Do Americans want ethanol? A comparative contingent-valuation study of willingness to pay for E-10 and E-85

Energy Technology Data Exchange (ETDEWEB)

Petrolia, Daniel R.; Bhattacharjee, Sanjoy [Department of Agricultural Economics, Mississippi State University, P.O. Box 5187, Mississippi State, MS 39762 (United States); Hudson, Darren [Department of Agricultural and Applied Economics, Texas Tech University, Lubbock, TX 79409 (United States); Herndon, Cary W. [North Mississippi Research and Extension Center, Mississippi State University, Verona, MS 38879 (United States)

2010-01-15

A nationwide contingent-valuation survey of consumer preferences for consumer fuel blends E-10 (a blend of 10% ethanol and 90% gasoline for use in standard vehicles) and E-85 (a blend of 85% ethanol and 15% gasoline for use in flex-fuel vehicles) was conducted to estimate willingness to pay (WTP) and identify key characteristics driving demand. Results indicate that overall perceptions of ethanol are positive, but ethanol is not the globally-preferred transportation-energy alternative, even among consumers with a positive WTP. Results indicate also that demand for E-85 is more price inelastic than E-10, with this result driven by consumers with no preference for E-10 but strong preferences for E-85. Finally, results also indicate that those consumers who are unsure about the micro-level benefits of E-85 are nonetheless more inclined to pay a premium. (author)

Do Americans want ethanol? A comparative contingent-valuation study of willingness to pay for E-10 and E-85

International Nuclear Information System (INIS)

Petrolia, Daniel R.; Bhattacharjee, Sanjoy; Hudson, Darren; Herndon, Cary W.

2010-01-01

A nationwide contingent-valuation survey of consumer preferences for consumer fuel blends E-10 (a blend of 10% ethanol and 90% gasoline for use in standard vehicles) and E-85 (a blend of 85% ethanol and 15% gasoline for use in flex-fuel vehicles) was conducted to estimate willingness to pay (WTP) and identify key characteristics driving demand. Results indicate that overall perceptions of ethanol are positive, but ethanol is not the globally-preferred transportation-energy alternative, even among consumers with a positive WTP. Results indicate also that demand for E-85 is more price inelastic than E-10, with this result driven by consumers with no preference for E-10 but strong preferences for E-85. Finally, results also indicate that those consumers who are unsure about the micro-level benefits of E-85 are nonetheless more inclined to pay a premium. (author)

78 FR 17660 - Draft Guidance for E85 Flexible Fuel Vehicle Weighting Factor for Model Years 2016-2019 Vehicles...

Science.gov (United States)

2013-03-22

... ENVIRONMENTAL PROTECTION AGENCY [FRL-9792-9] Draft Guidance for E85 Flexible Fuel Vehicle... draft EPA guidance to auto manufacturers for weighting the greenhouse gas (GHG) emissions of a flexible... all federal government work days from 8:30 a.m. to 4:30 p.m.; generally, it is open Monday through...

Coalition Cooperation Defines Roadmap for E85 and Biodiesel

Energy Technology Data Exchange (ETDEWEB)

2007-06-01

This Clean Cities success story relates how Colorado's Colorado Biofuels Coalition was formed and provides guidance on forming other such coalitions. This Colorado's coalition sucessfully increase the number of fueling stations providing biofuels and has goals to the number even more. Plans also include assisting with financing infrastructure, making alternative fuels available to more fleets, and educating about E85 and biodiesel use.

Report of the working group on the support and development of the E85 channel; Rapport du groupe de travail sur le soutien au developpement de la filiere E85

Energy Technology Data Exchange (ETDEWEB)

Prost, A.; Durieux, B.; Sauvalle, B.; Macaire, A

2006-07-01

The E85 is a fuel realized by a direct and a majority mixing of ethanol in non modified unleaded galena. Created in June 2006, this working group aims to analyze the success conditions of the E85 operating and manage the involved people around a common plan. This report presents the E85 characteristics, shows the economical and environmental interest of the project, provides recommendations and concludes with ten proposals. (A.L.B.)

Nanotechnology Role for the Production of Clean Fuel E-85 and Petrochemical Raw Materials

Directory of Open Access Journals (Sweden)

Iskander K. Basily

2012-01-01

Full Text Available There have been a number of substantive technical changes that can be described as revolutionary process and evolutionary process. One of these approaches is the use of nanotechnology in the two-stage pyrolysis of petroleum residues of the heavy distillates separated from the Arabian crude oil. Two-stage catalytic pyrolysis technique proved to be an excellent method for the production of unsaturated hydrocarbons (which easily can be converted to alcohol, by addition of H2O, for the production of E-85, i.e., clean fuel regardless the type of feed stocks used. Basically, the catalysts are arranged into three large groups; amorphous and crystalline alumino-silicates, alkaline or alkaline earth alumino compounds, and different metal oxides on different catalyst carriers such as Zeolites. The high yield of ethylene (30–40% brought by different catalysts at temperatures of 700–750°C appear to justify the intensive research work in this field.

Advanced Fuel/Cladding Testing Capabilities in the ORNL High Flux Isotope Reactor

International Nuclear Information System (INIS)

Ott, Larry J.; Ellis, Ronald James; McDuffee, Joel Lee; Spellman, Donald J.; Bevard, Bruce Balkcom

2009-01-01

The ability to test advanced fuels and cladding materials under reactor operating conditions in the United States is limited. The Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) and the newly expanded post-irradiation examination (PIE) capability at the ORNL Irradiated Fuels Examination Laboratory provide unique support for this type of advanced fuel/cladding development effort. The wide breadth of ORNL's fuels and materials research divisions provides all the necessary fuel development capabilities in one location. At ORNL, facilities are available from test fuel fabrication, to irradiation in HFIR under either thermal or fast reactor conditions, to a complete suite of PIEs, and to final product disposal. There are very few locations in the world where this full range of capabilities exists. New testing capabilities at HFIR have been developed that allow testing of advanced nuclear fuels and cladding materials under prototypic operating conditions (i.e., for both fast-spectrum conditions and light-water-reactor conditions). This paper will describe the HFIR testing capabilities, the new advanced fuel/cladding testing facilities, and the initial cooperative irradiation experiment that begins this year.

ARC System fuel cycle analysis capability, REBUS-2

International Nuclear Information System (INIS)

Hosteny, R.P.

1978-10-01

A detailed description is given of the ARC System fuel cycle modules FCI001, FCC001, FCC002, and FCC003 which form the fuel cycle analysis modules of the ARC System. These modules, in conjunction with certain other modules of the ARC System previously described in documents of this series, form the fuel cycle analysis system called REBUS-2. The physical model upon which the REBUS-2 fuel cycle modules are based and the calculational approach used in solving this model are discussed in detail. The REBUS-2 system either solves for the infinite time (i.e., equilibrium) operating conditions of a fuel recycle system under fixed fuel management conditions, or solves for the operating conditions during each of a series of explicitly specified (i.e., nonequilibrium) sequence of burn cycles. The code has the capability to adjust the fuel enrichment, the burn time, and the control poison requirements in order to satisfy user specified constraints on criticality, discharge fuel burnup, or to give the desired multiplication constant at some specified time during the reactor operation

ARC System fuel cycle analysis capability, REBUS-2

Energy Technology Data Exchange (ETDEWEB)

Hosteny, R.P.

1978-10-01

A detailed description is given of the ARC System fuel cycle modules FCI001, FCC001, FCC002, and FCC003 which form the fuel cycle analysis modules of the ARC System. These modules, in conjunction with certain other modules of the ARC System previously described in documents of this series, form the fuel cycle analysis system called REBUS-2. The physical model upon which the REBUS-2 fuel cycle modules are based and the calculational approach used in solving this model are discussed in detail. The REBUS-2 system either solves for the infinite time (i.e., equilibrium) operating conditions of a fuel recycle system under fixed fuel management conditions, or solves for the operating conditions during each of a series of explicitly specified (i.e., nonequilibrium) sequence of burn cycles. The code has the capability to adjust the fuel enrichment, the burn time, and the control poison requirements in order to satisfy user specified constraints on criticality, discharge fuel burnup, or to give the desired multiplication constant at some specified time during the reactor operation.

