrolyte fuel cell was studied for the purpose of improving the characteristics of the technology. Several facets were evaluated, namely: (1) reduced fuel cell costs; (2) reduced fuel cell weight; (3) improved fuel cell efficiency; and (4) increased systems compatibility. Demonstrated advances were incorporated into a full scale hardware design. A single cell unit was fabricated. A substantial degree of success was demonstrated.

  20. Programming of Energy Storage System in an Island Microgrid with Photovoltaic and Fuel Cell

    Directory of Open Access Journals (Sweden)

    Hossein KHORRAMDEL

    2014-07-01

    Full Text Available Photovoltaic (PV systems in island microgrids (MGs are becoming increasingly attractive as a means of energy generation, due to new developments in technologies, environmental concerns, and transmission congestion management. Usually, the energy storage system (ESS is used to store the excess power generated during off-peak hours, and to return it to the system when power from PV is not enough for the system, or generation is more expensive. A real-time dynamic programming algorithm for energy storage in a PV/battery system, based on the battery charge and discharge characteristics, and current and temperature dependence of the capacity of the battery, is presented in this paper. The work aims to extend existing battery- aware programming techniques. It differs from previous works, as it takes into consideration many aspects of battery characteristics that were not considered previously. This allows better use of the battery bank and can prolong the battery service time. This paper also builds a simple PV/battery system in an island microgrid. In this paper, fuel cell power plants (FCPPs are permanently used to operate in island microgrids, and 2 batteries are used as reserves for charge and discharge in various hours.

  1. Chemical engineering division fuel cycle programs. Progress report, January--September 1977

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M J; Ader, M; Barletta, R E

    1977-01-01

    Fuel-cycle studies reported for this period include pyrochemical separation of plutonium and americium oxides from contaminated materials of construction such as steel. When slag and actinide-contaminated metal in the same process vessel are heated until liquefied, the actinides are partitioned to a high degree into the slags. Also, studies of advanced solvent extraction techniques are focused on the development of centrifugal contactors for use in Purex processes. A miniature contactor is to be used for performance studies applicable to larger units. In other work, literature on the process chemistry of zirconium and ruthenium has been reviewed to aid in improving the process when short-residence-time contactors are used. In addition, a review of information on the dispersion of reagents and products during accidents in fuel reprocessing facilities has been initiated to develop systematic data useful in identifying source terms. A review and evaluation of the encapsulation of high-level waste in a metal matrix are continuing. The data will be used to identify the state of the art and the importance of selected features of this process. In other work, criteria for the handling of hulls are being developed on the basis of past work on the pyrophoricity of zirconium alloys and related criteria from several sources. These suggested criteria will be assembled with the necessary technical rationalization into a package for review by interested parties. Other work consists of a brief program to explore the disposal of noble gas fission products by deep-well injection and laboratory-scale experiments to study the migratory characteristics of nuclear waste confined in geologic formations. 28 figures, 26 tables.

  2. Chemical Engineering Division fuel cycle programs. Quarterly progress report, July-September 1978

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M.J.; Ader, M.; Barletta, R.E.

    1980-01-01

    Fuel cycle work included hydraulic performance and extraction efficiency of eight-stage centrifugal contactors, flowsheet for the Aralex process, Ru and Zr extraction in a miniature centrifugal contactor, study of Zr aging in the organic phase and its effect on Zr extraction and hydraulic testing of the 9-cm-ID contactor. Work for predicting accident consequences in LWR fuel processing covered the relation between energy input (to subdivide a solid) and the modes of particle size frequency distribution. In the pyrochemical and dry processing program corrosion-testing materials for containment vessels and equipment for studying carbide reactions in bismuth is under way. Analytical studies have been made of salt-transport processes; efforts to spin tungsten crucibles 13 cm dia continue, and other information on tungsten fabrication is being assembled; the process steps of the chloride volatility process have been demonstrated and the thoria powder product used to produce oxide pellets; solubility of UO/sub 2/, PuO/sub 2/, and fission products in molten alkali nitrates is being investigated; work was continued on reprocessing actinide oxides by extracting the actinides into ammonium chloroaluminate from bismuth; the preparation of thorium-uranium carbide from the oxide is being studied as a means of improving the oxide reactivity; studies are in progress on producing uranium metal and decontaminated ThO/sub 2/ by the reaction of (Th,U)O/sub 2/ solid solution in molten salts containing ThCl/sub 4/ and thorium metal chips. In the molten tin process, no basic thermodynamic or kinetic factors have been found that may limit process development.

  3. Preliminary assessment report for Fort William Henry Harrison, Montana Army National Guard, Helena, Montana. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    DuWaldt, J.; Meyer, T.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at a Montana Army National Guard (MTARNG) property near Helena, Montana. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the Fort William Henry Harrison property, requirements of the Department of Defense Installation Restoration Program.

  4. Preliminary performance appraisal of Navy V/STOL transport and search-type airplanes using hydrogen fuel

    Science.gov (United States)

    Strack, W. C.

    1974-01-01

    First-cut estimates are given of the performance advantages of liquid-hydrogen-fueled, ejector wing, V/STOL aircraft designed for shipboard delivery and search-type missions. Results indicate that the use of LH2 could reduce gross weights 30 percent, empty weights 15 percent, and energy consumption 10 percent for a fixed payload and mission. If gross weight is fixed, the delivery range could be increased about 60 percent or the hover time during a search mission doubled. No analysis or discussion of the economic and operational disadvantages is presented.

  5. Improving Phonological Awareness in Parents of Children at Risk of Literacy Difficulties: A Preliminary Evaluation of the Boost Program

    Directory of Open Access Journals (Sweden)

    Mark E. Boyes

    2017-09-01

    Full Text Available BackgroundPhonological awareness is an important skill underpinning the development of early literacy. Given the central role of parents in supporting the development of children’s early literacy skills, and that poor parental phonological awareness is associated with poorer child literacy outcomes, it is possible that improving parent phonological awareness may aid literacy development for at-risk children. This study is a preliminary evaluation of a program aiming to improve phonological awareness skills of parents in low socioeconomic status communities, and also provide these parents with strategies to support their child’s literacy development.MethodsAfter completing the program, participants were asked if it had helped them learn about how to assist their child’s reading and spelling, whether they planned on using the resources provided, and if they would be likely to attend a future workshop building on the Boost program. Phonological awareness measures (rhyme, syllable, and phoneme level, and measures of overall confidence in performance on the phonological awareness tasks, were administered both before and after attending the program.ResultsAlmost all parents indicated that the program helped with learning how to assist their child’s reading and spelling, that they would use the resources provided, and would likely attend a future workshop. Significant increases in pre- to post-program phonological awareness scores were obtained at the rhyme and phoneme level.ConclusionThe program and associated resources appear acceptable to parents in communities with high rates of literacy problems and improved parents’ phonological awareness skills. However, findings are preliminary and further evaluation using more rigorous methodologies and testing whether improvements in parents’ phonological awareness translate into better literacy outcomes for children is needed.

  6. U.S. Department of Energy Hydrogen and Fuel Cells Program, 2013 Annual Merit Review and Peer Evaluation Report (Book)

    Energy Technology Data Exchange (ETDEWEB)

    2013-10-01

    The fiscal year (FY) 2013 U.S. Department of Energy (DOE) Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Meeting (AMR), in conjunction with DOE's Vehicle Technologies Office AMR, was held from May 13-16, 2013, at the Crystal City Marriott and Crystal Gateway Marriott in Arlington, Virginia. This report is a summary of comments by AMR peer reviewers about the hydrogen and fuel cell projects funded by DOE's Office of Energy Efficiency and Renewable Energy (EERE).

  7. Elastic analysis of thermal gradient bowing in rod-type fuel elements subjected to axial thrust (LWBR Development Program)

    Energy Technology Data Exchange (ETDEWEB)

    Newman, J.B.

    1968-01-01

    Thermal radient bowing of rod type fuel elements can be analyzed in terms of the deflections of a precurved beam. The fundamental aspects of an analysis of axially compressed multispan beams are given. Elasticity of supports in both axial and transverse directions is considered; the technique is applicable to problems in which the axial thrust depends on the transverse deflection as well as problems with prescribed axial thrust. The formulas presented constitute the theory for a computer program of broad applicability, not only in the analysis of fuel rod bowing, but also to almost any multispan beam, particularly when the effects of axial loads cannot be neglected. 17 references. (NSA 22: 22866)

  8. Performance of a Double Catalyst Fuel Cell Cathode with a Tubular Oxygen Breathing and Preliminary Reduction Zone

    Institute of Scientific and Technical Information of China (English)

    Lu(i)s A. Waack BAMBACE; Miriam NISHIMORI; Fernando M. RAMOS; Demétrio BASTOS -NETTO

    2005-01-01

    @@ This paper discusses a mathematical model for a liquid phase reacting flow occurring at the cathode of a patent pending novel fuel cell geometry, where a non homogeneous catalysis carried by gold and Prussian Blue, with the first reducing air O2 and the second the resulting H2O2. The breathing zone is porous walls microtubes, with three different types of pores in its walls. Inside the microtubes there is water solution of sulfuric acid. The microtubes possess an external layer of extremely porous polymer hydrophobic agent. A Prussian Blue thin porous layer is over the selective membrane. Appropriate porous and tubular connecting elements close the fluid loop. The asymmetry induces proper current and electric potential profiles, which leads to a mainly electrocapillary electrokinetic flow, which enhances the oxygen transport and assures the H2O2 flow to its reduction layer.

  9. Preliminary Results of an On-Line, Multi-Spectrometer Fission Product Monitoring System to Support Advanced Gas Reactor Fuel Testing and Qualification in the Advanced Test Reactor at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Dawn M. Scates; John K. Hartwell; John B. Walter; Mark W. Drigert

    2007-10-01

    The Advanced Gas Reactor -1 (AGR-1) experiment is the first experiment in a series of eight separate low enriched uranium (LEU) oxycarbide (UCO) tri-isotropic (TRISO) particle fuel (in compact form) experiments scheduled for placement in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The experiment began irradiation in the ATR with a cycle that reached full power on December 26, 2006 and will continue irradiation for about 2.5 years. During this time six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The goals of the irradiation experiment is to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. This paper presents the preliminary test details of the fuel performance, as measured by the control and acquisition software.

  10. Preliminary Efficacy of a Cognitive-Behavioral Treatment Program for Anxious Youth with Autism Spectrum Disorders

    Science.gov (United States)

    White, Susan W.; Ollendick, Thomas; Scahill, Lawrence; Oswald, Donald; Albano, Anne Marie

    2009-01-01

    Anxiety is a commonly occurring psychiatric concern in adolescents with autism spectrum disorders (ASD). This pilot study examined the preliminary efficacy of a manual-based intervention targeting anxiety and social competence in four adolescents with high-functioning ASD. Anxiety and social functioning were assessed at baseline, midpoint,…

  11. Required Preliminary Administrative Service Credential Program Culminating Activities in California NCATE Accredited Universities

    Science.gov (United States)

    Wildman, Louis

    2014-01-01

    The purpose of this effort is to share information about the variety of culminating activities used in the acquisition of the California Preliminary Administrative Services Credential. Knowledge of these varying culminating activities and related practices has not previously been readily available. The culminating activities among California's…

  12. Spent nuclear fuels project: FY 1995 multi-year program plan, WBS {number_sign}1.4

    Energy Technology Data Exchange (ETDEWEB)

    Denning, J.L.

    1994-09-01

    The mission of the Spent Nuclear Fuel (SNF) program is to safely, reliably, and efficiently manage, condition, transport, and store Department of Energy (DOE)-owned SNF, so that it meets acceptance criteria for disposal in a permanent repository. The Hanford Site Spent Nuclear Fuel strategic plan for accomplishing the project mission is: Establish near-term safe storage in the 105-K Basins; Complete national Environmental Policy Act (NEPA) process to obtain a decision on how and where spent nuclear fuel will be managed on the site; Define and establish alternative interim storage on site or transport off site to support implementation of the NEPA decision; and Define and establish a waste package qualified for final disposition. This report contains descriptions of the following: Work Breakdown Structure; WBS Dictionary; Responsibility Assignment Matrix; Program Logic Diagrams; Program Master Baseline Schedule; Program Performance Baseline Schedule; Milestone List; Milestone Description Sheets; Cost Baseline Summary by Year; Basis of Estimate; Waste Type Data; Planned Staffing; and Fiscal Year Work Plan.

  13. Industrial fuel gas demonstration plant program. Current working estimate. Phase III and III

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    The United States Department of Energy (DOE) executed a contract with Memphis Light, Gas and Water Division (MLGW) which requires MLGW to perform process analysis, design, procurement, construction, testing, operation, and evaluation of a plant which will demonstrate the feasibility of converting high sulfur bituminous coal to industrial fuel gas with a heating value of 300 +- 30 Btu per standard cubic foot (SCF). The demonstration plant is based on the U-Gas process, and its product gas is to be used in commercial applications in Memphis, Tenn. The contract specifies that the work is to be conducted in three phases. The Phases are: Phase I - Program Development and Conceptual Design; Phase II - Demonstration Plant Final Design, Procurement and Construction; and Phase III - Demonstration Plant Operation. Under Task III of Phase I, a Cost Estimate for the Demonstration Plant was completed as well as estimates for other Phase II and III work. The output of this Estimate is presented in this volume. This Current Working Estimate for Phases II and III is based on the Process and Mechanical Designs presented in the Task II report (second issue) and the 12 volumes of the Task III report. In addition, the capital cost estimate summarized in the appendix has been used in the Economic Analysis (Task III) Report.

  14. Preliminary site characterization summary and engineering evaluation/cost analysis for Site 2, New Fuel Farm, Naval Air Station Fallon, Fallon, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Cronk, T.A.; Smuin, D.R. [Oak Ridge National Lab., TN (United States); Schlosser, R.M. [Oak Ridge Associated Universities, Inc., TN (United States)

    1991-09-01

    This report addresses subsurface contamination associated with Site 2, the New Fuel Farm at Naval Air Station Fallon (NAS Fallon), Nevada and is an integral part of Phase 2 of the Installation Restoration Program (IR Program) currently underway at the facility. This report: (1) reviews and assesses environmental information characterizing Site 2; (2) determine if site-characterization information is sufficient to design and evaluate removal actions; and, (3) investigates, develops, and describes any removal actions deemed feasible. Previous environmental investigations at Site 2 indicate the presence of floating product (primarily JP-5, jet fuel) on the water table underlying the facility. While the extent of floating-produce plumes has been characterized, the degree of associated soil and groundwater contamination remains uncertain. A comprehensive characterization of soil and groundwater contamination will be completed as the Remedial Investigation/Feasibility Study progresses. Corrective actions are recommended at this time to remove free-phase floating product. Implementing these removal actions will also provide additional information which will be used to direct further investigations of the extent, mobility, and potential environmental threat from soil and groundwater contaminants at this side.

  15. Progression of stages 3b–5 chronic kidney disease—Preliminary results of Taiwan National Pre-ESRD Disease Management Program in Southern Taiwan

    Directory of Open Access Journals (Sweden)

    Chun-Mei Lin

    2013-12-01

    Conclusion: Even though we cannot conclude with certainty that the Taiwan pre-ESRD disease management program is beneficial in slowing the progression of CKD stages 3b–5, our preliminary results seem to suggest this trend. Furthermore, the program may be improved by integrating it with other programs, such as those on diabetes and hypertension, thus making it a more patient-centered, multidisciplinary program.

  16. HTGR fuel recycle development program. Quarterly progress report for the period ending August 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-09-01

    The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on tradeoff studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle.