Ford Taurus Ethanol-Fueled Sedan

International Nuclear Information System (INIS)

Eudy, Leslie

1999-01-01

The U.S. Department of Energy (DOE) is encouraging the use of alternative fuels and alternative fuel vehicles (AFVs). To support this activity, DOE has directed the National Renewable Energy Laboratory (NREL) to conduct projects to evaluate the performance and acceptability of light-duty AFVs. In this study, we tested a pair of 1998 Ford Tauruses: one E85 (85% gasoline/15% ethanol) model (which was tested on both E85 and gasoline) and a gasoline model as closely matched as possible. Each vehicle was run through a series of tests to evaluate acceleration, fuel economy, braking, and cold-start capabilities, as well as more subjective performance indicators such as handling, climate control, and noise

Report of the working group on the support and development of the E85 channel

International Nuclear Information System (INIS)

Prost, A.; Durieux, B.; Sauvalle, B.; Macaire, A.

2006-01-01

The E85 is a fuel realized by a direct and a majority mixing of ethanol in non modified unleaded galena. Created in June 2006, this working group aims to analyze the success conditions of the E85 operating and manage the involved people around a common plan. This report presents the E85 characteristics, shows the economical and environmental interest of the project, provides recommendations and concludes with ten proposals. (A.L.B.)

Manufacturing fuel-switching capability, 1988

International Nuclear Information System (INIS)

1991-09-01

Historically, about one-third of all energy consumed in the United States has been used by manufacturers. About one-quarter of manufacturing energy is used as feedstocks and raw material inputs that are converted into nonenergy products; the remainder is used for its energy content. During 1988, the most recent year for which data are available, manufacturers consumed 15.5 quadrillion British thermal units (Btu) of energy to produce heat and power and to generate electricity. The manufacturing sector also has widespread capabilities to switch from one fuel to another for either economic or emergency reasons. There are numerous ways to define fuel switching. For the purposes of the Manufacturing Energy Consumption Survey (MECS), fuel switching is defined as the capability to substitute one energy source for another within 30 days with no significant modifications to the fuel-consuming equipment, while keeping production constant. Fuel-switching capability allows manufacturers substantial flexibility in choosing their mix of energy sources. The consumption of a given energy source can be maximized if all possible switching into that energy source takes place. The estimates in this report are based on data collected on the 1988 Manufacturing Energy Consumption Survey (MECS), Forms 846 (A through C). The EIA conducts this national sample survey of manufacturing energy consumption on a triennial basis. The MECS is the only comprehensive source of national-level data on energy-related information for the manufacturing industries. The MECS was first conducted in 1986 to collect data for 1985. This report presents information on the fuel-switching capabilities of manufacturers in 1988. This report is the second of a series based on the 1988 MECS. 8 figs., 31 tabs

Manufacturing fuel-switching capability, 1988

Energy Technology Data Exchange (ETDEWEB)

1991-09-01

Historically, about one-third of all energy consumed in the United States has been used by manufacturers. About one-quarter of manufacturing energy is used as feedstocks and raw material inputs that are converted into nonenergy products; the remainder is used for its energy content. During 1988, the most recent year for which data are available, manufacturers consumed 15.5 quadrillion British thermal units (Btu) of energy to produce heat and power and to generate electricity. The manufacturing sector also has widespread capabilities to switch from one fuel to another for either economic or emergency reasons. There are numerous ways to define fuel switching. For the purposes of the Manufacturing Energy Consumption Survey (MECS), fuel switching is defined as the capability to substitute one energy source for another within 30 days with no significant modifications to the fuel-consuming equipment, while keeping production constant. Fuel-switching capability allows manufacturers substantial flexibility in choosing their mix of energy sources. The consumption of a given energy source can be maximized if all possible switching into that energy source takes place. The estimates in this report are based on data collected on the 1988 Manufacturing Energy Consumption Survey (MECS), Forms 846 (A through C). The EIA conducts this national sample survey of manufacturing energy consumption on a triennial basis. The MECS is the only comprehensive source of national-level data on energy-related information for the manufacturing industries. The MECS was first conducted in 1986 to collect data for 1985. This report presents information on the fuel-switching capabilities of manufacturers in 1988. This report is the second of a series based on the 1988 MECS. 8 figs., 31 tabs.

Assessment of elliptic flame front propagation characteristics of iso-octane, gasoline, M85 and E85 in an optical engine

OpenAIRE

Ihracska, Balazs; Korakianitis, Theodosios P.; Ruiz, Paula; Emberson, David Robert; Crookes, Roy James; Diez, Alvaro; Wen, Dongsheng

2014-01-01

Premixed fuel-air flame propagation is investigated in a single-cylinder, spark-ignited, four-stroke optical test engine using high-speed imaging. Circles and ellipses are fitted onto image projections of visible light emitted by the flames. The images are subsequently analysed to statistically evaluate: flame area; flame speed; centroid; perimeter; and various flame-shape descriptors. Results are presented for gasoline, isooctane, E85 and M85. The experiments were conducted at stoichiometric...

40 CFR 85.1510 - Maintenance instructions, warranties, emission labeling and fuel economy requirements.

Science.gov (United States)

2010-07-01

..., emission labeling and fuel economy requirements. 85.1510 Section 85.1510 Protection of Environment..., warranties, emission labeling and fuel economy requirements. The provisions of this section are applicable to... for final admission. (d) Fuel economy labeling. (1) The certificate holder shall affix a fuel economy...

Enhanced Ozone Production at Low Temperatures due to Ethanol (E85)

Science.gov (United States)

Ginnebaugh, D. L.; Livingstone, P. L.; Jacobson, M. Z.

2009-12-01

The increased use of ethanol in transportation fuels warrants an investigation of its consequences. An important component of such an investigation is the temperature-dependence of ethanol and gasoline exhaust chemistry. We use the near-explicit Master Chemical Mechanism (MCM, version 3.1, LEEDS University) with the SMVGEAR II chemical ordinary differential solver to provide the speed necessary to simulate explicit chemistry to examine such effects. The MCM has over 13,500 organic reactions and 4,600 species. SMVGEAR II is a sparse-matrix Gear solver that reduces the computation time significantly while maintaining any specified accuracy. Although for this study we use a box model, we determined that the speed of the MCM with the SMVGEAR solver will allow the MCM to be modeled in 3-dimensions. We also verified the accuracy of the model with comparisons to smog chamber data. We use species-resolved tailpipe emissions data for E85 (15% gasoline, 85% ethanol fuel blend) and gasoline vehicles to compare the impact of each on ozone and carcinogenic organic gases as a function of ambient temperature and background concentrations, using Los Angeles in 2020 as a base case. We use two different emissions sets - one is a compilation of data taken at near 24 C and the other from data taken at -7 C - to determine how atmospheric chemistry and emissions are affected by temperature. We include diurnal effects by examining 2 day and 5 day scenarios. We find that for both emission data sets, the average ozone concentrations through the range of temperatures tested are higher with E85 than with gasoline by 8 parts per billion volume (ppbv) at higher temperatures to 55 ppbv at low temperatures and low sunlight (winter conditions) for an area with a high nitrogen oxides (NOx) to non-methane organic gases (NMOG) ratio. The results suggest that E85's effect on health through ozone formation becomes increasingly more significant relative to gasoline as temperatures decreased due to the

Handbook for Handling, Storing, and Dispensing E85 and Other Ethanol-Gasoline Blends

Energy Technology Data Exchange (ETDEWEB)

None

2016-03-02

This document provides information on ethanol fuel properties, standards, codes, best practices, and equipment information for those who blend, distribute, store, sell, or use E15 (gasoline blended with 10.5 percent - 15 percent ethanol), E85 (marketing term for ethanol-gasoline blends containing 51 percent - 83 percent ethanol, depending on geography and season), and other ethanol blends.

Handbook for Handling, Storing, and Dispensing E85 and Other Ethanol-Gasoline Blends

Energy Technology Data Exchange (ETDEWEB)

2016-03-01

This document provides information on ethanol fuel properties, standards, codes, best practices, and equipment information for those who blend, distribute, store, sell, or use E15 (gasoline blended with 10.5 percent - 15 percent ethanol), E85 (marketing term for ethanol-gasoline blends containing 51 percent - 83 percent ethanol, depending on geography and season), and other ethanol blends.

40 CFR 86.1229-85 - Dynamometer load determination and fuel temperature profile.

Science.gov (United States)

2010-07-01

... VEHICLES AND ENGINES (CONTINUED) Evaporative Emission Test Procedures for New Gasoline-Fueled, Natural Gas-Fueled, Liquefied Petroleum Gas-Fueled and Methanol-Fueled Heavy-Duty Vehicles § 86.1229-85 Dynamometer... has more than one fuel tank, a profile shall be established for each tank. Manufacturers may also...

On the intrinsic transient capability and limitations of solid oxide fuel cell systems

OpenAIRE

Mueller, F; Jabbari, F; Brouwer, J

2009-01-01

The intrinsic transient performance capability and limitation of integrated solid oxide fuel cell (SOFC) systems is evaluated based on the system balance-of-plant response and fuel cell operating requirements (i.e., allowable deviation from nominal operation). Specifically, non-dimensional relations are derived from conservation principles that quantify the maximum instantaneous current increase that a solid oxide fuel cell system can safely manage based on (1) the desired fuel cell operating...

MTR fuel plate qualification capabilities at SCK-CEN

International Nuclear Information System (INIS)

Koonen, E.; Jacquet, P.

2002-01-01

In order to enhance the capabilities of BR2 in the field of MTR fuel plate testing, a dedicated irradiation device has been designed. In its basic version this device allows the irradiation of 3 fuel plates. The central fuel plate may be replaced by a dummy plate or a plate carrying dosimeters. A first FUTURE device has been built. A benchmark irradiation has been executed with standard BR2 fuel plates in order to qualify this device. Detailed neutronic calculations were performed and the results compared to the results of the post-irradiation examinations of the plates. These comparisons demonstrate the capability to conduct a fuel plate irradiation program under requested and well-known irradiation conditions. Further improvements are presently being designed in order to extend the ranges of heat flux and surface temperature of the fuel plates that can be handled with the FUTURE device. (author)

Impact of dedicated E85 vehicle use on ozone and particulate matter in the US

Science.gov (United States)

Nopmongcol, Uarporn; Griffin, W. Michael; Yarwood, Greg; Dunker, Alan M.; MacLean, Heather L.; Mansell, Gerard; Grant, John

2011-12-01

Increased use of ethanol as a vehicle fuel worldwide warrants the need to understand air quality impacts of replacing gasoline with ethanol. This study evaluates the impacts of dedicated E85 (85% ethanol/15% gasoline) light-duty vehicles on emissions, ozone and particulate matter (PM) concentrations in the United States for a future year (2022) using a 3-D photochemical model, detailed emissions inventories that account for changes in all sectors studied, and winter and summer meteorology that occurred in 2002. Use of E85 introduces new emissions from ethanol production and distribution, reduces petrochemical industry emissions due to lower gasoline consumption, changes on-road vehicle emissions and alters biogenic emissions due to land use changes. Three scenarios with increased ethanol production for dedicated E85 light-duty vehicles were compared to a base case without increased ethanol production. Increased use of E85 caused both increases and decreases in ozone and PM, driven mainly by changes in NO x emissions related to biogenic and upstream petrochemical industry sources. In all states modeled, adoption of dedicated E85 vehicles caused negligible change in average higher ozone and PM concentrations of importance for air quality management strategies. Ozone and PM changes are relatively insensitive to how land area is allocated for switchgrass production. The findings are subject to various uncertainties, especially those in vehicle technology and emissions from cellulosic ethanol production.

Krypton-85 health risk assessment for a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Mellinger, P.J.; Tanner, J.E.; Brackenbush, L.W.; Gilbert, E.S.

1984-08-01

A health risk assessment was conducted to investigate the impact of implementing regulations from the Environmental Protection Agency's Final Environmental Statement - 40 CFR 190 - Environmental Protection Requirements for Normal Operation of Activities in the Uranium Fuel Cycle. Potential risks involved in the routine release of 85 Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of 85 Kr. The average occupationally exposed worker was estimated to receive about 400 to 600 mrem/y from 85 Kr recovery and immobilization activities. This dose is a factor of 20,000 to 30,000 higher than the estimated dose to the maximum offsite individual (0.02 mrem/y), and a factor of 130,000 to 200,000 higher than the dose received by the average member of the 50-mile population (0.003 mrem/y) from routine release of all 85 Kr. Given the uncertainties in the models used to generate lifetime risk numbers (0.02-0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks cannot be considered meaningful. There is certainly no reason to conclude that risks from 85 Kr routinely released to the environment are greater than those that would result from recovery, immobilization and storage of the noble gas. 22 references, 1 figure, 3 tables

Fuel Fabrication Capability Research and Development Plan

Energy Technology Data Exchange (ETDEWEB)

Senor, David J.; Burkes, Douglas

2013-06-28

The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative (GTRI) Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors.

Intermediate Alcohol-Gasoline Blends, Fuels for Enabling Increased Engine Efficiency and Powertrain Possibilities

Energy Technology Data Exchange (ETDEWEB)

Splitter, Derek A [ORNL; Szybist, James P [ORNL

2014-01-01

The present study experimentally investigates spark-ignited combustion with 87 AKI E0 gasoline in its neat form and in mid-level alcohol-gasoline blends with 24% vol./vol. iso-butanol-gasoline (IB24) and 30% vol./vol. ethanol-gasoline (E30). A single-cylinder research engine is used with a low and high compression ratio of 9.2:1 and 11.85:1 respectively. The engine is equipped with hydraulically actuated valves, laboratory intake air, and is capable of external exhaust gas recirculation (EGR). All fuels are operated to full-load conditions with =1, using both 0% and 15% external cooled EGR. The results demonstrate that higher octane number bio-fuels better utilize higher compression ratios with high stoichiometric torque capability. Specifically, the unique properties of ethanol enabled a doubling of the stoichiometric torque capability with the 11.85:1 compression ratio using E30 as compared to 87 AKI, up to 20 bar IMEPg at =1 (with 15% EGR, 18.5 bar with 0% EGR). EGR was shown to provide thermodynamic advantages with all fuels. The results demonstrate that E30 may further the downsizing and downspeeding of engines by achieving increased low speed torque, even with high compression ratios. The results suggest that at mid-level alcohol-gasoline blends, engine and vehicle optimization can offset the reduced fuel energy content of alcohol-gasoline blends, and likely reduce vehicle fuel consumption and tailpipe CO2 emissions.