  17. Consolidated fuel reprocessing program. Progress report, January 1-March 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-06-01

    Progress and activities are reported on process development, laboratory R and D, engineering research, engineering systems, Integrated Equipment Test (IET) facility operations, and HTGR fuel reprocessing. (DLC)

  18. Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979

    Energy Technology Data Exchange (ETDEWEB)

    Steindler, M J; Ader, M; Barletta, R E

    1980-01-01

    In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing of refractory metals and alloys, graphite, and SiC in PDPM environments was done. A tungsten-metallized Al/sub 2/O/sub 3/-3% Y/sub 2/O/sub 3/ crucible was successfully fabricated. Tungsten microstructure of a plasma-sprayed tungsten crucible was stabilized by nickel infiltration and heat treatment. Solubility measurements of Th in Cd and Cd-Mg alloys were continued, as were experiments to study the reduction of high-fired ThO/sub 2/. Work on the fused salt electrolysis of CaO also was continued. The method of coprocessing of U and Pu by a salt transport process was modified. Tungsten-coated molybdenum crucibles were fabricated. The proliferation resistance of chloride volatility processing of thorium-based fuels is being evaluated by studying the behavior of fission product elements during chlorination of U and Th. Thermodynamic analysis of the phase relationships in the U-Pu-Zn system was initiated. The Pyro-Civex reprocessing method is being reviewed. Reactivity of UO/sub 2/ and PuO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ is being studied along with the behavior of selected fission product elements. Work was continued on the reprocessing of actinide oxides by extracting the actinides from a bismuth solution. Rate of dissolution of UO/sub 2/ microspheres in LiCl/AlCl/sub 3/ was measured. Nitriding rates of Th and U dissolved in molten tin were measured. In work on the encapsulation of radioactive waste in metal, leach rates of a simulated waste glass were studied. Rates of dissolution of metals (potential barrier materials) in aqueous media are being studied. In work on the transport properties of nuclear waste in geologic media, the adsorption of iodate by hematite as a function of pH and iodate concentration was measured. The migration behavior of cesium in limestone was studied in relation to the cesium concentration and pH of simulated groundwater

  19. PRELIMINARY IN-SITU X-RAY ABSORPTION FINE STRUCTURE EXAMINATION OF PT/C AND PTCO/C CATHODE CATALYSTS IN AN OPERATIONAL POLYMER ELECTROLYTE FUEL CELL

    Energy Technology Data Exchange (ETDEWEB)

    Phelan, B.T.; Myers, D.J.; Smith, M.C.

    2009-01-01

    State-of-the-art polymer electrolyte fuel cells require a conditioning period to reach optimized cell performance. There is insuffi cient understanding about the behavior of catalysts during this period, especially with regard to the changing environment of the cathode electrocatalyst, which is typically Pt nanoparticles supported on high surface area Vulcan XC-72 carbon (Pt/C). The purpose of this research was to record preliminary observations of the changing environment during the conditioning phase using X-Ray Absorption Fine Structure (XAFS) spectroscopy. XAFS was recorded for a Pt/C cathode at the Pt L3-edge and a PtCo/C cathode at both the Pt L3-edge and Co K-edge. Using precision machined graphite cell-blocks, both transmission and fl uorescence data were recorded at Sector 12-BM-B of Argonne National Laboratory’s Advanced Photon Source. The fl uorescence and transmission edge steps allow for a working description of the changing electrocatalyst environment, especially water concentration, at the anode and cathode as functions of operating parameters. These features are discussed in the context of how future analysis may correlate with potential, current and changing apparent thickness of the membrane electrode assembly through loss of catalyst materials (anode, cathode, carbon support). Such direct knowledge of the effect of the conditioning protocol on the electrocatalyst may lead to better catalyst design. In turn, this may lead to minimizing, or even eliminating, the conditioning period.

  20. Preliminary Study on E.coli Microbial Fuel Cell and On-electrode Taming of the Biocatalyst

    Institute of Scientific and Technical Information of China (English)

    郗名悦; 孙彦平

    2008-01-01

    A mediator microbial ruel cell(MFC)was constructed by using E.coil as biocatalyst and new methylene blue as electron mediator.E coli cells were carried out in anaerobic growth prior to inoculating them into the MFC in order to pre-adapt bacterial metabolism in an anaerobic environment,the electricity generation of MFC Was tested,its maximum power density reached 263.94 mW/m2 with the corresponding current density 1 287.50 mA/m2.the internal resistance of MFC was 200 Ω.and capability of the MFC was even better than those reported so far.Moreover,on-electrode taming method was adopted to improve electrochemical activity of E.coli.namety a combination of E.coli taming and electricity generation simultaneously in the same MFC without scraping off the biofilm of MFC,after the 4th on-electrode taming,the tamed E.coli MFC showed a 54%improvement in peak current density,being 612.50 mA/m2.and a 64%improvement in the maximum poweroutput,behag 166.67mW/m2.compared with that of parental E coli MFC.And the maturation time of tamed biofilm Was obviously duced to 240 min,quickening up l times compared with that of parental E coli biofilm.Kev words:microbial fuel cell;E.coli;taming;biofilm

  1. Evaluation and demonstration of methods for improved fuel utilization. Fort Calhoun Poolside Inspection Programs: end-of-cycles 4 and 5

    Energy Technology Data Exchange (ETDEWEB)

    LaVake, J.C.; Smith, G.P.

    1980-08-01

    The purpose of this program is to demonstrate two techniques for improving fuel utilization in current Pressurized Water Reactors (PWR): (1) more efficient fuel management, and (2) high burnup. These improvements are being demonstrated in the Fort Calhoun reactor, a 1420 Mwt PWR. A more efficient fuel management scheme called SAVFUEL (Shimmed And Very Flexible Uranium Element Loading), will be demonstrated which reduces neutron leakage and is expected to reduce uranium requirements. Another part of the demonstration program will increase the fuel burnup of the current 14 x 14 fuel design to further reduce uranium requirements. The program is a joint Department of Energy (DOE), Omaha Public Power District (OPPD) and Combustion Engineering (C-E) endeavor and is part of a national effort to improve uranium utilization in light water reactors.

  2. Technical Approach and Plan for Transitioning Spent Nuclear Fuel (SNF) Project Facilities to the Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    SKELLY, W.A.

    1999-10-06

    This document describes the approach and process in which the 100-K Area Facilities are to be deactivated and transitioned over to the Environmental Restoration Program after spent nuclear fuel has been removed from the K Basins. It describes the Transition Project's scope and objectives, work breakdown structure, activity planning, estimated cost, and schedule. This report will be utilized as a planning document for project management and control and to communicate details of project content and integration.

  3. Application of the successive linear programming technique to the optimum design of a high flux reactor using LEU fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mo, S.C.

    1991-01-01

    The successive linear programming technique is applied to obtain the optimum thermal flux in the reflector region of a high flux reactor using LEU fuel. The design variables are the reactor power, core radius and coolant channel thickness. The constraints are the cycle length, average heat flux and peak/average power density ratio. The characteristics of the optimum solutions with various constraints are discussed.

  4. Application of the successive linear programming technique to the optimum design of a high flux reactor using LEU fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mo, S.C.

    1991-12-31

    The successive linear programming technique is applied to obtain the optimum thermal flux in the reflector region of a high flux reactor using LEU fuel. The design variables are the reactor power, core radius and coolant channel thickness. The constraints are the cycle length, average heat flux and peak/average power density ratio. The characteristics of the optimum solutions with various constraints are discussed.

  5. Preliminary In-Flight Loads Analysis of In-Line Launch Vehicles using the VLOADS 1.4 Program

    Science.gov (United States)

    Graham, J. B.; Luz, P. L.

    1998-01-01

    To calculate structural loads of in-line launch vehicles for preliminary design, a very useful computer program is VLOADS 1.4. This software may also be used to calculate structural loads for upper stages and planetary transfer vehicles. Launch vehicle inputs such as aerodynamic coefficients, mass properties, propellants, engine thrusts, and performance data are compiled and analyzed by VLOADS to produce distributed shear loads, bending moments, axial forces, and vehicle line loads as a function of X-station along the vehicle's length. Interface loads, if any, and translational accelerations are also computed. The major strength of the software is that it enables quick turnaround analysis of structural loads for launch vehicles during the preliminary design stage of its development. This represents a significant improvement over the alternative-the time-consuming, and expensive chore of developing finite element models. VLOADS was developed as a Visual BASIC macro in a Microsoft Excel 5.0 work book on a Macintosh. VLOADS has also been implemented on a PC computer using Microsoft Excel 7.0a for Windows 95. VLOADS was developed in 1996, and the current version was released to COSMIC, NASA's Software Technology Transfer Center, in 1997. The program is a copyrighted work with all copyright vested in NASA.

  6. Feasibility study of an interactive multimedia electronic problem solving treatment program for depression: a preliminary uncontrolled trial.

    Science.gov (United States)

    Berman, Margit I; Buckey, Jay C; Hull, Jay G; Linardatos, Eftihia; Song, Sueyoung L; McLellan, Robert K; Hegel, Mark T

    2014-05-01

    Computer-based depression interventions lacking live therapist support have difficulty engaging users. This study evaluated the usability, acceptability, credibility, therapeutic alliance and efficacy of a stand-alone multimedia, interactive, computer-based Problem Solving Treatment program (ePST™) for depression. The program simulated live treatment from an expert PST therapist, and delivered 6 ePST™ sessions over 9weeks. Twenty-nine participants with moderate-severe symptoms received the intervention; 23 completed a minimally adequate dose of ePST™ (at least 4 sessions). Program usability, acceptability, credibility, and therapeutic alliance were assessed at treatment midpoint and endpoint. Depressive symptoms and health-related functioning were assessed at baseline, treatment midpoint (4weeks), and study endpoint (10weeks). Depression outcomes and therapeutic alliance ratings were also compared to previously published research on live PST and computer-based depression therapy. Participants rated the program as highly usable, acceptable, and credible, and reported a therapeutic alliance with the program comparable to that observed in live therapy. Depressive symptoms improved significantly over time. These findings also provide preliminary evidence that ePST™ may be effective as a depression treatment. Larger clinical trials with diverse samples are indicated.

  7. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement. Volume 1, Appendix D: Part A, Naval Spent Nuclear Fuel Management

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.

  8. Manual for Replication of the Mother-Child Home Program. (Preliminary Version, for Field-Testing).

    Science.gov (United States)

    Levenstein, Phyllis; And Others

    Information to assist local institutions in operating Mother-Child Programs i s provided in this manual as part of the Verbal Interaction Project. Following an introduction, the manual discusses the following topics: (1) Ingredients and Procedures of a Mother-Child Program, (2) Major Program Components, (3) Administrative and Other Practical…

  9. A Bystander Bullying Psychoeducation Program with Middle School Students: A Preliminary Report

    Science.gov (United States)

    Midgett, Aida; Doumas, Diana; Sears, Dara; Lundquist, Amanda; Hausheer, Robin

    2015-01-01

    This study evaluated the effectiveness of a brief, stand-alone bystander bullying psychoeducation program for middle school students. The purpose of the program was to train students to take action as peer advocates. Pre- and post-tests indicated that after completing the 90-minute psychoeducation program, students reported an increase in their…

  10. Semi-annual status report of the Canadian Nuclear Fuel Waste Management Program, April 1--September 30, 1991

    Energy Technology Data Exchange (ETDEWEB)

    Wright, E.D. [comp.

    1992-02-01

    This report is the eleventh in a series of semi-annual status reports on the research and development program for the safe management and disposal of Canada's nuclear fuel waste. it describes progress achieved in the three major subprograms, engineered systems, natural systems and performance assessment, from 1991 April 1 to September 30. It also gives a brief description of the activities being carried out in preparation for the public and governmental review of the disposal concept. Since 1987, this program has been jointly funded by AECL and Ontario Hydro under the auspices of the CANDU Owners Group (COG).

  11. Krakow clean fossil fuels and energy efficiency program. Phase 1 report

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, T.; Pierce, B. [eds.

    1995-06-01

    Krakow is one of the largest and oldest cities in Poland. It is situated in the south of the country on the banks of the Vistula River. From the 11th until the 17th centuries, it was the capital of Poland. Today, Krakow is a city of 750,000 residents, one of the largest centers of higher education, an important industrial center, and is of particular importance because of the number and kinds of historic buildings and sites. For this reason, Krakow was included by the UNESCO in the list of the world`s cultural heritages. For about three decades, significant air pollution has been one of Krakow`s most serious problems. Because the city is situated in the Vistula River valley, it is poorly ventilated and experiences a high concentration of air pollutants. The quality of air in Krakow is affected mainly by industry (Sendzimir Steelworks, energy industry, chemical plants), influx from the Silesian industrial region (power plants, metallurgy), transboundary pollution (Ostrava - Czech Republic), and local sources of low pollution, i.e. more than 1,000 boiler houses using solid fuels and more than 100,000 coal-fired home stoves. These local sources, with low stacks and almost no pollution-control equipment, are responsible for about 35-40% of the air pollution. This report presents phase I results of a program to reduce pollution in krakow. Phase I was to gather information on emissions and costs, and to verify assumptions on existing heating methods and alternatives.

  12. Thermal-hydraulic Fortran program for steady-state calculations of plate-type fuel research reactors

    Directory of Open Access Journals (Sweden)

    Khedr Ahmed

    2008-01-01

    Full Text Available The safety assessment of research and power reactors is a continuous process covering their lifespan and requiring verified and validated codes. Power reactor codes all over the world are well established and qualified against real measuring data and qualified experimental facilities. These codes are usually sophisticated, require special skills and consume a lot of running time. On the other hand, most research reactor codes still require much more data for validation and qualification. It is, therefore, of benefit to any regulatory body to develop its own codes for the review and assessment of research reactors. The present paper introduces a simple, one-dimensional Fortran program called THDSN for steady-state thermal-hydraulic calculations of plate-type fuel research reactors. Besides calculating the fuel and coolant temperature distributions and pressure gradients in an average and hot channel, the program calculates the safety limits and margins against the critical phenomena encountered in research reactors, such as the onset of nucleate boiling, critical heat flux and flow instability. Well known thermal-hydraulic correlations for calculating the safety parameters and several formulas for the heat transfer coefficient have been used. The THDSN program was verified by comparing its results for 2 and 10 MW benchmark reactors with those published in IAEA publications and a good agreement was found. Also, the results of the program are compared with those published for other programs, such as the PARET and TERMIC.

  13. Experimental test plan: USDOE/JAERI collaborative program for the coated particle fuel performance test

    Energy Technology Data Exchange (ETDEWEB)

    Kania, M.J. [Oak Ridge National Lab., TN (United States); Fukuda, K. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1989-12-01

    This document describes the coated-particle fuel performance test agreed to under Annex 2 of the arrangement between the US Department of Energy and the Japan Atomic Energy Research Institute on cooperation in research and development regarding high-temperature gas-cooled reactors (HTGRs). The test will evaluate the behavior of reference fuel compacts containing coated-particle fuels fabricated according to the specifications for the US Modular HTGR and the Japanese High-Temperature Engineering Test Reactor (HTTR) concepts. Two experimental capsules, HRB-21 and HRB-22, are being tested. Capsule HRB-21 contains only US reference fuel, and HRB-22 contains only JAERI reference fuel. Both capsules will be irradiated in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Capsule HRB-21 will be operated at a mean volumetric fuel temperature of 975{degrees}C and will achieve a peak fissile burnup of 26% fissions per initial metal atom (FIMA) and a fast fluence of {le}4.5 {times} 10{sup 25} neutrons/m{sup 2}. Capsule HRB-22 will be operated at a mean centerline fuel temperature of 1250 to 1300{degrees}C and will achieve a peak fissile burnup of 5.5% FIMA and a fast fluence of 1.7 {times} 10{sup 25} neutrons/m{sup 2}. Performance of the fuels during irradiation will be closely monitored using on-line fission gas surveillance. Following irradiation, both capsules will undergo detailed examinations and core heatup simulation testing. Results from in-reactor monitoring and postirradiation testing will be analyzed to comparatively assess US and Japanese coated-particle fuel performance. 3 refs., 9 figs., 10 tabs.

  14. The hydrogen and the fuel cells in the world. Programs and evolutions; L'hydrogene et les piles a combustibles dans le monde. Programmes et evolutions

    Energy Technology Data Exchange (ETDEWEB)

    Lucchese, P. [CEA Saclay, Dir. des Nouvelles Technologies de l' Energie CEA, 91 - Gif-sur-Yvette (France)

    2008-07-01

    HyPac is a french platform on the hydrogen and fuel cells, created in 2008. The author presents the opportunity of such a platform facing the world research programs and other existing platforms. (A.L.B.)