Fuel Fabrication Capability Research and Development Plan

Energy Technology Data Exchange (ETDEWEB)

Senor, David J.; Burkes, Douglas

2014-04-17

The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors. Therefore, the overriding motivation behind the FFC R&D program described in this plan is to foster closer integration between fuel design and fabrication to reduce programmatic risk. These motivating factors are all interrelated, and progress addressing one will aid understanding of the others. The FFC R&D needs fall into two principal categories, 1) baseline process optimization, to refine the existing fabrication technologies, and 2) manufacturing process alternatives, to evaluate new fabrication technologies that could provide improvements in quality, repeatability, material utilization, or cost. The FFC R&D Plan examines efforts currently under way in regard to coupon, foil, plate, and fuel element manufacturing, and provides recommendations for a number of R&D topics that are of high priority but not currently funded (i.e., knowledge gaps). The plan ties all FFC R&D efforts into a unified vision that supports the overall Convert Program schedule in general, and the fabrication schedule leading up to the MP-1 and FSP-1 irradiation experiments specifically. The fabrication technology decision gates and down-selection logic and schedules are tied to the schedule for fabricating the MP-1 fuel plates, which will provide the necessary data to make a final fuel fabrication process down-selection. Because of the short turnaround between MP-1 and the follow-on FSP-1 and MP-2 experiments, the suite of specimen types that will be available for MP-1 will be the same as those available for FSP-1 and MP-2. Therefore, the only opportunity to explore parameter space and alternative processing

User's guide for the REBUS-3 fuel cycle analysis capability

International Nuclear Information System (INIS)

Toppel, B.J.

1983-03-01

REBUS-3 is a system of programs designed for the fuel-cycle analysis of fast reactors. This new capability is an extension and refinement of the REBUS-3 code system and complies with the standard code practices and interface dataset specifications of the Committee on Computer Code Coordination (CCCC). The new code is hence divorced from the earlier ARC System. In addition, the coding has been designed to enhance code exportability. Major new capabilities not available in the REBUS-2 code system include a search on burn cycle time to achieve a specified value for the multiplication constant at the end of the burn step; a general non-repetitive fuel-management capability including temporary out-of-core fuel storage, loading of fresh fuel, and subsequent retrieval and reloading of fuel; significantly expanded user input checking; expanded output edits; provision of prestored burnup chains to simplify user input; option of fixed-or free-field BCD input formats; and, choice of finite difference, nodal or spatial flux-synthesis neutronics in one-, two-, or three-dimensions

Consolidating indigenous capability for PHWR fuel manufacturing in India

Energy Technology Data Exchange (ETDEWEB)

Jayaraj, R.N., E-mail: cenfc@nfc.gov.in [Nuclear Fuel Complex, Dept. of Atomic Energy, Government of India, Hyderabad (India)

2010-07-01

Since inception of Nuclear Power Programme in India greater emphasis was laid on total self- reliance in Fuel manufacturing. For Pressurized Heavy Water Reactors (PHWRs), which forms a base for the first stage of the programme, an integrated approach was adopted encompassing different areas of expertise -Design, Construction and Operation of PHWRs; Heavy Water production and Fuel Design and Manufacturing technologies. For the first PHWR constructed about 35 years back with the Canadian collaboration, known as Rajasthan Atomic Power Station (RAPS), half the core requirement of fuel was met from the fuel manufactured for the first time in India. Since then the fuel production capabilities were enhanced by setting up an industrial scale fuel manufacturing facility - Nuclear Fuel Complex (NFC) at Hyderabad, India during early '70s. NFC has been continuously expanding its capacities to meet the fuel demand of all the PHWRs constructed and operated by Nuclear Power Corporation of India Limited (NPCIL). Presently, fifteen PHWR 220 MWe units and two PHWR 540 MWe units are in operation and one more PHWR 220 MWe unit is in advanced stage of commissioning in India. While continuously engaged in the manufacture of fuel for these reactors, NFC has been upgrading the production lines with new processes and quality assurance systems. In order to multiply the production capacities, NFC has embarked on developing indigenous capability for design and building of special purpose process equipment for Uranium dioxide powder production, pelletisation and final assembly operations. Some of the equipment having state-of-the-art features includes dryers/furnaces for UO{sub 2} powder, presses/ sintering furnaces for pelletisation and resistance welding equipment/ machining stations for assembly operations. In addition, several campaigns were taken over the years for manufacturing PHWR fuel bundles containing reprocessed Uranium, Thoria and slightly enriched Uranium. The paper

Consolidating indigenous capability for PHWR fuel manufacturing in India

International Nuclear Information System (INIS)

Jayaraj, R.N.

2010-01-01

Since inception of Nuclear Power Programme in India greater emphasis was laid on total self- reliance in Fuel manufacturing. For Pressurized Heavy Water Reactors (PHWRs), which forms a base for the first stage of the programme, an integrated approach was adopted encompassing different areas of expertise -Design, Construction and Operation of PHWRs; Heavy Water production and Fuel Design and Manufacturing technologies. For the first PHWR constructed about 35 years back with the Canadian collaboration, known as Rajasthan Atomic Power Station (RAPS), half the core requirement of fuel was met from the fuel manufactured for the first time in India. Since then the fuel production capabilities were enhanced by setting up an industrial scale fuel manufacturing facility - Nuclear Fuel Complex (NFC) at Hyderabad, India during early '70s. NFC has been continuously expanding its capacities to meet the fuel demand of all the PHWRs constructed and operated by Nuclear Power Corporation of India Limited (NPCIL). Presently, fifteen PHWR 220 MWe units and two PHWR 540 MWe units are in operation and one more PHWR 220 MWe unit is in advanced stage of commissioning in India. While continuously engaged in the manufacture of fuel for these reactors, NFC has been upgrading the production lines with new processes and quality assurance systems. In order to multiply the production capacities, NFC has embarked on developing indigenous capability for design and building of special purpose process equipment for Uranium dioxide powder production, pelletisation and final assembly operations. Some of the equipment having state-of-the-art features includes dryers/furnaces for UO 2 powder, presses/ sintering furnaces for pelletisation and resistance welding equipment/ machining stations for assembly operations. In addition, several campaigns were taken over the years for manufacturing PHWR fuel bundles containing reprocessed Uranium, Thoria and slightly enriched Uranium. The paper summarises

Transportation capabilities study of DOE-owned spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Clark, G.L.; Johnson, R.A.; Smith, R.W. [Packaging Technology, Inc., Tacoma, WA (United States); Abbott, D.G.; Tyacke, M.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1994-10-01

This study evaluates current capabilities for transporting spent nuclear fuel owned by the US Department of Energy. Currently licensed irradiated fuel shipping packages that have the potential for shipping the spent nuclear fuel are identified and then matched against the various spent nuclear fuel types. Also included are the results of a limited investigation into other certified packages and new packages currently under development. This study is intended to support top-level planning for the disposition of the Department of Energy`s spent nuclear fuel inventory.

Examining the impacts of ethanol (E85) versus gasoline photochemical production of smog in a fog using near-explicit gas- and aqueous-chemistry mechanisms

International Nuclear Information System (INIS)

Ginnebaugh, Diana L; Jacobson, Mark Z

2012-01-01

This study investigates the air quality impacts of using a high-blend ethanol fuel (E85) instead of gasoline in vehicles in an urban setting when a morning fog is present under summer and winter conditions. The model couples the near-explicit gas-phase Master Chemical Mechanism (MCM v. 3.1) with the extensive aqueous-phase Chemical Aqueous Phase Radical Mechanism (CAPRAM 3.0i) in SMVGEAR II, a fast and accurate ordinary differential equation solver. Summer and winter scenarios are investigated during a two day period in the South Coast Air Basin (SCAB) with all gasoline vehicles replaced by flex-fuel vehicles running on E85 in 2020. We find that E85 slightly increases ozone compared with gasoline in the presence or absence of a fog under summer conditions but increases ozone significantly relative to gasoline during winter conditions, although winter ozone is always lower than summer ozone. A new finding here is that a fog during summer may increase ozone after the fog disappears, due to chemistry alone. Temperatures were high enough in the summer to increase peroxy radical (RO 2 ) production with the morning fog, which led to the higher ozone after fog dissipation. A fog on a winter day decreases ozone after the fog. Within a fog, ozone is always lower than if no fog occurs. The sensitivity of the results to fog parameters like droplet size, liquid water content, fog duration and photolysis are investigated and discussed. The results support previous work suggesting that E85 and gasoline both enhance pollution with E85 enhancing pollution significantly more at low temperatures. Thus, neither E85 nor gasoline is a ‘clean-burning’ fuel. (letter)

Verification of FA2D Prediction Capability Using Fuel Assembly Benchmark

International Nuclear Information System (INIS)

Jecmenica, R.; Pevec, D.; Grgic, D.; Konjarek, D.

2008-01-01

FA2D is 2D transport collision probability code developed at Faculty of Electrical Engineering and Computing, University Zagreb. It is used for calculation of cross section data at fuel assembly level. Main objective of its development was capability to generate cross section data to be used for fuel management and safety analyses of PWR reactors. Till now formal verification of code predictions capability is not performed at fuel assembly level, but results of fuel management calculations obtained using FA2D generated cross sections for NPP Krsko and IRIS reactor are compared against Westinghouse calculations. Cross section data were used within NRC's PARCS code and satisfactory preliminary results were obtained. This paper presents results of calculations performed for Nuclear Fuel Industries, Ltd., benchmark using FA2D, and SCALE5 TRITON calculation sequence (based on discrete ordinates code NEWT). Nuclear Fuel Industries, Ltd., Japan, released LWR Next Generation Fuels Benchmark with the aim to verify prediction capability in nuclear design for extended burnup regions. We performed calculations for two different Benchmark problem geometries - UO 2 pin cell and UO 2 PWR fuel assembly. The results obtained with two mentioned 2D spectral codes are presented for burnup dependency of infinite multiplication factor, isotopic concentration of important materials and for local peaking factor vs. burnup (in case of fuel assembly calculation).(author)

Reactivity Insertion Accident (RIA) Capability Status in the BISON Fuel Performance Code

Energy Technology Data Exchange (ETDEWEB)

Williamson, Richard L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Folsom, Charles Pearson [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pastore, Giovanni [Idaho National Lab. (INL), Idaho Falls, ID (United States); Veeraraghavan, Swetha [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-05-01

One of the Challenge Problems being considered within CASL relates to modelling and simulation of Light Water Reactor LWR) fuel under Reactivity Insertion Accident (RIA) conditions. BISON is the fuel performance code used within CASL for LWR fuel under both normal operating and accident conditions, and thus must be capable of addressing the RIA challenge problem. This report outlines required BISON capabilities for RIAs and describes the current status of the code. Information on recent accident capability enhancements, application of BISON to a RIA benchmark exercise, and plans for validation to RIA behavior are included.

Preliminary Assessment of Spatial Competition in the Market for E85

Energy Technology Data Exchange (ETDEWEB)

Clinton, Bentley [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2017-02-01

Anecdotal evidence suggests retail E85 prices may track retail gasoline prices rather than wholesale costs. This indicates E85 prices may be higher than they would be if priced on a cost basis hence limiting adoption by some price-sensitive consumers. Using publicly available and proprietary E83 and regular gasoline price data, we examine pricing behavior in the market for E85. Specifically, we assess the extent to which local retail competition in E85 markets decreases E85 retail prices. Results of econometric analysis suggest that higher levels of retail competition (measured in terms of station density) are associated with lower E85 prices at the pump. While more precise causal estimates may be produced from more comprehensive data, this study is the first to our knowledge that estimates the spatial competition dimension of E85 pricing behavior by firms. This is an initial presentation; a related technical report is also available.

Quantitative Analysis of Kr-85 Fission Gas Release from Dry Process for the Treatment of Spent PWR Fuel

International Nuclear Information System (INIS)

Park, Geun Il; Cho, Kwang Hun; Lee, Dou Youn; Lee, Jung Won; Park, Jang Jin; Song, Kee Chan

2007-01-01

As spent UO 2 fuel oxidizes to U 3 O 8 by air oxidation, a corresponding volume expansion separate grains, releasing the grain-boundary inventory of fission gases. Fission products in spent UO 2 fuel can be distributed in three major regions : the inventory in fuel-sheath gap, the inventory on grain boundaries and the inventory in UO 2 matrix. Release characteristic of fission gases depends on its distribution amount in three regions as well as spent fuel burn-up. Oxidation experiments of spent fuel at 500 .deg. C gives the information of fission gases inventory in spent fuel, and further annealing experiments at higher temperature produces matrix inventory of fission gases on segregated grain. In previous study, fractional release characteristics of Kr- 85 during OREOX (Oxidation and REduction of Oxide fuel) treatment as principal key process for recycling spent PWR fuel via DUPIC cycle have already evaluated as a function of fuel burn-up with 27.3, 35 and 65 MWd/tU. In this paper, new release experiment results of Kr-85 using spent fuel with burn- up of 58 GWd/tU are included to evaluate the fission gas release behavior. As a point of summary in fission gases release behavior, the quantitative analysis of Kr- 85 release characteristics from various spent fuels with different burn-up during voloxidation and OREOX process were reviewed

Fuel analysis code FAIR and its high burnup modelling capabilities

International Nuclear Information System (INIS)

Prasad, P.S.; Dutta, B.K.; Kushwaha, H.S.; Mahajan, S.C.; Kakodkar, A.

1995-01-01

A computer code FAIR has been developed for analysing performance of water cooled reactor fuel pins. It is capable of analysing high burnup fuels. This code has recently been used for analysing ten high burnup fuel rods irradiated at Halden reactor. In the present paper, the code FAIR and its various high burnup models are described. The performance of code FAIR in analysing high burnup fuels and its other applications are highlighted. (author). 21 refs., 12 figs

User's guide for the REBUS-3 fuel cycle analysis capability

Energy Technology Data Exchange (ETDEWEB)

Toppel, B.J.

1983-03-01

REBUS-3 is a system of programs designed for the fuel-cycle analysis of fast reactors. This new capability is an extension and refinement of the REBUS-3 code system and complies with the standard code practices and interface dataset specifications of the Committee on Computer Code Coordination (CCCC). The new code is hence divorced from the earlier ARC System. In addition, the coding has been designed to enhance code exportability. Major new capabilities not available in the REBUS-2 code system include a search on burn cycle time to achieve a specified value for the multiplication constant at the end of the burn step; a general non-repetitive fuel-management capability including temporary out-of-core fuel storage, loading of fresh fuel, and subsequent retrieval and reloading of fuel; significantly expanded user input checking; expanded output edits; provision of prestored burnup chains to simplify user input; option of fixed-or free-field BCD input formats; and, choice of finite difference, nodal or spatial flux-synthesis neutronics in one-, two-, or three-dimensions.

Rod consolidation of RG and E's [Rochester Gas and Electric Corporation] spent PWR [pressurized water reactor] fuel

International Nuclear Information System (INIS)

Bailey, W.J.

1987-05-01

The rod consolidation demonstration involved pulling the fuel rods from five fuel assemblies from Unit 1 of RG and E's R.E. Ginna Nuclear Power Plant. Slow and careful rod pulling efforts were used for the first and second fuel assemblies. Rod pulling then proceeded smoothly and rapidly after some minor modifications were made to the UST and D consolidation equipment. The compaction ratios attained ranged from 1.85 to 2.00 (rods with collapsed cladding were replaced by dummy rods in one fuel assembly to demonstrate the 2:1 compaction ratio capability). This demonstration involved 895 PWR fuel rods, among which there were some known defective rods (over 50 had collapsed cladding); no rods were broken or dropped during the demonstration. However, one of the rods with collapsed cladding unexplainably broke during handling operations (i.e., reconfiguration in the failed fuel canister), subsequent to the rod consolidation demonstration. The broken rod created no facility problems; the pieces were encapsulated for subsequent storage. Another broken rod was found during postdemonstration cutting operations on the nonfuel-bearing structural components from the five assemblies; evidence indicates it was broken prior to any rod consolidation operations. During the demonstration, burnish-type lines or scratches were visible on the rods that were pulled; however, experience indicates that such lines are generally produced when rods are pulled (or pushed) through the spacer grids. Rods with collapsed cladding would not enter the funnel (the transition device between the fuel assembly and the canister that aids in obtaining high compaction ratios). Reforming of the flattened areas of the cladding on those rods was attempted to make the rod cross sections more nearly circular; some of the reformed rods passed through the funnel and into the canister

Oxygenated fuel (M-85) behavior in the subsurface -- A Laboratory scale investigation

International Nuclear Information System (INIS)

Donaldson, C.R.; Barker, J.F.; Chatzis, I.