  15. Program for fundamental and applied research of fuel cells in VNIIEF

    Energy Technology Data Exchange (ETDEWEB)

    Anisin, A.V.; Borisseonock, V.A.; Novitskii, Y.Z.; Potyomckin, G.A.

    1996-04-01

    According to VNIIEF the integral part of development of fuel cell power plants is fundamental and applied research. This paper describes areas of research on molten carbonate fuel cells. Topics include the development of mathematical models for porous electrodes, thin film electrolytes, the possibility of solid nickel anodes, model of activation polarization of anode, electrolyte with high solubility of oxygen. Other areas include research on a stationary mode of stack operation, anticorrosion coatings, impedance diagnostic methods, ultrasound diagnostics, radiation treatments, an air aluminium cell, and alternative catalysts for low temperature fuel cells.

  16. Effects of earthquakes on the deep repository for spent fuel in Sweden based on case studies and preliminary model results

    Energy Technology Data Exchange (ETDEWEB)

    Baeckblom, Goeran [Conrox, Djursholm (Sweden); Munier, Raymond [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2002-06-01

    The Baltic Shield is one of the most stable areas in the world. Earthquakes have only on a few occasions exceeded magnitude 4 in Sweden in modern times. The safety case for a deep repository for spent fuel however includes an earthquake scenario due to the following reason: Earthquakes with much greater magnitudes occurred in northern Sweden during the most recent deglaciation period some 9,000 - 10,000 years ago when re-activated faults ruptured the surface. One of the most prominent evidences is the Paervie fault in Lapland, Sweden. The displacements exceeded 10 m in places and occurred over distances of around 150 km. The deep repository is designed to keep radiation well below the natural, ambient radiation for any time in the future. The safety function is achieved by a combination of engineered and natural barriers. One important safety issue is that future displacements in the rock should be less than 0.1 m at the precise location where the engineered canisters containing the waste are emplaced in the rock. Larger displacements could damage the canister that is designed to be tight for several 100,000 of years. SKB now re-visits the issues of seismic effects on underground facilities to supplement and update previous work. The project Effects of Earthquakes on Underground Facilities aims to re-compile field evidences of seismic damage on underground facilities, to shed additional light on the matter of friction loss in bedrock due to water-level changes and finally to find suitable ways to inform concerned citizens on the matter. The fact-finding was carried out in the form of interviews, literature surveys, Internet searches and by sending letters to some 60 organisations and researchers asking for co-operation. The most important conclusions are: Earthquake impact during the pre-closure phase: Damage due to shaking in an underground facility may occur if the peak ground acceleration exceeds 2 m/s{sup 2}. Sweden is located in the Baltic Shield that is

  17. Effects of earthquakes on the deep repository for spent fuel in Sweden based on case studies and preliminary model results

    Energy Technology Data Exchange (ETDEWEB)

    Baeckblom, Goeran [Conrox, Djursholm (Sweden); Munier, Raymond [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2002-06-01

    The Baltic Shield is one of the most stable areas in the world. Earthquakes have only on a few occasions exceeded magnitude 4 in Sweden in modern times. The safety case for a deep repository for spent fuel however includes an earthquake scenario due to the following reason: Earthquakes with much greater magnitudes occurred in northern Sweden during the most recent deglaciation period some 9,000 - 10,000 years ago when re-activated faults ruptured the surface. One of the most prominent evidences is the Paervie fault in Lapland, Sweden. The displacements exceeded 10 m in places and occurred over distances of around 150 km. The deep repository is designed to keep radiation well below the natural, ambient radiation for any time in the future. The safety function is achieved by a combination of engineered and natural barriers. One important safety issue is that future displacements in the rock should be less than 0.1 m at the precise location where the engineered canisters containing the waste are emplaced in the rock. Larger displacements could damage the canister that is designed to be tight for several 100,000 of years. SKB now re-visits the issues of seismic effects on underground facilities to supplement and update previous work. The project Effects of Earthquakes on Underground Facilities aims to re-compile field evidences of seismic damage on underground facilities, to shed additional light on the matter of friction loss in bedrock due to water-level changes and finally to find suitable ways to inform concerned citizens on the matter. The fact-finding was carried out in the form of interviews, literature surveys, Internet searches and by sending letters to some 60 organisations and researchers asking for co-operation. The most important conclusions are: Earthquake impact during the pre-closure phase: Damage due to shaking in an underground facility may occur if the peak ground acceleration exceeds 2 m/s{sup 2}. Sweden is located in the Baltic Shield that is

  18. Fuel Gas Demonstration Plant Program: Small-Scale Industrial Project. Demonstration plant design and economic evaluation, Phase I. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-01

    The Fuel Gas Demonstration Plant Program envisions a coal gasification facility to provide low Btu gas to the Erie Mining Company taconite pelletizing operations at Hoyt Lakes, Minnesota. Initially, it will consist of a Demonstration Plant which will be sized to supply 7.4 billion Btu (HHV) of fuel energy per day, which is approximately 37% of the Erie Mining Company's daily energy requirement for the induration of pellets. The Demonstration Plant will be designed to permit ultimate expansion to a Commercial Plant capable of supplying the entire fuel gas requirement of the pellet plant. Erie Mining Company is one of the largest producers of iron ore pellets in the United States. Its plant consists of 27 shaft furnaces with an annual production capacity of 10.3 million tons. The furnaces now operate on natural gas and use ful oil as a backup energy supply. Fuel consumption is normally equivalent to 20 billion Btu per day. The contract arrangement between the Department of Energy and Erie Mining Company provides mutually advantageous opportunity and means for: employing coal gasification technology and equipment which is now commercially available, for production and use of low Btu gas in an industrial environment under actual operating conditions; identifying, defining and resolving problems and operational unknowns that have heretofore retarded industrial use of synthetic gas; establishing parameters for retrofitting existing industrial furnaces for use of low Btu gas; and determining and demonstrating the technical and economic feasibility of the proposed scheme.

  19. Origins of institutional change: Brazilian alcohol fuel program between 1975 and 2000

    Energy Technology Data Exchange (ETDEWEB)

    Ollinaho, O.I.

    2012-07-01

    In this dissertation, I study the origins of institutional change. In organizational institutionalism institutional change is seen as being triggered either by exogenous shocks or by endogenous factors. I propose to see the origins of change instead through the dichotomy of cognitive versus material. One rationale for this is that, when addressing more broadly dispersed societal practices, the distinction between endogenous and exogenous loses its meaning. Another reason is that without taking materiality into account in a more comprehensive manner, institutional theory is toothless against the vast material fluxes that human activity, patterned as established practices, produces and consumes. Human activity is transforming the very basis of its foundation: raw material sources, ecosystems and even the climate of the planet. Not only does human activity have an impact on the planet, but the materiality in which we live, has its impact on our activity. I argue that changes in materiality affect our habitualized activities depending on how these changes are produced. This setting requires a more comprehensive relating of material and cognitive processes, something that I attempt to elucidate in this dissertation. I ground my conceptual development in the German sociology of knowledge, foremost in the writings of Alfred Schuetz and Thomas Luckmann. Established practices related to fossil fuels are central with regard to the adverse impacts of human activity. I study arguably the most successful attempt to deviate from these patterns: Proalcool. This ambitious Brazilian biofuel program was launched in 1975. Although alcohol was generally argued to be the definitive Brazilian solution and alcohol cars dominated the scene in the 1980s, by the end of the 1990s the program had lost its legitimacy and was seen as baggage to be done away with. I reconstruct the evolution of the program from 1975 to 2000 as a detailed narrative based on some 4000 news articles published in a

  20. Eighteenth symposium on biotechnology for fuels and chemicals: Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This volume provides the proceedings for the Eighteenth Symposium on Biotechnology for Fuels and Chemicals held May 5-9, 1996 in Gatlinburg, Tennessee. The proceedings contains abstracts for oral and poster presentations.

  1. Actinide partitioning-transmutation program final report. IV. Miscellaneous aspects. [Transport; fuel fabrication; decay; policy; economics

    Energy Technology Data Exchange (ETDEWEB)

    Alexander, C.W.; Croff, A.G.

    1980-09-01

    This report discusses seven aspects of actinide partitioning-transmutation (P-T) which are important in any complete evaluation of this waste treatment option but which do not fall within other major topical areas concerning P-T. The so-called miscellaneous aspects considered are (1) the conceptual design of a shipping cask for highly neutron-active fresh and spent P-T fuels, (2) the possible impacts of P-T on mixed-oxide fuel fabrication, (3) alternatives for handling the existing and to-be-produced spent fuel and/or wastes until implementation of P-T, (4) the decay and dose characteristics of P-T and standard reactor fuels, (5) the implications of P-T on currently existing nuclear policy in the United States, (6) the summary costs of P-T, and (7) methods for comparing the risks, costs, and benefits of P-T.

  2. Spent fuel handling and packaging program. Quarterly report, April-June 1980

    Energy Technology Data Exchange (ETDEWEB)

    Durrill, D C

    1980-07-01

    This document is a report of activities performed by Westinghouse Advanced Energy Systems Division-Nevada Operations at the E-MAD Facility, Area 25, Nevada Test Site, in meeting subtask objectives during the third quarter of FY 1980. Activities during this period included completion of encapsulation and preparation for shipment of 11 spent fuel assemblies to be tested at the Climax test site by Lawrence Livermore Laboratories; calorimetry of two fuel assemblies; repeat of three 1 kW Fuel Temperature Test runs; acquisition of gas samples from fueled canisters; removal of ten R-MAD shielding windows; and assembly and checkout of the canister cutter, which was received from AESD-Large.

  3. 78 FR 11870 - Proposed Information Collection Request; Comment Request; Renewable Fuels Standard (RFS2) Program

    Science.gov (United States)

    2013-02-20

    ... Fuel Producer Co-products Report RFS0801: RFS2 Renewable Biomass Report RFS0901: RFS2 Production... domestic plantation/forest land owners and foreign biofuel feedstock producers which were not reflected in...

  4. Consolidated fuel-reprocessing program. Progress report, April 1-June 30, 1982

    Energy Technology Data Exchange (ETDEWEB)

    Burch, W D

    1982-09-01

    Highlights of progress accomplished during the quarter ending June 30, 1982 are summarized. Discussion is presented under the headings: Process development; Laboratory R and D; Engineering research; Engineering systems; Integrated equipment test facility operation; Instrument development; and HTGR fuel reprocessing.

  5. SOLVENT EXTRACTION RESEARCH AND DEVELOPMENT IN THE U.S. FUEL CYCLE PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    Terry A. Todd

    2011-10-01

    Treatment or processing of used nuclear fuel to recycle uranium and plutonium has historically been accomplished using the well known PUREX process. The PUREX process has been used on an industrial scale for over 60 years in the nuclear industry. Research is underway to develop advanced separation methods for the recovery of other used fuel components, such as the minor actinides (Np, Am, Cm) for possible transmutation in fast spectrum reactors, or other constituents (e.g. Cs, Sr, transition metals, lanthanides) to help facilitate effective waste management options. This paper will provide an overview of new solvent extraction processes developed for advanced nuclear fuel cycles, and summarize recent experimental results. This will include the utilization of new extractants for selective separation of target metals and new processes developed to selectively recover one or more elements from used fuel.

  6. Oxide fuel element and blanket element development programs. Quarterly progress report, January-February-March, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Fuel pin profilometry of some 9% burnup F20-F5 pins showed small diameter increases at the fuel-insulator interface at the top of the core. Neither these secondary peaks nor the larger diameter increases near the core midplane exhibited any relationship to the local presence of once-molten fuel in any F20 fuel pin. Augmented safety analysis computations for experiment AB-1 (additional transients suggested by HEDL) showed that cumulative damage fractions from the additional transients were in every case less than 10/sup -4/. Mechanical tests have been performed that confirm previous computations for the removal end plugs to be used in a characterizer subassembly for AB-1. The resulting pin removal forces are well within the design envelope.

  7. Internal hydriding in irradiated defected Zircaloy fuel rods: A review (LWBR Development Program)

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, J C

    1987-10-01

    Although not a problem in recent commercial power reactors, including the Shippingport Light Water Breeder Reactor, internal hydriding of Zircaloy cladding was a persistent cause of gross cladding failures during the 1960s. It occurred in the fuel rods of water-cooled nuclear power reactors that had a small cladding defect. This report summarizes the experimental findings, causes, mechanisms, and methods of minimizing internal hydriding in defected Zircaloy-clad fuel rods. Irradiation test data on the different types of defected fuel rods, intentionally fabricated defected and in-pile operationally defected rods, are compared. Significant factors affecting internal hydriding in defected Zircaloy-clad fuel rods (defect hole size, internal and external sources of hydrogen, Zircaloy cladding surface properties, nickel alloy contamination of Zircaloy, the effect of heat flux and fluence) are discussed. Pertinent in-pile and out-of-pile test results from Bettis and other laboratories are used as a data base in constructing a qualitative model which explains hydrogen generation and distribution in Zircaloy cladding of defected water-cooled reactor fuel rods. Techniques for minimizing internal hydride failures in Zircaloy-clad fuel rods are evaluated.

  8. Future aviation fuels overview

    Science.gov (United States)

    Reck, G. M.

    1980-01-01

    The outlook for aviation fuels through the turn of the century is briefly discussed and the general objectives of the NASA Lewis Alternative Aviation Fuels Research Project are outlined. The NASA program involves the evaluation of potential characteristics of future jet aircraft fuels, the determination of the effects of those fuels on engine and fuel system components, and the development of a component technology to use those fuels.

  9. Preliminary assessment report for Florence Military Reservation, Installation 04080, Florence, Arizona. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Arizona Army National Guard property near Florence, Arizona. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. Florence Military Reservation is a 5,655-acre site located in the southern portion of Arizona, about 65 mi southeast of Phoenix, in the county of Pinal. Florence Military Reservation includes Unit Training Equipment Site (UTES) 1, an artillery firing range, and ammunition storage. The subject of this PA is the UTES. The environmentally significant operations associated with the UTES property are (1) vehicle maintenance and refueling, (2) supply/storage of materials, and (3) the vehicle washrack.

  10. Computer program for obtaining thermodynamic and transport properties of air and products of combustion of ASTM-A-1 fuel and air

    Science.gov (United States)

    Hippensteele, S. A.; Colladay, R. S.

    1978-01-01

    A computer program for determining desired thermodynamic and transport property values by means of a three-dimensional (pressure, fuel-air ratio, and either enthalpy or temperature) interpolation routine was developed. The program calculates temperature (or enthalpy), molecular weight, viscosity, specific heat at constant pressure, thermal conductivity, isentropic exponent (equal to the specific heat ratio at conditions where gases do not react), Prandtl number, and entropy for air and a combustion gas mixture of ASTM-A-1 fuel and air over fuel-air ratios from zero to stoichiometric, pressures from 1 to 40 atm, and temperatures from 250 to 2800 K.

  11. A new national service learning program in the Netherlands : preliminary evidence

    NARCIS (Netherlands)

    Bekkers, René

    2009-01-01

    Since 2006, the Department of Education in the Netherlands encourages the introduction of service learning programs at the level of secondary education. The goal of the programs is to promote civic-mindedness: civic engagement, awareness of values and norms, and active citizenship. Past studies of

  12. A new national service learning program in the Netherlands : preliminary evidence

    NARCIS (Netherlands)

    Bekkers, René

    2009-01-01

    Since 2006, the Department of Education in the Netherlands encourages the introduction of service learning programs at the level of secondary education. The goal of the programs is to promote civic-mindedness: civic engagement, awareness of values and norms, and active citizenship. Past studies of t

  13. A new national service learning program in the Netherlands : preliminary evidence

    NARCIS (Netherlands)

    Bekkers, René

    2009-01-01

    Since 2006, the Department of Education in the Netherlands encourages the introduction of service learning programs at the level of secondary education. The goal of the programs is to promote civic-mindedness: civic engagement, awareness of values and norms, and active citizenship. Past studies of t

  14. An Exploratory Study for MLK (Martin Luther King) Program Improvement. Preliminary Report.

    Science.gov (United States)

    Bournazos, Kimon

    A highly necessary step in the institution of programs for educating and preparing minority youth for the world is periodic evaluation to make certain that the quality of the program is at such a level that the needs of the participants are properly served. One hundred twenty-eight students answered a 44-item questionnaire concerning their…

  15. Success in Preschool Learning Related to Formal and Open-Framework Programs: A Preliminary Report.

    Science.gov (United States)

    Lawton, Joseph T.