1993-01-01

M-85 is an oxygenated fuel consisting of 85% methanol and 15% gasoline. The complete miscibility of methanol with water may lead to a significantly different source behavior and contamination scenario for M-85 relative to a conventional gasoline. A laboratory investigation involving phase equilibria, cosolvency and column experiments was designed to assess the subsurface behavior of M-85 in comparison to API PS-6 gasoline. Liquid-liquid equilibrium determinations have indicated that unlike PS-6, which is essentially immiscible with water, M-85 would behave as a single miscible phase with groundwater under certain conditions. However, as mixing with groundwater proceeded, two distinct, immiscible phases would result. Column experiments involved the injection of a slug of M-85 or PS-6 onto a saturated, packed column of Borden sand. Aqueous BTEX and methanol breakthrough curves were prepared based on column effluent analyses. Subsequent soil sample analyses provided information regarding the residual gasoline phase distributions from each source. The results of the column experiments indicated that the groundwater contamination arising from an M-85 source would be more complex than from PS-6. The plume of dissolved organic compounds migrating from an M-85 source was characterized by a high methanol content front and associated enhanced BTEX concentrations relative to PS-6, due to methanol's cosolubility effects

Alternative Fuels Data Center: Ethanol Fueling Stations

Science.gov (United States)

... More in this section... Ethanol Basics Benefits & Considerations Stations Locations Infrastructure fueling stations by location or along a route. Infrastructure Development Learn about ethanol fueling infrastructure; codes, standards, and safety; and ethanol equipment options. Maps & Data E85 Fueling Station

Improvements in TREAT hodoscope fuel-motion capabilities

International Nuclear Information System (INIS)

Fink, C.L.; Boyar, R.E.; Eichholz, J.J.; DeVolpi, A.

1982-01-01

The fast-neutron detection system of the hadoscope has been a major ingredient in the success of the hodoscope as a fuel-motion monitoring device. While the original Hornyak-button detector system has met most of the current fuel-motion needs, the more stringent requirements of improved reactor-safety codes, and of new experimental test facilities necessitate improved detection capabilities. Development efforts have centered on three areas: the construction of an array of proton-recoil proportional counters to be used in conjunction with the Hornyak-button detectors, the upgrading of the Hornyak-button detectors to increase linearity and signal-to-background ratio, and the intercalibration of detectors using a modified horizontal and a new vertical scan system

Increasing TRIGA fuel lifetime with 12 wt.% U TRIGA fuel

Energy Technology Data Exchange (ETDEWEB)

Naughton, W F; Cenko, M J; Levine, S H; Witzig, W F [Pennsylvania State University (United States)

1974-07-01

In-core fuel management studies have been performed for the Penn State Breazeale Reactor (PSBR) wherein 12 wt % U fuel elements are used to replace the standard 8.5 wt % U TRIGA fuel. The core configuration used to develop a calculational model was a 90-element hexagonal array, which is representative of the PSBR core, and consists of five hexagonal rings surrounding a central thimble containing water. The technique employed for refueling the core fully loaded with 8.5 wt % U fuel involves replacing 8.5 wt % U fuel with 12 wt % U fuel using an in-out reloading scheme. A batch reload consists of 6 new 12 wt % U fuel elements. Placing the 12 wt % U fuel in the B ring produces fuel temperatures ({approx}450 {sup o}C) that are well below the 800{sup o}C maximum limitation when the PSBR is operating at its maximum allowed power of 1 Megawatt. The advantages of using new 12 wt % U fuel to replace the burned up 8.5 wt % U fuel in the B ring over refueling strictly with 8.5 wt % U-Zr TRIGA fuel are clearly delineated in Table 1 where cost calculations used the General Atomic pre-1972 prices for TRIGA fuel, i.e., $1500 and $1650 for an 8.5 and 12 wt % U fuel element, respectively. Experimental results obtained to date utilizing the 12 wt % U fuel elements agree with the computed results. (author)

Preliminary Assessment of Spatial Competition in the Market for E85: Presentation Supplement

Energy Technology Data Exchange (ETDEWEB)

Clinton, Bentley [National Renewable Energy Lab. (NREL), Golden, CO (United States); Johnson, Caley [National Renewable Energy Lab. (NREL), Golden, CO (United States); Moriarty, Kristi [National Renewable Energy Lab. (NREL), Golden, CO (United States); Newes, Emily [National Renewable Energy Lab. (NREL), Golden, CO (United States); Vimmerstedt, Laura [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2017-02-01

Anecdotal evidence suggests retail E85 prices may track retail gasoline prices rather than wholesale costs. This indicates E85 prices may be higher than they would be if priced on a cost basis hence limiting adoption by some price-sensitive consumers. Using publicly available and proprietary E85 and regular gasoline price data, we examine pricing behavior in the market for E85. Specifically, we assess the extent to which local retail competition in E85 markets decreases E85 retail prices. Results of econometric analysis suggest that higher levels of retail competition (measured in terms of station density) are associated with lower E85 prices at the pump. While more precise causal estimates may be produced from more comprehensive data, this study is the first to our knowledge that estimates the spatial competition dimension of E85 pricing behavior by firms. This technical report elaborates on a related presentation.

Capability of minor nuclide confinement in fuel reprocessing

International Nuclear Information System (INIS)

Fujine, Sachio; Uchiyama, Gunzo; Mineo, Hideaki; Kihara, Takehiro; Asakura, Toshihide

1999-01-01

Experiment with spent fuels has started with the small scale reprocessing facility in NUCEF-BECKY αγ cell. Primary purpose of the experiment is to study the capability of long-lived nuclide confinement both in the PUREX flow sheet applied to the large scale reprocessing plant and also in the PARC (Partitioning Conundrum key process) flow sheet which is our proposal as a simplified reprocessing of one cycle extraction system. Our interests in the experiment are the behaviors of minor long-lived nuclides and the behaviors of the heterogeneous substances, such as sedimentation in the dissolver, organic cruds in the extraction banks. The significance of those behaviors will be assessed from the standpoint of the process safety of reprocessing for high burn-up fuels and MOX fuels. (author)

Control decisions for 3H, 14C, 85Kr, and 129I released from the commercial fuel cycle

International Nuclear Information System (INIS)

Thomas, T.R.; Brown, R.A.

1985-01-01

The effects of complete release of 3 H, 14 C, 85 Kr and 129 I from operating a 400-GWe fuel cycle for 100 years are shown. The postulated accrued health effects (HE) from 14 C and 129 I appear large; however, these numbers are insignificant when compared to the 176 billion cancer deaths that would occur from all causes in the 10,000-year reference period. The percent increase in global cancer deaths would be no greater than 5 x 10 -5 % for each of the radionuclides. Based on the 1980 inventory of each radionuclide in the environment, complete release for 100 years from a 400-GWe fuel cycle would not increase the 3 H or 14 C inventories, however, large increases in 85 Kr and 129 I inventories would occur. The effects, besides dose impacts, of large increases in inventory are unknown and serve only as warning flags that should be taken into consideration. Only 129 I releases from a fuel reprocessing plant would exceed the allowable maximum exposed individual dose limit and 85 Kr and 129 I would exceed the allowable release limit. The effects of controlled releases from commercial fuel reprocessing plants serving a 400-GWe fuel cycle for 100 years are also shown

Assessment of the prediction capability of the TRANSURANUS fuel performance code on the basis of power ramp tested LWR fuel rods

International Nuclear Information System (INIS)

Pastore, G.; Botazzoli, P.; Di Marcello, V.; Luzzi, L.