    1978-01-01

    Two types of educational programs for young children were examined, the formal based on Ausebel's learning theory and the open-framework based on Piaget's theory of intellectual development. The formal program resulted in improved performance on both classification and conservation tasks. (MF)

  16. Preliminary assessment report for Army Aviation Support Facility No. 3, Installation 13307, Hunter Army Airfield, Savannah, Georgia. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Kolpa, R.; Smith, K.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard property located on Hunter Army Airfield (HAA) near Savannah, Georgia, known as Army Aviation Support Facility (AASF) No. 3. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, types and quantities of hazardous substances utilized, the nature and amounts of wastes generated or stored at the facility, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the AASF No. 3 property, requirements of the Department of Defense Installation Restoration Program (IRP). The scope of this assessment is limited to the facilities and past activities contained within the area now occupied by AASF No. 3. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of HAA completed in 1992 (USATHAMA 1992) and to provide comprehensive information on AASF No. 3 for incorporation with information contained in that previous assessment for the entirety of HAA.

  17. Preliminary assessment report for Army Aviation Support Facility No. 3, Installation 13307, Hunter Army Airfield, Savannah, Georgia. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Kolpa, R.; Smith, K.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard property located on Hunter Army Airfield (HAA) near Savannah, Georgia, known as Army Aviation Support Facility (AASF) No. 3. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, types and quantities of hazardous substances utilized, the nature and amounts of wastes generated or stored at the facility, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the AASF No. 3 property, requirements of the Department of Defense Installation Restoration Program (IRP). The scope of this assessment is limited to the facilities and past activities contained within the area now occupied by AASF No. 3. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of HAA completed in 1992 (USATHAMA 1992) and to provide comprehensive information on AASF No. 3 for incorporation with information contained in that previous assessment for the entirety of HAA.

  18. 77 FR 13009 - Regulation of Fuels and Fuel Additives: Identification of Additional Qualifying Renewable Fuel...

    Science.gov (United States)

    2012-03-05

    ... AGENCY 40 CFR Part 80 RIN 2060-AR07 Regulation of Fuels and Fuel Additives: Identification of Additional Qualifying Renewable Fuel Pathways Under the Renewable Fuel Standard Program AGENCY: Environmental Protection... January 5, 2012 to amend the Renewable Fuel Standard program regulations. Because EPA received...

  19. Preliminary results on molecular modeling of asphaltenes using structure elucidation programs in conjunction with molecular simulation programs

    Energy Technology Data Exchange (ETDEWEB)

    Kowalewski, I.; Vandenbroucke, M.; Huc, A.Y.; Taylor, M.J.; Faulon, J.L. [Institut Francais du Petrole, Rueil-Malmaison (France). Division Geologie-Geochimie

    1996-01-01

    Molecular modeling using structure elucidation programs in conjunction with molecular simulation programs has been performed on asphaltene molecules, the heaviest fraction of crude oil, in order to obtain a chemical model allowing the tentative study of their physicochemical properties. Boscan asphaltenes (Venezuela) derived from a marine source rock have been analysed. The different steps of this molecular modeling are described. First, a 3-D chemical representation of Boscan asphaltene is defined from an analytical data set. Second, the results of molecular dynamic simulations indicate that only a few stable conformations are possible due to the high reticulation of the model of the asphaltene unit obtained. 42 refs., 6 figs., 9 tabs.

  20. Minimum fuel coplanar aeroassisted orbital transfer using collocation and nonlinear programming

    Science.gov (United States)

    Shi, Yun Yuan; Young, D. H.

    1991-01-01

    The fuel optimal control problem arising in coplanar orbital transfer employing aeroassisted technology is addressed. The mission involves the transfer from high energy orbit (HEO) to low energy orbit (LEO) without plane change. The basic approach here is to employ a combination of propulsive maneuvers in space and aerodynamic maneuvers in the atmosphere. The basic sequence of events for the coplanar aeroassisted HEO to LEO orbit transfer consists of three phases. In the first phase, the transfer begins with a deorbit impulse at HEO which injects the vehicle into a elliptic transfer orbit with perigee inside the atmosphere. In the second phase, the vehicle is optimally controlled by lift and drag modulation to satisfy heating constraints and to exit the atmosphere with the desired flight path angle and velocity so that the apogee of the exit orbit is the altitude of the desired LEO. Finally, the second impulse is required to circularize the orbit at LEO. The performance index is maximum final mass. Simulation results show that the coplanar aerocapture is quite different from the case where orbital plane changes are made inside the atmosphere. In the latter case, the vehicle has to penetrate deeper into the atmosphere to perform the desired orbital plane change. For the coplanar case, the vehicle needs only to penetrate the atmosphere deep enough to reduce the exit velocity so the vehicle can be captured at the desired LEO. The peak heating rates are lower and the entry corridor is wider. From the thermal protection point of view, the coplanar transfer may be desirable. Parametric studies also show the maximum peak heating rates and the entry corridor width are functions of maximum lift coefficient. The problem is solved using a direct optimization technique which uses piecewise polynomial representation for the states and controls and collocation to represent the differential equations. This converts the optimal control problem into a nonlinear programming problem

  1. Preliminary design study of a quiet, high flow fan (QHF) stage. [turbofans - quiet engine program

    Science.gov (United States)

    Walker, C. L.; Kisner, L. S.; Delaney, R. A.; Beguhn, A. A.; Frye, D. E.

    1974-01-01

    Concepts selected to reduce fan generated noise in a turbofan are presented. Near-sonic flow at the fan inlet to reduce upstream propagated noise and the use of long-chord vanes to reduce downstream noise is discussed. The near-sonic condition at the rotor inlet plane was achieved by designing for high specific mass flow and by maintaining the high flow at reduced power by variable stators and variable fan exhaust nozzle. The long-chord vanes reduce response to unsteady flow. The acoustic design showed that long-chord stators would significantly reduce turbofan source noise and that other stator design parameters have no appreciable effect on noise for the spacing and chord length of the turbofan design. Four rig flow paths studied in the aerodynamic preliminary design are discussed. Noise prediction results indicate that a turbofan powered aircraft would be under federal air regulations levels without any acoustic treatment.

  2. Fabrication of Monolithic RERTR Fuels by Hot Isostatic Pressing

    Energy Technology Data Exchange (ETDEWEB)

    Jan-Fong Jue; Blair H. Park; Curtis R. Clark; Glenn A. Moore; Dennis D. Keiser, Jr.

    2010-11-01

    The RERTR (Reduced Enrichment for Research and Test Reactors) Program is developing advanced nuclear fuels for high-power test reactors. Monolithic fuel design provides higher uranium loading than that of the traditional dispersion fuel design. Hot isostatic pressing is a promising process for low-cost batch fabrication of monolithic RERTR fuel plates for these high-power reactors. Bonding U Mo fuel foil and 6061 Al cladding by hot isostatic press bonding was successfully developed at Idaho National Laboratory. Due to the relatively high processing temperature, the interaction between fuel meat and aluminum cladding is a concern. Two different methods were employed to mitigate this effect: (1) a diffusion barrier and (2) a doping addition to the interface. Both types of fuel plates have been fabricated by hot isostatic press bonding. Preliminary results show that the direct fuel/cladding interaction during the bonding process was eliminated by introducing a thin zirconium diffusion barrier layer between the fuel and the cladding. Fuel plates were also produced and characterized with a silicon-rich interlayer between fuel and cladding. This paper reports the recent progress of this developmental effort and identifies the areas that need further attention.

  3. DETERMINING THE COMPOSITION OF HIGH TEMPERATURE COMBUSTION PRODUCTS OF FOSSIL FUEL BASED ON VARIATIONAL PRINCIPLES AND GEOMETRIC PROGRAMMING

    Directory of Open Access Journals (Sweden)

    Velibor V Vujović

    2011-01-01

    Full Text Available This paper presents the algorithm and results of a computer program for calculation of complex equilibrium composition for the high temperature fossil fuel combustion products. The method of determining the composition of high temperatures combustion products at the temperatures appearing in the open cycle MHD power generation is given. The determination of combustion product composition is based on minimization of the Gibbs free energy. The number of equations to be solved is reduced by using variational principles and a method of geometric programming and is equal to the sum of the numbers of elements and phases. A short description of the computer program for the calculation of the composition and an example of the results are also given.

  4. Spent fuel sabotage test program, characterization of aerosol dispersal : technical review and analysis supplement.

    Energy Technology Data Exchange (ETDEWEB)

    Durbin, Samuel G.; Lindgren, Eric Richard

    2009-07-01

    This project seeks to provide vital data required to assess the consequences of a terrorist attack on a spent fuel transportation cask. One such attack scenario involves the use of conical shaped charges (CSC), which are capable of damaging a spent fuel transportation cask. In the event of such an attack, the amount of radioactivity that may be released as respirable aerosols is not known with great certainty. Research to date has focused on measuring the aerosol release from single short surrogate fuel rodlets subjected to attack by a small CSC device in various aerosol chamber designs. The last series of three experiments tested surrogate fuel rodlets made with depleted uranium oxide ceramic pellets in a specially designed double chamber aerosol containment apparatus. This robust testing apparatus was designed to prevent any radioactive release and allow high level radioactive waste disposal of the entire apparatus following testing of actual spent fuel rodlets as proposed. DOE and Sandia reviews of the project to date identified a number of issues. The purpose of this supplemental report is to address and document the DOE review comments and to resolve the issues identified in the Sandia technical review.

  5. Preliminary assessment report for Camp Carroll Training Center, Installation 02045, Anchorage, Alaska. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Krokosz, M.; Sefano, J.

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Alaska Army National Guard property known as Camp Carroll Training Center, located on the Fort Richardson Army facility near Anchorage, Alaska. Preliminary assessments of federal facilities are being conducted to compile the information necessary for the completion of preremedial activities and to provide a basis for establishing, corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, types and quantities of hazardous substances used, the nature and amounts of wastes generated or stored at the facility, and potential pathways by which contamination could affect public health and the environment. The primary environmentally significant operations (ESOs) associated with the property are (1) the Alaska Air National Guard storage area behind Building S57112 (Organizational Maintenance Shop [OMS] 6); (2) the state of Alaska maintenance facility and the soil/tar-type spill north of the state of Alaska maintenance facility; (3) the waste storage area adjacent to OMS 6; (4) the contaminated area from leaking underground storage tanks (USTs) and the oil-water separator; and (5) soil staining in the parking area at the Camp Carroll Headquarters Building. Camp Carroll appears to be in excellent condition from an environmental standpoint, and current practices are satisfactory. Argonne recommends that the Alaska Department of Military Affairs consider remediation of soil contamination associated with all storage areas, as well as reviewing the practices of other residents of the facility. Argonne also recommends that the current methods of storing waste material behind Building S57112 (OMS 6) be reviewed for alternatives.

  6. Impact of an educational program on the quality of life of patients with lymphedema: A preliminary evaluation.

    Science.gov (United States)

    Blaise, Sophie; Satger, Bernadette; Pernod, Gilles; Richaud, Cécile; Villemur, Béatrice; Carpentier, Patrick H

    2017-09-01

    We report on the preliminary evaluation of a well-designed program, Living with Lymphedema. This longitudinal cohort study assessed patients' quality of life using questionnaires. Our main objective was to evaluate the satisfaction of the patients and their adherence to the program. This was done using a specific questionnaire of satisfaction as well as by noting patients' adherence to the program (number of patients attending all three consultations). The secondary objective was to assess the effect of the program on the patient's quality of life. The assessment criteria were the evolution of the Medical Outcomes Study 36-Item Short Form Health Survey and EuroQol questionnaire scores between the first (C1) and third (C3) consultations. The Living with Lymphedema program targeted all patients with lymphedema in the Grenoble (France) conurbation and within the GRANTED health care network that includes vascular medicine specialists, primary care physicians, physical therapists, and dietitians in the Alpine region of France. All studied patients were ambulatory patients. The GRANTED network took care only of the educational aspect of the disease. All patients with primary or secondary lymphedema were offered the Living with Lymphedema program, whatever their age and the location of the lymphedema (upper or lower limbs). The collection of patient data conformed to the ethical and administrative regulations of the regional health authority. Grenoble Institutional Review Board (CPP Sud-Est V; No. 5891) approval for the study was specifically obtained for this evaluation on December 24, 2012. The program was built around one-to-one consultations, group workshops, and more specialized appointments. It was complementary to the routine medical care received by the patient (not evaluated in this study). It proposed three individual "educational" consultations, seven group workshops, and two specialized consultations with a dietitian. All the consultations or workshops were

  7. “Getting Ready for School:” A Preliminary Evaluation of a Parent-Focused School-Readiness Program

    Directory of Open Access Journals (Sweden)

    Kimberly G. Noble

    2012-01-01

    Full Text Available Children from disadvantaged backgrounds tend to start school with fewer school readiness skills than their more advantaged peers. Emergent literacy and math skills play an important role in this gap. The family is essential in helping children build these skills, and the active involvement of families is crucial to the success of any intervention for young children. The Getting Ready for School (GRS program is a parent-focused curriculum designed to help parents equip their children with the skills and enthusiasm necessary for learning when they start school. Parents meet in weekly workshops led by a trained facilitator and implement the curriculum at home with their children. The objective of this pilot study was to assess the promise of the GRS intervention in children participating in an urban Head Start program and to explore parents' responses to the intervention. We hypothesized that participation in GRS would improve school readiness in literacy and math skills, relative to participation in business-as-usual Head Start. Four Head Start classrooms (two randomly selected “intervention” and two “comparison” classrooms participated in this study. Preliminary analyses suggest that GRS improves school readiness over and above a Head Start-as-usual experience. Implications for early childhood programs and policies are discussed.

  8. An economic evaluation of Columbia River anadromous fish programs: A preliminary study

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This paper evaluates the economics of the Columbia River anadromous fish programs. The paper begins with a description of the Columbia River watershed and discusses...

  9. Acceleration risk in student fighter pilots: preliminary analysis of a management program.

    Science.gov (United States)

    Galvagno, Samuel M; Massa, Thomas V; Price, Scott C

    2004-12-01

    Despite advances in G-protection, F-16 student pilots continue to demonstrate G-performance inadequacies. The G-Risk Indicator Management (GRIM) Program was introduced at Luke Air Force Base in 2000 to facilitate early detection of G-related problems and to aid in the establishment of tailored ground training programs designed to enhance a student's performance under G. Assessment of anthropomorphic data, previous G-performance, anaerobic fitness, and centrifuge qualification scores comprise the initial assessment in the GRIM Program. Observations from these assessments are used to qualitatively determine the level of risk for the student. In the absence of any historical controls, no conclusions could be drawn with regards to the overall efficiency of the GRIM program. Significant differences were found between groups for anaerobic test scores, centrifuge scores, and gradebook comments. The results from this non-experimental study suggest the need for future studies to better determine the validity of G-risk indicators.

  10. Preliminary examination of a couple-based eating disorder prevention program.

    Science.gov (United States)

    Ramirez, Ana L; Perez, Marisol; Taylor, Aaron

    2012-06-01

    The purpose of the current study was to investigate a new dissonance-based prevention program that is based on the dual pathway model of eating disorders within the context of an individual's romantic relationship. A total of 209 dating couples participated in a couple-based prevention program or an assessment-only condition and completed measures of body dissatisfaction, thin-ideal internalization, disordered eating, negative affect, and relationship satisfaction at two time points (approximately one week apart) and approximately half of the sample completed 1-month follow-up measures. The prevention program significantly reduced several key risk factors for eating disorders such as environmental pressures to be thin, internalization of the thin and athletic ideals, state body dissatisfaction, and actual-ideal body discrepancy. Initial support was found for the inclusion of couples in eating disorder prevention programs as a successful way of addressing the thin ideal and its detrimental effects for women.

  11. HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1976. [Graphite and fuel irradiations; fission product release

    Energy Technology Data Exchange (ETDEWEB)

    1976-12-27

    The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and the data are presented in tables, graphs, and photographs.

  12. HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1977. [Graphite and fuel irradiation; fission product release

    Energy Technology Data Exchange (ETDEWEB)

    1977-09-01

    The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and data are presented.

  13. Early detection of ovarian cancer: preliminary results of the Yale Early Detection Program.

    OpenAIRE

    Schwartz, P. E.; Chambers, J. T.; Taylor, K. J.; Pellerito, J.; Hammers, L.; Cole, L. A.; Yang-Feng, T L; Smith, P; Mayne, S T; Makuch, R.

    1991-01-01

    Eighty-four women at high risk for ovarian cancer by having first-degree relatives with epithelial ovarian cancer participated in a newly established, early ovarian cancer detection program at Yale University. Participants were to be evaluated with physical examinations and circulating tumor markers at entry and every six months thereafter. Endovaginal ultrasound and color Doppler flow studies were to be performed at three and nine months following entry into the program. In addition, women w...

  14. A Cybernetic Approach to Acquisition System Program Office Management: Preliminary Concepts and Procedures

    Science.gov (United States)

    1990-09-01

    of Eliyahu Goldratt , to the USAF acquisition System Program Office (SPO). An extensive review of the literature was conducted, and the theories of...Harvard Business School Press, 1988. 11. Goldratt . Eliyahu M. and Jeff Fox. The Goal. Crouton-on-Hudson NY: North River Press, 1986. 12. Goldratt ...analysis espoused by Stafford Beer, in concert with the Theory of Constraints of Eliyahu Goldratt , to the USAF acquisition System Program Office (SPO). Ai

  15. THE DYNAMIC STOCHASTIC LINEAR PROGRAMMING MODEL FOR MANAGEMENT IN THE CONSUMPTION OF FUEL IN FLEX

    Directory of Open Access Journals (Sweden)

    Paulo Cesar Chagas Rodrigues

    2012-07-01

    Full Text Available From the amount invested in fuel prices, the rate of road that owners of vehicles powered by combustion need to run within the city and on the roads in the region, began a study in order to allow a better definition as to the cost of supply of vehicle with Ethanol or gasoline. And to analyze the equation that the government, through Petrobras announces in the media, because it is mentioned that to obtain the lowest cost when the supply should divide the value of a liter of Ethanol Gasoline for that case stay above 0.70 is the ideal fuel to petrol and vice versa.

  16. Systems management support for ERCDC study of undergrounding and berm containment. Interim report. Preliminary program assessment and follow-on program development

    Energy Technology Data Exchange (ETDEWEB)

    1977-08-01

    Interim results of a study being conducted with respect to the technological aspects of the costs and benefits of underground nuclear power plant construction in direct support of the California Energy Commission's legislative mandate in this area are presented. The program was directed towards problem scoping, methodology evaluation, program definition and planning for subsequent, more detailed investigations of underground facility designs and their potential advantages and disadvantages. The material presented describes the results of (a) systems analyses which were conducted to determine logical requirements for determination of those elements of a nuclear power plant which should be constructed underground; (b) bounding estimates of incremental plant costs for a variety of underground concepts; (c) applicable prior experience in underground facility design and construction which could be used to identify potential sources of strength and weaknessees of underground nuclear power plants; (d) estimates of seismic environments for underground construction in California; (e) preliminary descriptions of underground reactor accident scenarios; (f) bounding estimates of the consequences of such accidents, in terms of comparisons of relative emissions of radioactivity with respect to similar accidents for surface-sited nuclear power plants and (g) results of analyses of several other important technological aspects of the problem. A description is also provided of the program development work performed to provide planning and criteria for subsequent investigations to determine: (a) definitive underground nuclear power plant designs and costs, and (b) estimates of accident consequences in underground nuclear power plants.

  17. Systems management support for ERCDC study of undergrounding and berm containment. Interim report. Preliminary program assessment and follow-on program development

    Energy Technology Data Exchange (ETDEWEB)

    1977-08-01

    Interim results of a study being conducted with respect to the technological aspects of the costs and benefits of underground nuclear power plant construction in direct support of the California Energy Commission's legislative mandate in this area are presented. The program was directed towards problem scoping, methodology evaluation, program definition and planning for subsequent, more detailed investigations of underground facility designs and their potential advantages and disadvantages. The material presented describes the results of (a) systems analyses which were conducted to determine logical requirements for determination of those elements of a nuclear power plant which should be constructed underground; (b) bounding estimates of incremental plant costs for a variety of underground concepts; (c) applicable prior experience in underground facility design and construction which could be used to identify potential sources of strength and weaknessees of underground nuclear power plants; (d) estimates of seismic environments for underground construction in California; (e) preliminary descriptions of underground reactor accident scenarios; (f) bounding estimates of the consequences of such accidents, in terms of comparisons of relative emissions of radioactivity with respect to similar accidents for surface-sited nuclear power plants and (g) results of analyses of several other important technological aspects of the problem. A description is also provided of the program development work performed to provide planning and criteria for subsequent investigations to determine: (a) definitive underground nuclear power plant designs and costs, and (b) estimates of accident consequences in underground nuclear power plants.

  18. ISLAMIC MICROFINANCE AND POVERTY ALLEVIATION PROGRAM: PRELIMINARY RESEARCH FINDINGS FROM INDONESIA

    Directory of Open Access Journals (Sweden)

    Yasushi Suzuki

    2016-06-01

    Full Text Available Poverty should be defined, measured, and scrutinized its root causes from a multi-dimension perspectives. Therefore, in designing and implementation of poverty alleviation program, it should consider economic factors, social and political contexts surrounding the poor. Sen (1982; 1999 views poverty as a multifaceted world and ethical dimension essentially should be placed underpinning it as a vital economic problem. The paper takes the stance that the poor themselves have potential capacity to alleviate their condition in resolving poverty trap. Community development program is one of the strategies to deal with the poverty problem. Islamic microfinance can play an important role in combating poverty dilemma especially in Muslim majority population communities. Through the approach proposed by Bigg and Satterthwaite (2005 with strengthening local organizations and community development programs, Islamic microfinance should engage a strategic partnership with the Masjid and Islamic charity institutions (zakat and waqf organization. This strategic alliance will result more integrated programs and also capacity building of the institutions involved. This paper aims to contribute a grass root model in the purpose of combating poverty in the framework of Islamic economic system. =========================================== Kemiskinan harus didefinisikan, diukur, dan diteliti akar penyebabnya dari berbagai perspektif. Oleh karena itu, dalam merancang dan mengimplementasikan program pengentasan kemiskinan, faktor-faktor ekonomi, konteks sosial dan politik yang mengelilingi kemiskinan juga harus dipertimbangkan. Sen (1982; 1999 memandang kemiskinan sebagai sebuah dunia yang kompleks, dan dimensi dasar etika harus ditempatkan sebagai sebuah masalah ekonomi yang vital. Peneliti sendiri dalam hal ini berpandangan bahwa orang-orang miskin pada dasarnya punya kapasitas yang memadai untuk keluar dari garis kemiskinan. Salah satunya adalah dengan program

  19. Preliminary Assessment of the Hanford Tank Waste Feed Acceptance and Product Qualification Programs

    Energy Technology Data Exchange (ETDEWEB)

    Herman, C. C.; Adamson, Duane J.; Herman, D. T.; Peeler, David K.; Poirier, Micheal R.; Reboul, S. H.; Stone, M. E.; Peterson, Reid A.; Chun, Jaehun; Fort, James A.; Vienna, John D.; Wells, Beric E.

    2013-04-01

    The U.S. Department of Energy Office of Environmental Management (EM) is engaging the national laboratories to provide the scientific and technological rigor to support EM program and project planning, technology development and deployment, project execution, and assessment of program outcomes. As an early demonstration of this new responsibility, Savannah River National Laboratory (SRNL) and Pacific Northwest National Laboratory (PNNL) have been chartered to implement a science and technology program addressing Hanford Tank waste feed acceptance and product qualification. As a first step, the laboratories examined the technical risks and uncertainties associated with the planned waste feed acceptance and qualification testing for Hanford tank wastes. Science and technology gaps were identified for work associated with 1) feed criteria development with emphasis on identifying the feed properties and the process requirements, 2) the Tank Waste Treatment and Immobilization Plant (WTP) process qualification program, and 3) the WTP HLW glass product qualification program. Opportunities for streamlining the accetpance and qualification programs were also considered in the gap assessment. Technical approaches to address the science and technology gaps and/or implement the opportunities were identified. These approaches will be further refined and developed as strong integrated teams of researchers from national laboratories, contractors, industry, and academia are brought together to provide the best science and technology solutions. Pursuing the identified approaches will have immediate and long-term benefits to DOE in reducing risks and uncertainties associated with tank waste removal and preparation, transfers from the tank farm to the WTP, processing within the WTP Pretreatment Facility, and in producing qualified HLW glass products. Additionally, implementation of the identified opportunities provides the potential for long-term cost savings given the anticipated

  20. Game-Based Cognitive-Behavioral Therapy (GB-CBT) Group Program for Children Who Have Experienced Sexual Abuse: A Preliminary Investigation

    Science.gov (United States)

    Misurell, Justin R.; Springer, Craig; Tryon, Warren W.

    2011-01-01

    This preliminary investigation examined the efficacy of a game-based cognitive-behavioral therapy group program for elementary school-aged children who have experienced sexual abuse. Treatment aimed to improve: (a) internalizing symptoms, (b) externalizing behaviors, (c) sexually inappropriate behaviors, (d) social skills deficits, (e) self-esteem…

  1. Acceptability and Preliminary Outcomes of a Peer-Led Depression Prevention Intervention for African American Adolescents and Young Adults in Employment Training Programs

    Science.gov (United States)

    Tandon, Darius; Mendelson, Tamar; Mance, GiShawn

    2011-01-01

    This study examines the acceptability and preliminary outcomes from an open trial of a depression prevention intervention for low-income African American adolescents and young adults in employment training programs. The sample (N=42) consisted of predominately African American adolescents and young adults (mean age=19.1) exhibiting subclinical…

  2. Game-Based Cognitive-Behavioral Therapy (GB-CBT) Group Program for Children Who Have Experienced Sexual Abuse: A Preliminary Investigation

    Science.gov (United States)

    Misurell, Justin R.; Springer, Craig; Tryon, Warren W.

    2011-01-01

    This preliminary investigation examined the efficacy of a game-based cognitive-behavioral therapy group program for elementary school-aged children who have experienced sexual abuse. Treatment aimed to improve: (a) internalizing symptoms, (b) externalizing behaviors, (c) sexually inappropriate behaviors, (d) social skills deficits, (e) self-esteem…

  3. Smoking cessation intervention within the framework of a lung cancer screening program: preliminary results and clinical perspectives from the "Cosmos-II" Trial.

    Science.gov (United States)

    Filippo, Lococo; Principe, Rosastella; Cesario, Alfredo; Apolone, Giovanni; Carleo, Francesco; Ialongo, Pasquale; Veronesi, Giulia; Cardillo, Giuseppe

    2015-02-01

    Data coming from the literature investigating the effectiveness and interaction between smoking cessation (SC) and lung cancer screening (LCScr) are still sparse and inconsistent. Herein, we report the preliminary results from the ongoing lung cancer screening trial ("Cosmos-II") focusing our analysis on the inter-relationship between the SC program and the LCScr.

  4. Seventeenth symposium on biotechnology for fuels and chemicals. Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    This volume contains the abstracts of oral and poster presentations made at the Seventeenth Symposium on Biotechnology for Fuels and Chemicals. Session titles include Thermal, Chemical, and Biological Processing; Applied Biological Research; Bioprocessing Research; Special Topics Discussion Groups; Process Economics and Commercialization; and Environmental Biotechnology.

  5. 78 FR 71731 - 2014 Standards for the Renewable Fuel Standard Program

    Science.gov (United States)

    2013-11-29

    ... production capacities, company production plans, the progress made in 2013, expected production distribution... ranges for each of the individual companies and a production probability distribution within the range... involved with the production, distribution, and sale of transportation fuels, including gasoline and...

  6. CEA and AREVA HTR fuel particles manufacturing and characterization R and D Program

    Energy Technology Data Exchange (ETDEWEB)

    Charollais, F.; Perez, M.; Fonquernie, S.; Ablitzer, C.; Duhart, A.; Perrais, C.; Dugne, O.; Guillermier, P.; Harbonnier, G

    2004-07-01

    Worldwide, renewal of interest for High Temperature Reactors (HTR) moderated by graphite, using helium gas as coolant is due to the possibility offered by HTR technology to build small competitive modular units (100-300 MWe) and to produce high temperature gas required for hydrogen production or heat production. In this context, Commissariat a l'Energie Atomique (CEA) supported by AREVA, conducts R and D projects on HTR, which one is the mastering of the UO{sub 2} TRISO fuel fabrication technology including innovating prospects. The first step of the work is to recover fabrication know-how and to improve fabrication processes (for preparing the erection of a fuel pilot manufacture line of HTR particles). The second step will be the manufacturing of HTR fuel elements in purpose of irradiation tests. This publication deals with the know-how recovery and improved processes of UO{sub 2} TRISO manufacture, i.e. kernel and coatings manufacturing, the development of innovative characterization methods, a modelling approach of CVD processes and the status of the future laboratory manufacture line. Alternative fuel designs are also investigated, for instance the way of manufacturing UCO and UC{sub x} kernels with higher refractory coating material such as ZrC. (authors)

  7. Manual of phosphoric acid fuel cell power plant cost model and computer program

    Science.gov (United States)

    Lu, C. Y.; Alkasab, K. A.

    1984-01-01

    Cost analysis of phosphoric acid fuel cell power plant includes two parts: a method for estimation of system capital costs, and an economic analysis which determines the levelized annual cost of operating the system used in the capital cost estimation. A FORTRAN computer has been developed for this cost analysis.

  8. 75 FR 43522 - Notice of Supplemental Determination for Renewable Fuels Produced Under the Final RFS2 Program...

    Science.gov (United States)

    2010-07-26

    ... of fuel pathways such as ethanol from corn starch or biodiesel from soybean oil our reference case... transportation fuels, including gasoline and diesel fuel or renewable fuels such as ethanol and biodiesel... assumed that the co- product glycerin would displace residual oil as a fuel source on an energy...

  9. [Implementation of a psychological support program for children with cancer in Poland. Preliminary report].

    Science.gov (United States)

    Samardakiewicz, M; Kowalczyk, J; Antonowicz, M; Budzińska-Skowronska, U; Boguslawska-Jaworska, J; Mazurowa, M; Mazur, A; Rokicka-Milewska, R; Bukowska-Posadzy, A; Kołecki, P; Maroczkaniec, E; Slazak, D; Sońta-Jakimczyk, D; Szweda, E; Armata, J; Budziński, W; Balcerska, A

    2000-01-01

    Intensive chemotherapy programme in children with cancer may result in psychological mal adjustment. Treatment facilities as well as psychological support are of great importance to minimize these side effects. In 1998 the programme of psychological support was introduced in 7 Polish paediatric haematology / oncology centres. Psychological adjustment of patients treated in each centre was examined 5 yrs after the termination of therapy. At the same time children with new diagnosis of cancer were monitored psychologically along with the psychological support programme. Psychological status of each patient was examined with the following tests: Cattell's questionnaires (CPQ, HSPQ), Manifest Anxiety Scale, Spielberger's inventories (STAI, STAIC), Wechsler Intelligence Scale. The programme of psychological support was based on guidelines of SIOP Psychosocial Committee and included such elements as informing about diagnosis and treatment, explaining any doubt, maintaining an open communication, educational care in the periods of treatment, encouraging to activity even during periods of discomfort. The analysis showed that most of the participating centres could only provide some elements of the support programme. The main problem was to convince medical staff to inform children on diagnosis and treatment plans. Preliminary results of the study indicate that full psychological support for children with cancer and their families from the beginning of therapy can result in improvement in psychological adjustment. During the ensuing period, patients and their parents appreciate the possibilities to contact a psychologist.