2009-01-01

The present work is aimed at assessing the prediction capability of the TRANSURANUS code for the performance analysis of LWR fuel rods under power ramp conditions. The analysis refers to all the power ramp tested fuel rods belonging to the Studsvik PWR Super-Ramp and BWR Inter-Ramp Irradiation Projects, and is focused on some integral quantities (i.e., burn-up, fission gas release, cladding creep-down and failure due to pellet cladding interaction) through a systematic comparison between the code predictions and the experimental data. To this end, a suitable setup of the code is established on the basis of previous works. Besides, with reference to literature indications, a sensitivity study is carried out, which considers the 'ITU model' for fission gas burst release and modifications in the treatment of the fuel solid swelling and the cladding stress corrosion cracking. The performed analyses allow to individuate some issues, which could be useful for the future development of the code. Keywords: Light Water Reactors, Fuel Rod Performance, Power Ramps, Fission Gas Burst Release, Fuel Swelling, Pellet Cladding Interaction, Stress Corrosion Cracking

The first car fuel of the post-petroleum era

International Nuclear Information System (INIS)

Willot, D.

2006-01-01

French authorities have decided to back the development and the use of ethanol. A program called Flex-fuel-2010 favours the production and a wide use of the E85 fuel for transport in France. It appears that the volume of France's exports in cereals and beet sugar represent, in ethanol equivalent, 70% of our needs in car fuel for private transport. Oil companies and supermarket chains compel themselves to open more than 500 selling spots of E85 fuel throughout France in 2007. In 2007, car manufacturers like Renault and PSA will begin to sell cars running on E85 at a price equivalent to that of current cars. Fiscal incentives are also expected to favour the use of E85. (A.C.)

California GAMA Special Study. Development of a Capability for the Analysis of Krypton-85 in Groundwater Samples

Energy Technology Data Exchange (ETDEWEB)

Visser, Ate [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bibby, Richard K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Moran, Jean E. [California State Univ. (CalState), Long Beach, CA (United States); Singleton, Michael J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Esser, Bradley K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-06-01

A capability for the analysis of krypton-85 (⁸⁵Kr) in groundwater samples was developed at LLNL. Samples are collected by extracting gas from 2000-4000 L of groundwater at the well, yielding approximately 0.2 cm³ STP krypton. Sample collection takes 1 to 4 hours. Krypton is purified in the laboratory using a combination of molecular sieve and activated charcoal traps, and transferred to a liquid scintillation vial. The ⁸⁵Kr activity is measured by liquid scintillation on a Quantulus 1220 liquid scintillation counter from PerkinElmer. The detection limit for a typical 0.2 cm³Kr sample size is 11% of the present day activity in air, corresponding to the decay corrected activity in air in 1987. The typical measurement uncertainty is below 10% for recently recharged samples. Six groundwater samples were collected, purified and counted. ⁸⁵Kr was not detected in any of the samples counted at LLNL. ⁸⁵Kr was detected by the low level counting laboratory of Bern University in all samples between 1.5 and 6.6 decays per minute per cm³ krypton, corresponding to decay corrected activities in air between 1971 and 1985. The new capability is an excellent complement to tritium-helium, expanding the existing suite of age dating tools available to the GAMA program (³⁵S, ³H/³He, ¹⁴C and radiogenic helium). ⁸⁵Kr can replace ³H/³He in settings where ³H/³He ages are impossible to determine (for example where terrigenic helium overwhelms tritiogenic helium) and provides additional insight into travel time distributions in complex mixed groundwater systems.

Capability and dependency in the Newcastle 85+ cohort study. Projections of future care needs.

Science.gov (United States)

Jagger, Carol; Collerton, Joanna C; Davies, Karen; Kingston, Andrew; Robinson, Louise A; Eccles, Martin P; von Zglinicki, Thomas; Martin-Ruiz, Carmen; James, Oliver F W; Kirkwood, Tom B L; Bond, John

2011-05-04

Little is known of the capabilities of the oldest old, the fastest growing age group in the population. We aimed to estimate capability and dependency in a cohort of 85 year olds and to project future demand for care. Structured interviews at age 85 with 841 people born in 1921 and living in Newcastle and North Tyneside, UK who were permanently registered with participating general practices. Measures of capability included were self-reported activities of daily living (ADL), timed up and go test (TUG), standardised mini-mental state examination (SMMSE), and assessment of urinary continence in order to classify interval-need dependency. To project future demand for care the proportion needing 24-hour care was applied to the 2008 England and Wales population projections of those aged 80 years and over by gender. Of participants, 62% (522/841) were women, 77% (651/841) lived in standard housing, 13% (106/841) in sheltered housing and 10% (84/841) in a care home. Overall, 20% (165/841) reported no difficulty with any of the ADLs. Men were more capable in performing ADLs and more independent than women. TUG validated self-reported ADLs. When classified by 'interval of need' 41% (332/810) were independent, 39% (317/810) required help less often than daily, 12% (94/810) required help at regular times of the day and 8% (67/810) required 24-hour care. Of care-home residents, 94% (77/82) required daily help or 24-hour care. Future need for 24-hour care for people aged 80 years or over in England and Wales is projected to increase by 82% from 2010 to 2030 with a demand for 630,000 care-home places by 2030. This analysis highlights the diversity of capability and levels of dependency in this cohort. A remarkably high proportion remain independent, particularly men. However a significant proportion of this population require 24-hour care at home or in care homes. Projections for the next 20 years suggest substantial increases in the number requiring 24-hour care due to

Spent nuclear fuel shipping cask handling capabilities of commercial light water reactors

International Nuclear Information System (INIS)

Daling, P.M.; Konzek, G.J.; Lezberg, A.J.; Votaw, E.F.; Collingham, M.I.

1985-04-01

This report describes an evaluation of the cask handling capabilities of those reactors which are operating or under construction. A computerized data base that includes cask handling information was developed with information from the literature and utility-supplied data. The capability of each plant to receive and handle existing spent fuel shipping casks was then evaluated. Modal fractions were then calculated based on the results of these evaluations and the quantities of spent fuel projected to be generated by commercial nuclear power plants through 1998. The results indicated that all plants are capable of receiving and handling truck casks. Up to 118 out of 130 reactors (91%) could potentially handle the larger and heavier rail casks if the maximum capability of each facility is utilized. Design and analysis efforts and physical modifications to some plants would be needed to achieve this high rail percentage. These modifications would be needed to satisfy regulatory requirements, increase lifting capabilities, develop rail access, or improve other deficiencies. The remaining 12 reactors were determined to be capable of handling only the smaller truck casks. The percentage of plants that could receive and handle rail casks in the near-term would be reduced to 64%. The primary reason for a plant to be judged incapable of handling rail casks in the near-term was a lack of rail access. The remaining 36% of the plants would be limited to truck shipments. The modal fraction calculations indicated that up to 93% of the spent fuel accumulated by 1998 could be received at federal storage or disposal facilities via rail (based on each plant's maximum capabilities). If the near-term cask handling capabilities are considered, the rail percentage is reduced to 62%

Spent fuel reprocessing system security engineering capability maturity model

International Nuclear Information System (INIS)

Liu Yachun; Zou Shuliang; Yang Xiaohua; Ouyang Zigen; Dai Jianyong

2011-01-01

In the field of nuclear safety, traditional work places extra emphasis on risk assessment related to technical skills, production operations, accident consequences through deterministic or probabilistic analysis, and on the basis of which risk management and control are implemented. However, high quality of product does not necessarily mean good safety quality, which implies a predictable degree of uniformity and dependability suited to the specific security needs. In this paper, we make use of the system security engineering - capability maturity model (SSE-CMM) in the field of spent fuel reprocessing, establish a spent fuel reprocessing systems security engineering capability maturity model (SFR-SSE-CMM). The base practices in the model are collected from the materials of the practice of the nuclear safety engineering, which represent the best security implementation activities, reflect the regular and basic work of the implementation of the security engineering in the spent fuel reprocessing plant, the general practices reveal the management, measurement and institutional characteristics of all process activities. The basic principles that should be followed in the course of implementation of safety engineering activities are indicated from 'what' and 'how' aspects. The model provides a standardized framework and evaluation system for the safety engineering of the spent fuel reprocessing system. As a supplement to traditional methods, this new assessment technique with property of repeatability and predictability with respect to cost, procedure and quality control, can make or improve the activities of security engineering to become a serial of mature, measurable and standard activities. (author)

ORNL capability to conduct post irradiation examination of full-length commercial nuclear fuel rods

International Nuclear Information System (INIS)

Spellman, Donald J.