  10. Fuel flexible fuel injector

    Science.gov (United States)

    Tuthill, Richard S; Davis, Dustin W; Dai, Zhongtao

    2015-02-03

    A disclosed fuel injector provides mixing of fuel with airflow by surrounding a swirled fuel flow with first and second swirled airflows that ensures mixing prior to or upon entering the combustion chamber. Fuel tubes produce a central fuel flow along with a central airflow through a plurality of openings to generate the high velocity fuel/air mixture along the axis of the fuel injector in addition to the swirled fuel/air mixture.

  11. Preliminary Effects of the Incredible Years Teacher Training Program on Classroom Management Skills

    Science.gov (United States)

    Murray, Desiree W.; Murr, Natalie; Rabiner, David L.

    2012-01-01

    The overall purpose of this IES-funded Goal 3 study, now entering its third year, is to evaluate the efficacy of Incredible Years Teacher program (IYT) for improving K-2 students' academic achievement, attention, and social-emotional competence. The authors will also examine the extent to which classroom behavior mediates the relationship between…

  12. Nursing Student Performance, 1986-1993: Preliminary Findings. Program Evaluation PE93-1.

    Science.gov (United States)

    Boughan, Karl

    A study was conducted at Prince George's Community College (PGCC), in Maryland, to evaluate nursing student performance from point of admission to the taking of the National Council Licensure Examination (NCLEX). A sample of 853 students who enrolled in the nursing program entry course between fall 1986 and spring 1992 were surveyed to determine…

  13. A Preliminary Outcome Study of an Outpatient Treatment Program for Gamblers.

    Science.gov (United States)

    Blackman, Sheldon; And Others

    The Gamblers Treatment Clinic (GTC) opened in 1982 as a New York State Office of Mental Health Demonstration Program. The basic premise of the GTC is that excessive gambling is a disorder of impulse control. Treatment, conducted in the community in a time-limited fashion, attempts to uncover the underlying dynamics that precipitate disorders of…

  14. The "RAPID" Cognitive-Behavioral Therapy Program for Inattentive Children: Preliminary Findings

    Science.gov (United States)

    Young, Susan

    2013-01-01

    Objective: The objectives of the current study were to ascertain feasibility and acceptability of directly delivering a cognitive-behavioral therapy (CBT) group intervention for inattentive children in a school setting, to examine the reliability of the RATE-C Questionnaires that accompany the program, and to determine whether they can be used to…

  15. English Program Review at Coastline Community College, Fountain Valley, California. [A Preliminary Report, October 1988.

    Science.gov (United States)

    Yglesias, Kenneth D., Comp.; Fry, Marilyn, Comp.

    Prepared as part of the program review process at California's Coastline Community College (CCC), this report describes and evaluates CCC's English Department, highlighting problems and successes from 1976 to 1987. Part I offers a narrative account of: (1) the changes that took place in the department between 1976 and 1987, focusing on early…

  16. Preliminary evaluation of a multidisciplinary pain management program for children and adolescents with chronic musculoskeletal pain

    NARCIS (Netherlands)

    De Blecourt, A. C. E.; Schiphorst Preuper, H. R.; Van der Schans, C. P.; Groothoff, J. W.; Reneman, M. F.

    2008-01-01

    Purpose. To describe the outcome of a multidisciplinary pain management program for children and adolescents with chronic musculoskeletal pain. Methods. Study design: exploratory retrospective cohort study. The study sample consisted of a cohort of 70 children and adolescents ( age: 8 - 21 years) wi

  17. Preliminary Examination of Adolescent Spending in a Contingency Management-Based Smoking-Cessation Program

    Science.gov (United States)

    Cavallo, Dana A.; Nich, Charla; Schepis, Ty S.; Smith, Anne E.; Liss, Thomas B.; McFetridge, Amanda K.; Krishnan-Sarin, Suchitra

    2010-01-01

    Contingency management (CM) utilizing monetary incentives is efficacious in enhancing abstinence in an adolescent smoking-cessation program, but how adolescents spend their money has not been examined. We assessed spending habits of 38 adolescent smokers in a CM-based smoking-cessation project prior to quitting and during treatment using a…

  18. Preliminary evaluation of a multidisciplinary pain management program for children and adolescents with chronic musculoskeletal pain

    NARCIS (Netherlands)

    De Blecourt, A. C. E.; Schiphorst Preuper, H. R.; Van der Schans, C. P.; Groothoff, J. W.; Reneman, M. F.

    2008-01-01

    Purpose. To describe the outcome of a multidisciplinary pain management program for children and adolescents with chronic musculoskeletal pain. Methods. Study design: exploratory retrospective cohort study. The study sample consisted of a cohort of 70 children and adolescents ( age: 8 - 21 years) wi

  19. Assessment of Primary Representational Systems with Neurolinguistic Programming: Examination of Preliminary Literature.

    Science.gov (United States)

    Dorn, Fred J.; And Others

    1983-01-01

    Reviews the inconsistent findings of studies on neurolinguistic programing and recommends some areas that should be examined to verify various claims. Discusses methods of assessing client's primary representational systems, including predicate usage and eye movements, and suggests that more reliable methods of assessing PRS must be found. (JAC)

  20. Compressed air energy storage preliminary design and site development program in an aquifer. Turbomachinery design

    Science.gov (United States)

    Berman, P. A.; Bonk, J. S.; Kobett, W. F.; Kosanovich, N. S.; Long, L. J.; Marinacci, D. J.

    1981-07-01

    Compressed Air Energy Storage (CAES) is a means of storing electrical energy generated by utility baseload power plants during off-peak hours. This stored energy will be used during periods of high demand. Compressed Air Energy Storage (CAES) system uses off-peak power from an electrical grid to operate an electric dynamo. This is used as a motor to drive a compressor train that charges atmospheric air at elevated pressure into an underground aquifer. During high electrical demand periods, the pressurized air is withdrawn from the aquifer and channeled to combustors where it is heated and then expanded through a combustion turbine. The turbine drives the electric dynamo, being operated as a generator, to supply power back to the grid. Since the CAES turbine train is divorced from the compressor during power generation, the net output power is about three times that of a normal combustion turbine. Although the fuel consumption rate is nearly the same, the heat rate is much lower.

  1. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Y.C. [Square Y Consultants, Orchard Park, NY (US); Chen, S.Y.; Biwer, B.M.; LePoire, D.J. [Argonne National Lab., IL (US)

    1995-11-01

    This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows{trademark} environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident.

  2. A mindfulness-based program for improving quality of life among hematopoietic stem cell transplantation survivors: feasibility and preliminary findings.

    Science.gov (United States)

    Grossman, Paul; Zwahlen, Diana; Halter, Jorg P; Passweg, Jakob R; Steiner, Claudia; Kiss, Alexander

    2015-04-01

    Health-related quality of life (HRQoL) is often substantially reduced among individuals who have undergone hematopoietic stem cell transplantation (HSCT), and incidences of depression, fatigue, and anxiety are elevated. We examined effects of a mindfulness-based intervention (MBI) compared to psycho-oncological telephone consultation upon HRQoL, depression, anxiety, and fatigue among HSCT survivors. Sixty-two medically stable patients participated in the study; they had completed HSCT ≥6 months previously. Thirty-two were randomly assigned to intervention arms, and 30 were offered their treatment preference. MBI consisted of a structured 8-week program of mindfulness training. Assessments were made at baseline, post-intervention and 3 months follow-up. Primary outcome was HRQoL. Depression, fatigue, anxiety, and personal goal attainment were secondary measures. Non-completion of interventions was low in both groups (9 %, MBI; 7 % control). Employing intention-to-treat analysis, MBI, compared with comparison procedure, improved HRQoL and reduced depression and anxiety at post-intervention (p's benefits were modest. These findings demonstrate broad feasibility and acceptance of, as well as satisfaction and adherence with, a program of mindfulness training for HSCT survivors; findings also suggest improved HRQoL and well-being as a consequence of MBI. Nevertheless, this is a preliminary study; a larger trial with more prolonged intervention phase is warranted.

  3. Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Date Report No. 3: Diesel Fuel Sulfur Effects on Particulate Matter Emissions

    Energy Technology Data Exchange (ETDEWEB)

    DOE; ORNL; NREL; EMA; MECA

    1999-11-15

    The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NO{sub x}) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This interim report covers the effects of diesel fuel sulfur level on particulate matter emissions for four technologies.

  4. Fuel performance improvement program: description and characterization of HBWR Series H-2, H-3, and H-4 test rods

    Energy Technology Data Exchange (ETDEWEB)

    Guenther, R.J.; Barner, J.O.; Welty, R.K.

    1980-03-01

    The fabrication process and as-built characteristics of the HBWR Series H-2 and H-3 test rods, as well as the three packed-particle (sphere-pac) rods in HBWR Series H-4 are described. The HBWR Series H-2, H-3, and H-4 tests are part of the irradiation test program of the Fuel Performance Improvement Program. Fifteen rods were fabricated for the three test series. Rod designs include: (1) a reference dished pellet design incorporating chamfered edges, (2) a chamfered, annular pellet design combined with graphite-coated cladding, and (3) a sphere-pac design. Both the annular-coated and sphere-pac designs include internal pressurization using helium.

  5. Results of Ponseti Brasil Program: Multicentric Study in 1621 Feet: Preliminary Results.

    Science.gov (United States)

    Nogueira, Monica P; Queiroz, Ana C D B F; Melanda, Alessandro G; Tedesco, Ana P; Brandão, Antonio L G; Beling, Claudio; Violante, Francisco H; Brandão, Gilberto F; Ferreira, Laura F A; Brambila, Leandro S; Leite, Leopoldina M; Zabeu, Jose L; Kim, Jung H; Fernandes, Kalyana E; Arima, Marcia A S; Aguilar, Maria D P Q; Farias Filho, Orlando C D; Oliveira Filho, Oscar B D A; Pinho, Solange D S; Moulin, Paulo; Volpi, Reinaldo; Fox, Mark; Greenwald, Miles F; Lyle, Brandon; Morcuende, Jose A

    The Ponseti method has been shown to be the most effective treatment for congenital clubfoot. The current challenge is to establish sustainable national clubfoot treatment programs that utilize the Ponseti method and integrate it within a nation's governmental health system. The Brazilian Ponseti Program (Programa Ponseti Brasil) has increased awareness of the utility of the Ponseti method and has trained >500 Brazilian orthopaedic surgeons in it. A group of 18 of those surgeons had been able to reproduce the Ponseti clubfoot treatment, and compiled their initial results through structured spreadsheet. The study compiled 1040 patients for a total of 1621 feet. The average follow-up time was 2.3 years with an average correction time of approximately 3 months. Patients required an average of 6.40 casts to achieve correction. This study demonstrates that good initial correction rates are reproducible after training; from 1040 patients only 1.4% required a posteromedial release. Level IV.

  6. Site Study Plan for Aesthetics, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

    Energy Technology Data Exchange (ETDEWEB)

    1987-06-01

    The Aesthetic Site Study Plan describes a field program consisting of identification of the visually affected area; determination of scenic quality, visual sensitivity, and visual management classes of the site and vicinity; and analysis of the level of visual contrast that would be created by the project. Field ratings of scenic quality, visual sensitivity, and visual contrast will be supplemented by a public perception survey designed to incorporate the views of the public. This plan describes the need for the study, the study design, data management and use, schedule for proposed activities, and quality assurance program. This study will provide data needed to satisfy requirements contained in, or derived from, SRPO Requirement Document (SRP-RD). 35 refs., 6 figs., 2 tabs.

  7. Early detection of ovarian cancer: preliminary results of the Yale Early Detection Program.

    Science.gov (United States)

    Schwartz, P. E.; Chambers, J. T.; Taylor, K. J.; Pellerito, J.; Hammers, L.; Cole, L. A.; Yang-Feng, T. L.; Smith, P.; Mayne, S. T.; Makuch, R.

    1991-01-01

    Eighty-four women at high risk for ovarian cancer by having first-degree relatives with epithelial ovarian cancer participated in a newly established, early ovarian cancer detection program at Yale University. Participants were to be evaluated with physical examinations and circulating tumor markers at entry and every six months thereafter. Endovaginal ultrasound and color Doppler flow studies were to be performed at three and nine months following entry into the program. In addition, women were encouraged to follow American Cancer Society guidelines for mammography. Stool was checked for occult blood. Endometrial sampling was offered to post-menopausal women. No participant has developed an ovarian cancer since entering the program. One woman has been diagnosed to have breast cancer. False-positive levels of circulating tumor markers (CA 125, 4/84 [4.8 percent]; lipid-associated sialic acid in plasma, 13/84 [15.5 percent]; NB/70K, 4/84 [4.8 percent]; and urinary gonadotropin fragment, 1/65 [1.5 percent]) were observed on entry into the program. Low resistive indices (less than 0.5) were documented in 8/91 (8.8 percent) ovaries studied by the color Doppler flow technique. One participant underwent a laparotomy based on a false-positive endovaginal ultrasound examination. Tests now being employed in community practice have a high likelihood of being associated with false-positive results. Therapeutic interventions based on isolated abnormal tumor markers or ultrasound studies obtained from women with family histories of ovarian cancer may lead to inappropriate surgery. It is necessary for cancer centers to develop expertise in ovarian cancer detection techniques to advise physicians in their geographic areas appropriately about the significance of the abnormal screening test. PMID:1810101

  8. Empirical Tests and Preliminary Results with the Krakatoa Tool for Full Static Program Verification

    Directory of Open Access Journals (Sweden)

    Ramírez-de León Edgar Darío

    2014-10-01

    Full Text Available XJML (Ramírez et al., 2012 is a modular external platform for Verification and Validation of Java classes using the Java Modeling Language (JML through contracts written in XML. One problem faced in the XJML development was how to integrate Full Static Program Verification (FSPV. This paper presents the experiments and results that allowed us to define what tool to embed in XJML to execute FSPV.

  9. Appendix B: Hydrogen, Fuel Cells, and Infrastructure Technologies Program inputs for FY 2008 benefits estimates

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2009-01-18

    Document summarizes the results of the benefits analysis of EERE’s programs, as described in the FY 2008 Budget Request. EERE estimates benefits for its overall portfolio and nine Research, Development, Demonstration, and Deployment (RD3) programs.

  10. A telerehabilitation program improves postural control in multiple sclerosis patients: a Spanish preliminary study.

    Science.gov (United States)

    Ortiz-Gutiérrez, Rosa; Cano-de-la-Cuerda, Roberto; Galán-del-Río, Fernando; Alguacil-Diego, Isabel María; Palacios-Ceña, Domingo; Miangolarra-Page, Juan Carlos

    2013-10-31

    Postural control disorders are among the most frequent motor disorder symptoms associated with multiple sclerosis. This study aims to demonstrate the potential improvements in postural control among patients with multiple sclerosis who complete a telerehabilitation program that represents a feasible alternative to physical therapy for situations in which conventional treatment is not available. Fifty patients were recruited. Control group (n = 25) received physiotherapy treatment twice a week (40 min per session). Experimental group (n = 25) received monitored telerehabilitation treatment via videoconference using the Xbox 360® and Kinect console. Experimental group attended 40 sessions, four sessions per week (20 min per session).The treatment schedule lasted 10 weeks for both groups. A computerized dynamic posturography (Sensory Organization Test) was used to evaluate all patients at baseline and at the end of the treatment protocol. Results showed an improvement over general balance in both groups. Visual preference and the contribution of vestibular information yielded significant differences in the experimental group. Our results demonstrated that a telerehabilitation program based on a virtual reality system allows one to optimize the sensory information processing and integration systems necessary to maintain the balance and postural control of people with multiple sclerosis. We suggest that our virtual reality program enables anticipatory PC and response mechanisms and might serve as a successful therapeutic alternative in situations in which conventional therapy is not readily available.

  11. A Telerehabilitation Program Improves Postural Control in Multiple Sclerosis Patients: A Spanish Preliminary Study

    Directory of Open Access Journals (Sweden)

    Rosa Ortiz-Gutiérrez

    2013-10-01

    Full Text Available Postural control disorders are among the most frequent motor disorder symptoms associated with multiple sclerosis. This study aims to demonstrate the potential improvements in postural control among patients with multiple sclerosis who complete a telerehabilitation program that represents a feasible alternative to physical therapy for situations in which conventional treatment is not available. Fifty patients were recruited. Control group (n = 25 received physiotherapy treatment twice a week (40 min per session. Experimental group (n = 25 received monitored telerehabilitation treatment via videoconference using the Xbox 360® and Kinect console. Experimental group attended 40 sessions, four sessions per week (20 min per session.The treatment schedule lasted 10 weeks for both groups. A computerized dynamic posturography (Sensory Organization Test was used to evaluate all patients at baseline and at the end of the treatment protocol. Results showed an improvement over general balance in both groups. Visual preference and the contribution of vestibular information yielded significant differences in the experimental group. Our results demonstrated that a telerehabilitation program based on a virtual reality system allows one to optimize the sensory information processing and integration systems necessary to maintain the balance and postural control of people with multiple sclerosis. We suggest that our virtual reality program enables anticipatory PC and response mechanisms and might serve as a successful therapeutic alternative in situations in which conventional therapy is not readily available.

  12. Evaluation of Storage for Transportation Equipment, Unfueled Convertors, and Fueled Convertors at the INL for the Radioisotope Power Systems Program

    Energy Technology Data Exchange (ETDEWEB)

    S. G. Johnson; K. L. Lively

    2010-05-01

    This report contains an evaluation of the storage conditions required for several key components and/or systems of the Radioisotope Power Systems (RPS) Program at the Idaho National Laboratory (INL). These components/systems (transportation equipment, i.e., type ‘B’ shipping casks and the radioisotope thermo-electric generator transportation systems (RTGTS), the unfueled convertors, i.e., multi-hundred watt (MHW) and general purpose heat source (GPHS) RTGs, and fueled convertors of several types) are currently stored in several facilities at the Materials and Fuels Complex (MFC) site. For various reasons related to competing missions, inherent growth of the RPS mission at the INL and enhanced efficiency, it is necessary to evaluate their current storage situation and recommend the approach that should be pursued going forward for storage of these vital RPS components and systems. The reasons that drive this evaluation include, but are not limited to the following: 1) conflict with other missions at the INL of higher priority, 2) increasing demands from the INL RPS Program that exceed the physical capacity of the current storage areas and 3) the ability to enhance our current capability to care for our equipment, decrease maintenance costs and increase the readiness posture of the systems.

  13. U.S. Department of Energy Hydrogen and Fuel Cells Program 2015 Annual Merit Review and Peer Evaluation Report: June 8-12, 2015, Arlington, Virginia

    Energy Technology Data Exchange (ETDEWEB)

    Popovich, Neil

    2015-10-01

    The fiscal year 2015 U.S. Department of Energy (DOE) Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Meeting (AMR), in conjunction with DOE's Vehicle Technologies Office AMR, was held from June 8-12, 2015, in Arlington, Virginia. This report is a summary of comments by AMR peer reviewers about the hydrogen and fuel cell projects funded by DOE's Office of Energy Efficiency and Renewable Energy.

  14. U.S. Department of Energy Hydrogen and Fuel Cells Program 2016 Annual Merit Review and Peer Evaluation Report: June 6-10, 2016, Washington, DC

    Energy Technology Data Exchange (ETDEWEB)

    Popovich, Neil

    2016-10-01

    The fiscal year 2016 U.S. Department of Energy (DOE) Hydrogen and Fuel Cells Program Annual Merit Review and Peer Evaluation Meeting (AMR), in conjunction with DOE's Vehicle Technologies Office AMR, was held from June 6-10, 2015, in Washington, D.C.. This report is a summary of comments by AMR peer reviewers about the hydrogen and fuel cell projects funded by DOE's Office of Energy Efficiency and Renewable Energy.

  15. Fuel Accident Condition Simulator (FACS) Furnace for Post-Irradiation Heating Tests of VHTR Fuel Compacts

    Energy Technology Data Exchange (ETDEWEB)

    Paul A Demkowicz; Paul Demkowicz; David V Laug

    2010-10-01

    Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as part of the Next Generation Nuclear Plant Fuels Development and Qualification Program. The PIE campaign will include extensive accident testing of irradiated very high temperature reactor fuel compacts to verify fission product retention characteristics at high temperatures. This work will be carried out at both the Idaho National Laboratory (INL) and the Oak Ridge National Laboratory, beginning with accident tests on irradiated fuel from the AGR-1 experiment in 2010. A new furnace system has been designed, built, and tested at INL to perform high temperature accident tests. The Fuel Accident Condition Simulator furnace system is designed to heat fuel specimens at temperatures up to 2000°C in helium while monitoring the release of volatile fission metals (e.g. Cs, Ag, Sr, Eu, and I) and fission gases (Kr, Xe). Fission gases released from the fuel to the sweep gas are monitored in real time using dual cryogenic traps fitted with high purity germanium detectors. Condensable fission products are collected on a plate attached to a water-cooled cold finger that can be exchanged periodically without interrupting the test. Analysis of fission products on the condensation plates involves dry gamma counting followed by chemical analysis of selected isotopes. This paper will describe design and operational details of the Fuel Accident Condition Simulator (FACS) furnace system, as well as preliminary system calibration results.

  16. Perception of hearing protectors by workers that participate in hearing preservation programs: a preliminary study.

    Science.gov (United States)

    Gonçalves, Cláudia Giglio de Oliveira; Lüders, Débora; Guirado, Débora Simões; Albizu, Evelyn Joice; Marques, Jair Mendes

    2015-01-01

    To evaluate and compare the workers' perception of comfort and use aspects regarding two types of hearing protectors (shell and earplug), in three units from a lumbering company, with different implantation times for Hearing Preservation Programs. This is a cross-sectional study comparing 440 workers' perception of hearing protectors, from three companies in Paraná State (Brazil), with different times for Hearing Preservation Programs. Two closed questionnaires were applied (9 and 10 questions, respectively), with a scale of answers varying from 1 to 5 (Likert's scale) regarding the perception of the comfort of hearing protectors. Then, audiometry results were analyzed. About 17.5% presented audiogram examinations with alterations. With regard to the questionnaire about the comfort perception, the importance of noise attenuation (mean of 4.25) was the most relevant aspect, followed by communication possibility (mean of 4.15). In the protector assessment, Unit A with more Hearing Preservation Program time presented better scores for both the worker's perception of important aspects regarding hearing protector and for the assessment of the used hearing protector. There was a significant difference on communication difficulty with the use of a hearing protector among workers with normal and altered audiograms (p=0.0371). With regard to the global comfort in the comparison of workers using the shell-type hearing protector with those using insert-type hearing protectors, there was no difference (p=0.2264), irrespective of the type of the unit. In general, the unit workers presented a good perception of the important aspects about the hearing protection use of both types of hearing protectors.

  17. New Approach in Fibromyalgia Exercise Program: A Preliminary Study Regarding the Effectiveness of Balance Training.

    Science.gov (United States)

    Kibar, Sibel; Yıldız, Hatice Ecem; Ay, Saime; Evcik, Deniz; Ergin, Emine Süreyya

    2015-09-01

    To determine the effectiveness of balance exercises on the functional level and quality of life (QOL) of patients with fibromyalgia syndrome (FMS) and to investigate the circumstances associated with balance disorders in FMS. Randomized controlled trial. Physical medicine and rehabilitation clinic. Patients (N=57) (age range, 18-65y) with FMS were randomly assigned into 2 groups. Group 1 was given flexibility and balance exercises for 6 weeks, whereas group 2 received only a flexibility program as the control group. Functional balance was measured by the Berg Balance Scale (BBS), and dynamic and static balance were evaluated by a kinesthetic ability trainer (KAT) device. Fall risk was assessed with the Hendrich II fall risk model. The Nottingham Health Profile, Fibromyalgia Impact Questionnaire (FIQ), and Beck Depression Inventory (BDI) were used to determine QOL and functional and depression levels, respectively. Assessments were performed at baseline and after the 6-week program. In group 1, statistically significant improvements were observed in all parameters (P.05). When comparing the 2 groups, there were significant differences in group 1 concerning the KAT static balance test (P=.017) and FIQ measurements (P=.005). In the correlation analysis, the BDI was correlated with the BBS (r=-.434) and Hendrich II results (r=.357), whereas body mass index (BMI) was correlated with the KAT static balance measurements (r=.433), BBS (r=-.285), and fall frequency (r=.328). A 6-week balance training program had a beneficial effect on the static balance and functional levels of patients with FMS. We also observed that depression deterioration was related to balance deficit and fall risk. Higher BMI was associated with balance deficit and fall frequency. Copyright © 2015 American Congress of Rehabilitation Medicine. Published by Elsevier Inc. All rights reserved.

  18. Use of Web 2.0 Social Media Platforms to Promote Community-Engaged Research Dialogs: A Preliminary Program Evaluation.

    Science.gov (United States)

    Valdez Soto, Miguel; Balls-Berry, Joyce E; Bishop, Shawn G; Aase, Lee A; Timimi, Farris K; Montori, Victor M; Patten, Christi A

    2016-09-09

    Community-engaged research is defined by the Institute of Medicine as the process of working collaboratively with groups of people affiliated by geographic proximity, special interests, or similar situations with respect to issues affecting their well-being. Traditional face-to-face community-engaged research is limited by geographic location, limited in resources, and/or uses one-way communications. Web 2.0 technologies including social media are novel communication channels for community-engaged research because these tools can reach a broader audience while promoting bidirectional dialogs. This paper reports on a preliminary program evaluation of the use of social media platforms for promoting engagement of researchers and community representatives in dialogs about community-engaged research. For this pilot program evaluation, the Clinical and Translational Science Office for Community Engagement in Research partnered with the Social Media Network at our institution to create a WordPress blog and Twitter account. Both social media platforms were facilitated by a social media manager. We used descriptive analytics for measuring engagement with WordPress and Twitter over an 18-month implementation period during 2014-2016. For the blog, we examined type of user (researcher, community representative, other) and used content analysis to generate the major themes from blog postings. For use of Twitter, we examined selected demographics and impressions among followers. There were 76 blog postings observed from researchers (48/76, 64%), community representatives (23/76, 32%) and funders (5/76, 8%). The predominant themes of the blog content were research awareness and dissemination of community-engaged research (35/76, 46%) and best practices (23/76, 30%). For Twitter, we obtained 411 followers at the end of the 18-month evaluation period, with an increase of 42% (from 280 to 411) over the final 6 months. Followers reported varied geographic location (321/411, 78

  19. Use of Web 2.0 Social Media Platforms to Promote Community-Engaged Research Dialogs: A Preliminary Program Evaluation

    Science.gov (United States)

    Valdez Soto, Miguel; Bishop, Shawn G; Aase, Lee A; Timimi, Farris K; Montori, Victor M; Patten, Christi A

    2016-01-01

    Background Community-engaged research is defined by the Institute of Medicine as the process of working collaboratively with groups of people affiliated by geographic proximity, special interests, or similar situations with respect to issues affecting their well-being. Traditional face-to-face community-engaged research is limited by geographic location, limited in resources, and/or uses one-way communications. Web 2.0 technologies including social media are novel communication channels for community-engaged research because these tools can reach a broader audience while promoting bidirectional dialogs. Objective This paper reports on a preliminary program evaluation of the use of social media platforms for promoting engagement of researchers and community representatives in dialogs about community-engaged research. Methods For this pilot program evaluation, the Clinical and Translational Science Office for Community Engagement in Research partnered with the Social Media Network at our institution to create a WordPress blog and Twitter account. Both social media platforms were facilitated by a social media manager. We used descriptive analytics for measuring engagement with WordPress and Twitter over an 18-month implementation period during 2014-2016. For the blog, we examined type of user (researcher, community representative, other) and used content analysis to generate the major themes from blog postings. For use of Twitter, we examined selected demographics and impressions among followers. Results There were 76 blog postings observed from researchers (48/76, 64%), community representatives (23/76, 32%) and funders (5/76, 8%). The predominant themes of the blog content were research awareness and dissemination of community-engaged research (35/76, 46%) and best practices (23/76, 30%). For Twitter, we obtained 411 followers at the end of the 18-month evaluation period, with an increase of 42% (from 280 to 411) over the final 6 months. Followers reported varied

  20. QUARTERLY PROGRESS REPORT JANUARY, FEBRUARY, MARCH, 1967 REACTOR FUELS AND MATERIALS DEVELOPMENT PROGRAMS FOR FUELS AND MATERIALS BRANCH OF USAEC DEVISION OF REACTOR DEVELOPMENT AND TECHNOLOGY

    Energy Technology Data Exchange (ETDEWEB)

    Albaugh, F. W.; Bush, S. H.; Cadwell, J. J.; de Halas, D. R.; Worlton, D. C.

    1967-06-01

    Work is reported in the areas of: fast fuels oxides and nitrides; nuclear ceramics; nuclear graphite; basic swelling studies; irradiation damage to reactor metals; ATR gas loop operation and maintenance; metallic fuels; nondestructive testing research; and fast reactor dosimetry and damage analysis.

  1. HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1977. [Graphite and fuel irradiation; fission product release

    Energy Technology Data Exchange (ETDEWEB)

    1977-12-01

    The work reported here includes studies of basic fission product transport mechanisms, core graphite development and testing, and the development and testing of recyclable fuel systems. Materials studied include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and data are presented.

  2. Preliminary testing of an asthma distance education program (ADEP) for school nurses in Appalachia.

    Science.gov (United States)

    Putman-Casdorph, Heidi; Pinto, Susan

    2011-12-01

    Asthma remains one of the most challenging chronic illnesses faced by school nurses both nationally and in the State of West Virginia. There is a clear need to provide ongoing continuing asthma education to school nurses. However, nurses face many barriers to receiving this education. The purpose of this pilot project was to develop and evaluate distance learning technology as a method to deliver continuing asthma education to school nurses in West Virginia. A sample of 20 school nurses from 2 counties in West Virginia participated in the study using the Wimba live classroom distance learning program. Significant modest improvements were found in both the intervention groups compared to a control group postintervention. The results of this pilot study are promising and show that distance learning technology could be a viable solution for school nurses to receive asthma continuing education.

  3. The benefits of yoga for rheumatoid arthritis: results of a preliminary, structured 8-week program.

    Science.gov (United States)

    Badsha, Humeira; Chhabra, Vishwas; Leibman, Cathy; Mofti, Ayman; Kong, Kok Ooi

    2009-10-01

    The aim of this study was to measure the effects of a bi-weekly Raj yoga program on rheumatoid arthritis (RA) disease activity. Subjects were recruited from among RA patients in Dubai, United Arab Emirates by email invitations of the RA database. Demographic data, disease activity indices, health assessment questionnaire (HAQ), and quality of life (QOL) by SF-36 were documented at enrollment and after completion of 12 sessions of Raj yoga. A total of 47 patients were enrolled: 26 yoga and 21 controls. Baseline demographics were similar in both groups. Patients who underwent yoga had statistically significant improvements in DAS28 and HAQ, but not QOL. Our pilot study of 12 sessions of yoga for RA was able to demonstrate statistically significant improvements in RA disease parameters. We believe that a longer duration of treatment could result in more significant improvements.

  4. [Preliminary results of a therapeutic program for childhood obesity in primary health care].

    Science.gov (United States)

    Temboury Molina, M C; Sacristán Martín, A; San Frutos Fernández, M A; Rodríguez Alfaro, F; Llorente González, R

    1993-05-01

    The high prevalence of childhood obesity in our society, its adverse consequences in the psychosocial development of the child, together with its risk of persistence into adulthood, prompted us to carry out this treatment program in our Primary Care Unit. It is based fundamentally on four aspects: diet, physical exercise, psychological and family support. Thirty children, between 4 and 14 years of age, were controlled for 11 months. These children's personal and family characteristics, their habits and psychological aspects were described. An average reduction of the IMC of 2.50 was obtained. The best results were obtained in children with two or more siblings, with a good adherence to the diet and with adequate family support. Sex, obesity of other family members, initial age, previous habits, etc., were not found to be influential. The importance of prevention and family collaboration is emphasized.

  5. CRACOW CLEAN FOSSIL FUELS AND ENERGY EFFICIENCY PROGRAM. PROGRESS REPORT, OCTOBER 1998

    Energy Technology Data Exchange (ETDEWEB)

    PIERCE,B.

    1998-10-01

    Since 1990 the US Department of Energy has been involved in a program aimed at reducing air pollution caused by small, coal-fired sources in Poland. The program focuses on the city of Cracow and is designed so that results will be applicable and extendable to the entire region. This report serves both as a review of the progress which has been made to date in achieving the program objectives and a summary of work still in progress.

  6. Preliminary Data on a Care Coordination Program for Home Care Recipients.

    Science.gov (United States)

    Dean, Katie M; Hatfield, Laura A; Jena, Anupam B; Cristman, David; Flair, Michael; Kator, Kylie; Nudd, Geoffrey; Grabowski, David C

    2016-09-01

    Home care recipients are often hospitalized for potentially avoidable reasons. A pilot program (Intervention in Home Care to Improve Health Outcomes (In-Home)) was designed to help home care providers identify acute clinical changes in condition and then manage the condition in the home and thereby avoid a costly hospitalization. Caregivers answer simple questions about the care recipient's condition during a telephone-based "clock-out" at the end of each shift. Responses are electronically captured in the agency management software that caregivers use to "clock-in," manage care, and "clock-out" on every shift. These are transmitted to the agency's care manager, who follows up on the change in condition and escalates appropriately. A description of the In-Home model is presented, and pilot data from 22 home care offices are reported. In the pilot, caregivers reported a change in condition after 2% of all shifts, representing an average of 1.9 changes per care recipient in a 6-month period. Changes in behavior and skin condition were the most frequently recorded domains. Interviews with participating caregivers and care managers suggested positive attitudes regarding the intervention; challenges included resistance to change on the part of home care staff and difficulties in applying a uniform intervention to individuals with varying needs in home care offices with varying capacities. In an ongoing randomized trial, the success of the overall program will be measured primarily according to the potential reduction in avoidable hospitalizations of home care recipients and the effect this potential reduction has on spending and healthcare outcomes. © 2016, Copyright the Authors Journal compilation © 2016, The American Geriatrics Society.

  7. Master's Degree Program in Scientific and Cultural Communication: Preliminary reports on an innovative experience in Brazil

    Directory of Open Access Journals (Sweden)

    Carlos A. Vogt

    2009-03-01

    Full Text Available The multidisiciplinary Master’s Degree Program in Scientific and Cultural Communication (MDCC began in the first semester of 2007. It is offered by the Laboratory of Advanced Studies in Journalism (Labjor of the Creativity Development Nucleus (NUDECRI and by the Institute of Language Studies (IEL, both of which are entities the State University of Campinas (UNICAMP. The program is also supported by the Department of Scientific and Technological Policy (DPCT of the Geosciences Institute (IG and by MediaTec – Media and Communication Technologies Laboratory of the Multimedia Department (DMM of the Art Institute (IA. The objective of the MDCC is to train and enable researchers with in-depth theoretical knowledge about current questions related to science communication. A global vision of the systems of science and technology are joined together with an understanding of a solid, contemporary literary and cultural repertoire. The interaction among subjects offered in the MDCC seeks to provide an education that allows critical reflection about the main accomplishments of science, technology and culture in our current society and the way in which the mass or specialized media have worked in order to communicate these accomplishments. The areas of research focus on the analysis of cultural production and science communication within the most diverse means of information, such as print, radio, television and electronic media. There is a special emphasis on areas such as science and technical history and the sociology of science, as well as other spaces of science and cultural communication, such as museums, forums and events.

  8. Industrial Fuel Gas Demonstration Plant Program. Volume III. Demonstration plant environmental analysis (Deliverable No. 27)

    Energy Technology Data Exchange (ETDEWEB)

    1979-08-01

    An Environmental Report on the Memphis Light, Gas and Water Division Industrial Fuel Demonstration Plant was prepared for submission to the US Department of Energy under Contract ET-77-C-01-2582. This document is Volume III of a three-volume Environmental Report. Volume I consists of the Summary, Introduction and the Description of the Proposed Action. Volume II consists of the Description of the Existing Environment. Volume III contains the Environmental Impacts of the Proposed Action, Mitigating Measures and Alternatives to the Proposed Action.

  9. Gaseous fuel reactor systems for aerospace applications

    Science.gov (United States)

    Thom, K.; Schwenk, F. C.

    1977-01-01

    Research on the gaseous fuel nuclear rocket concept continues under the programs of the U.S. National Aeronautics and Space Administration (NASA) Office for Aeronautics and Space Technology and now includes work related to power applications in space and on earth. In a cavity reactor test series, initial experiments confirmed the low critical mass determined from reactor physics calculations. Recent work with flowing UF6 fuel indicates stable operation at increased power levels. Preliminary design and experimental verification of test hardware for high-temperature experiments have been accomplished. Research on energy extraction from fissioning gases has resulted in lasers energized by fission fragments. Combined experimental results and studies indicate that gaseous-fuel reactor systems have significant potential for providing nuclear fission power in space and on earth.

  10. Preliminary PINC(Program for the Inspection of Nickel Alloy Components) RRT(Round Robin Test) - Pressurizer Dissimilar Metal Weld

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung Cho; Kang, Sung Sik; Shin, Ho Sang; Chung, Ku Kab; Song, Myung Ho; Chung, Hae Dong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2009-06-15

    After several damages by PWSCC were found in the world, USNRC and PNNL(Pacific Northwest National Laboratory) started the research on PWSCC under the project name of PINC. The aim of the project was 1) to fabricate representative NDE mock-ups with flaws to simulate PWSCCs, 2) to identify and quantitatively assess NDE methods for accurately detecting, sizing and characterizing PWSCCs, 3) to document the range of locations and morphologies of PWSCCs and 4) to incorporate results with other results of ongoing PWSCC research programs, as appropriate. Korea nuclear industries have also been participating in the project. Thermally and mechanically cracked-four mockups were prepared and phased array and manual ultrasonic testing(UT) techniques were applied. The results and lessons learned from the preliminary RRT are summarized as follows: 1) Korea RRT teams performed the RRT successfully. 2) Crack detection probability of the participating organizations was an average 87%, 80% and 80% respectively. 3) RMS error of the crack sizing showed comparatively good results. 4) The lessons learned may be helpful to perform the PINC RRT and PSI /ISI in Korea in the future.

  11. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates.

  12. Optimization of enrichment distributions in nuclear fuel assemblies loaded with uranium and plutonium via a modified linear programming technique

    Science.gov (United States)

    Cuevas Vivas, Gabriel Francisco

    A methodology to optimize enrichment distributions in Light Water Reactor (LWR) fuel assemblies is developed and tested. The optimization technique employed is the linear programming revised simplex method, and the fuel assembly's performance is evaluated with a neutron transport code that is also utilized in the calculation of sensitivity coefficients. The enrichment distribution optimization procedure begins from a single-value (flat) enrichment distribution until a target, maximum local power peaking factor, is achieved. The optimum rod enrichment distribution, with 1.00 for the maximum local power peaking factor and with each rod having its own enrichment, is calculated at an intermediate stage of the analysis. Later, the best locations and values for a reduced number of rod enrichments is obtained as a function of a target maximum local power peaking factor by applying sensitivity to change techniques. Finally, a shuffling process that assigns individual rod enrichments among the enrichment groups is performed. The relative rod power distribution is then slightly modified and the rod grouping redefined until the optimum configuration is attained. To verify the accuracy of the relative rod power distribution, a full computation with the neutron transport code using the optimum enrichment distribution is carried out. The results are compared and tested for assembly designs loaded with fresh Low Enriched Uranium (LEU) and plutonium Mixed OXide (MOX) fuels. MOX isotopics for both reactor-grade and weapons-grade plutonium were utilized to demonstrate the wide-range of applicability of the optimization technique. The features of the assembly designs used for evaluation purposes included burnable absorbers and internal water regions, and were prepared to resemble the configurations of modern assemblies utilized in commercial Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). In some cases, a net improvement in the relative rod power distribution or

  13. Hurricanes and anchors: preliminary results from the National Park Service regional reef assessment program

    Science.gov (United States)

    Rogers, Caroline S.

    1994-01-01

    The U .S . National Park Service NPS began a Regional Assessment Program for coral reefs in the U.S. Virgin Islands and Florida in 1988. Scientists from NPS and six other institutions have now established longterm monitoring sites at Virgin Islands National Park St. John, USVI, Buck Island Reef National Monument St. Croix, USVI, Biscayne National Park Florida and Fort Jefferson National Monument Florida. Hurricane Hugo passed through the USVI in 1989, causing severe destruction in some reef areas while leaving others untouched. Patchy damage to reefs in Florida was also noted after Hurricane Andrew; damage from this August 1992 storm is still being assessed. Fort Jefferson National Monument escaped the onslaught of Andrew. No significant recovery in live coral cover has been evident at the Buck Island or Virgin Islands National Park VINP study sites 3.5 years after Hurricane Hugo. Similarly, no recovery was evident at another site in St. John which was destroyed by a large anchor 4.5 years ago.

  14. Fifteenth symposium on biotechnology for fuels and chemicals: Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This collection contains 173 abstracts from presented papers and poster sessions. The five sessions of the conference were on the subjects of: (1) Thermal, Chemical, and Biological Processing, (2) Applied Biological Research, (3) Bioprocessing Research (4), Process Economics and Commercialization, and (5) Environmental Biotechnology. Examples of specific topics in the first session include the kinetics of ripening cheese, microbial liquefaction of lignite, and wheat as a feedstock for fuel ethanol. Typical topics in the second session were synergism studies of bacterial and fungal celluloses, conversion of inulin from jerusalem artichokes to sorbitol and ethanol by saccharomyces cerevisiae, and microbial conversion of high rank coals to methane. The third session entertained topics such as hydrodynamic modeling of a liquid fluidized bed bioreactor for coal biosolubilization, aqueous biphasic systems for biological particle partitioning, and arabinose utilization by xylose-fermenting yeast and fungi. The fourth session included such topics as silage processing of forage biomass to alcohol fuels, economics of molasses to ethanol in India, and production of lactic acid from renewable resources. the final session contained papers on such subjects as bioluminescent detection of contaminants in soils, characterization of petroleum contaminated soils in coral atolls in the south Pacific, and landfill management for methane generation and emission control.

  15. The Design and Manufacturing Report of Non-Instrumented Rig for Dual-cooled Annular Fuel Irradiation Test in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dae Ho; Bang, Je Geon; Lim, Ik Sung; Kim, Sun Ki; Yang, Yong Sik; Song, Kun Woo; Seo, Chul Gyo; Park, Chan Kook

    2008-09-15

    This project is preparing to irradiation test of the developed double cooled annular fuel pellet in HANARO for pursuit advanced performance in High Performance Fuel Technology Development as a part Nuclear Mid and Long-term R and D Program. On the basis test rod is performed the nuclei property and preliminary fuel performance analysis, test rod and non-instrumented rig designed and manufactured for irradiation test in HANARO OR hole. This non- instrumented rig was confirmed the compatibility of HANARO and the integrity of rig structure, and satisfied the quality assurance requirements. This non- instrumented rig is adopt to the irradiation test for double cooled annular fuel pellet in HANARO.

  16. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle descriptions

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    The Nonproliferation Alternative Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates. Volume IX is divided into three sections: Chapter 1, Reactor Systems; Chapter 2, Fuel-Cycle Systems; and the Appendixes. Chapter 1 contains the characterizations of the following 12 reactor types: light-water reactor; heavy-water reactor; water-cooled breeder reactor; high-temperature gas-cooled reactor; gas-cooled fast reactor; liquid-metal fast breeder reactor; spectral-shift-controlled reactor; accelerator-driven reactor; molten-salt reactor; gaseous-core reactor; tokamak fusion-fisson hybrid reactor; and fast mixed-spectrum reactor. Chapter 2 contains similar information developed for fuel-cycle facilities in the following categories: mining and milling; conversion and enrichment; fuel fabrication; spent fuel reprocessing; waste handling and disposal; and transportation of nuclear materials.

  17. Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, Sharon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Patton, Bradley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-09-01

    The U.S. Department of Energy (DOE) manages an inventory of materials that contains a range of long-lived radioactive isotopes that were produced from the 1960s through the 1980s by irradiating targets in production nuclear reactors at the Savannah River Site (SRS). One reactor was operated in a high-flux mode to produce heavy isotopes for defense purposes, DOE programmatic use, scientific research, and industrial and medical applications. In this reactor, eighty-six Mk-18A (Mk-18A) targets were subjected to long-term high neutron fluxes 47 years ago. Twentyone targets of these were processed to recover 244Pu, heavy curium (i.e., curium rich in 246-248Cm), and 252Cf. The plutonium fraction, which was rich in 244Pu, was electromagnetically enriched in the Oak Ridge National Laboratory (ORNL) calutrons to produce gram quantities of 244Pu. This high-purity 244Pu was portioned out to scientists for basic research and for nuclear nonproliferation safeguards programs. The recovered tails (designated as FP-33) contain 244Pu isotopic purities below 20% and are stored at ORNL. The processing of these 21 Mk-18A targets provided the supply of 244Pu and heavy curium in use today. The remaining 65 unprocessed targets are currently in a storage pool at SRS; they contain the world’s remaining supply of unseparated 244Pu and heavy curium.

  18. Evolutionary programming-based methodology for economical output power from PEM fuel cell for micro-grid application

    Science.gov (United States)

    El-Sharkh, M. Y.; Rahman, A.; Alam, M. S.

    This paper presents a methodology for finding the optimal output power from a PEM fuel cell power plant (FCPP). The FCPP is used to supply power to a small micro-grid community. The technique used is based on evolutionary programming (EP) to find a near-optimal solution of the problem. The method incorporates the Hill-Climbing technique (HCT) to maintain feasibility during the solution process. An economic model of the FCPP is used. The model considers the production cost of energy and the possibility of selling and buying electrical energy from the local grid. In addition, the model takes into account the thermal energy output from the FCPP and the thermal energy requirement for the micro-grid community. The results obtained are compared against a solution based on genetic algorithms. Results are encouraging and indicate viability of the proposed technique.

  19. Compressed air energy storage: preliminary design and site development program in an aquifer. Final draft, Task 1: establish facility design criteria and utility benefits

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-10-01

    Compressed air energy storage (CAES) has been identified as one of the principal new energy storage technologies worthy of further research and development. The CAES system stores mechanical energy in the form of compressed air during off-peak hours, using power supplied by a large, high-efficiency baseload power plant. At times of high electrical demand, the compressed air is drawn from storage and is heated in a combustor by the burning of fuel oil, after which the air is expanded in a turbine. In this manner, essentially all of the turbine output can be applied to the generation of electricity, unlike a conventional gas turbine which expends approximately two-thirds of the turbine shaft power in driving the air compressor. The separation of the compression and generation modes in the CAES system results in increased net generation and greater premium fuel economy. The use of CAES systems to meet the utilities' high electrical demand requirements is particularly attractive in view of the reduced availability of premium fuels such as oil and natural gas. This volume documents the Task 1 work performed in establishing facility design criteria for a CAES system with aquifer storage. Information is included on: determination of initial design bases; preliminary analysis of the CAES system; development of data for site-specific analysis of the CAES system; detailed analysis of the CAES system for three selected heat cycles; CAES power plant design; and an economic analysis of CAES.

  20. OSMOSE an experimental program for improving neutronic predictions of advanced nuclear fuels.

    Energy Technology Data Exchange (ETDEWEB)

    Klann, R. T.; Aliberti, G.; Zhong, Z.; Graczyk, D.; Loussi, A.; Nuclear Engineering Division; Commissariat a l Energie Atomique

    2007-10-18

    This report describes the technical results of tasks and activities conducted in FY07 to support the DOE-CEA collaboration on the OSMOSE program. The activities are divided into five high-level tasks: reactor modeling and pre-experiment analysis, sample fabrication and analysis, reactor experiments, data treatment and analysis, and assessment for relevance to high priority advanced reactor programs (such as GNEP and Gen-IV).