2007-01-01

Hot cells at Oak Ridge National Laboratory (ORNL) are nearing completion of a multi-year upgrade program to implement 21. century capabilities to meet the examination demands for higher burnup fuels and the future demands that will come from fuel recycling programs. Fuel reliability and zero tolerance for fuel failure is more than an industry goal. Fuel reliability is becoming a requirement that supports the renaissance of nuclear power generation. Thus, fuel development and management of new forms of waste that will come from programs such as the Global Nuclear Energy Partnership (GNEP) will require extensive use of the flexible, high-quality, technically advanced hot cells at ORNL. ORNL has the capability to perform post irradiation examination (PIE) of irradiated commercial nuclear fuel rods and the management structure to ensure a timely, cost-effective result. ORNL can: 1) Handle the transportation issues, 2) Perform macroscopic fuel rod examinations, 3) Perform microscopic fuel and clad examinations, and 4) Manage legacy material and waste disposal issues from PIE activities. All four of these items will be managed in a way that allows the customer day-to-day access to the results and data. Hot cell examination equipment that is necessary to determine the characteristics and performance of irradiated materials must operate in a hostile environment and is subject to long-term degradation that may result in reliability and quality assurance (QA) issues. ORNL has modernized its hot cell nuclear fuel examination equipment, installing state-of-the-art automated examination equipment and data gathering capabilities. ORNL is planning a major commitment to nuclear fuel examination and development, and future improvements will continue to be made over the next few years. (author)

Overview of fuel testing capabilities at the OECD Halden reactor project

Energy Technology Data Exchange (ETDEWEB)

Wiesenack, W [Institutt for Atomenergi, Halden (Norway). OECD Halden Reaktor Projekt

1994-12-31

Fuel performance and reliability investigations at the OECD Haiden Reactor Project are described. They are supported by a variety of irradiation rigs, suitable irradiation techniques and a range of instrumentation. Testing capabilities and applications are mainly aimed at exploring mechanisms of fuel behaviour and high burnup. Examples of fuel performance taken from data provided by the Halden Project for the IAEA Co-ordinated Research Programme FUMEX are presented. A number of heavily instrumented rigs to suit different test objects have been developed: base irradiation rig, gas meter rig, diameter measurement rig, ramp rig, gas flow rig, instrumented fuel assembly. In core-measurements and variety of sensors as : fuel thermocouples, bellows pressure transducers, fuel stack elongation detectors, cladding diameter gauge and cladding elongation detectors have been used. Techniques which make it possible to obtain reliable data for all relevant burnups from beginning-of-life to ultra high exposure reaching 100 Mwd/kg UO{sub 2} are described. 7 figs., 3 refs.

An alternative transportation fuels update : a case study of the developing E85 industry.

Science.gov (United States)

2011-10-01

As the United States imports more than half of its oil and overall consumption continues to climb, : the 1992 Energy Policy Act established the goal of having alternative fuels replace at least ten : percent of petroleum fuels used in the trans...

Simulating the mesoscale transport of krypton-85.

Science.gov (United States)

Felsberg, Anne; Ross, J Ole; Schlosser, Clemens; Kirchner, Gerald

2018-01-01

Due to its half-life, chemical inertness and low solubility in water, radioactive 85 Kr is a valuable tracer for testing the performance of atmospheric dispersion models in simulating long-range transport of pollutants. This paper evaluates the capability of simulating the dispersion of radiokrypton emitted by a nuclear fuel reprocessing plant in north-west France. Three time periods during which elevated activity concentrations of 85 Kr in ground level air were detected in south-west Germany are chosen. Simulations have been performed using the HYSPLIT code and the European Centre for Median-Range Weather Forecasts (ECMWF) data base. Although their results show a slight trend of underestimating the measured 85 Kr concentrations, there is a significant correlation and moderate scatter between observations and simulations with about 50% of the results being within a factor of two of the measured concentrations. The simulated travel time distributions provided a valuable tool for providing additional insight into the dispersion of the tracer radionuclides and for identifying potential causes of deviations between measured and calculated concentrations. Copyright © 2017. Published by Elsevier Ltd.

Handbook for Handling, Storing, and Dispensing E85 and Other Ethanol-Gasoline Blends

Energy Technology Data Exchange (ETDEWEB)

None

2013-09-17

This document serves as a guide for blenders, distributors, sellers, and users of E85 and other ethanol blends above E10. It provides basic information on the proper and safe use of E85 and other ethanol blends and includes supporting technical and policy references.

High efficiency Dual-Cycle Conversion System using Kr-85.

Science.gov (United States)

Prelas, Mark A; Tchouaso, Modeste Tchakoua

2018-04-26

This paper discusses the use of one of the safest isotopes known isotopes, Kr-85, as a candidate fuel source for deep space missions. This isotope comes from 0.286% of fission events. There is a vast quantity of Kr-85 stored in spent fuel and it is continually being produced by nuclear reactors. In using Kr-85 with a novel Dual Cycle Conversion System (DCCS) it is feasible to boost the system efficiency from 26% to 45% over a single cycle device while only increasing the system mass by less than 1%. The Kr-85 isotope is the ideal fuel for a Photon Intermediate Direct Energy Conversion (PIDEC) system. PIDEC is an excellent choice for the top cycle in a DCCS. In the top cycle, ionization and excitation of the Kr-85:Cl gas mixture (99% Kr and 1% Cl) from beta particles creates KrCl* excimer photons which are efficiently absorbed by diamond photovoltaic cells on the walls of the pressure vessels. The benefit of using the DCCS is that Kr-85 is capable of operating at high temperatures in the primary cycle and the residual heat can then be converted into electrical power in the bottom cycle which uses a Stirling Engine. The design of the DCCS begins with a spherical pressure vessel of radius 13.7 cm with 3.7 cm thick walls and is filled with a Kr-85:Cl gas mixture. The inner wall has diamond photovoltaic cells attached to it and there is a sapphire window between the diamond photovoltaic cells and the Kr-85:Cl gas mixture which shields the photovoltaic cells from beta particles. The DCCS without a gamma ray shield has specific power of 6.49 W/kg. A removable 6 cm thick tungsten shield is used to safely limit the radiation exposure levels of personnel. A shadow shield remains in the payload to protect the radiation sensitive components in the flight package. The estimated specific power of the unoptimized system design in this paper is about 2.33 W/kg. The specific power of an optimized system should be higher. The Kr-85 isotope is relatively safe because it

FMEF/experimental capabilities

International Nuclear Information System (INIS)

Burgess, C.A.; Dronen, V.R.

1981-01-01

The Fuels and Materials Examination Facility (FMEF), under construction at the Hanford site north of Richland, Washington, will be one of the most modern facilities offering irradiated fuels and materials examination capabilities and fuel fabrication development technologies. Scheduled for completion in 1984, the FMEF will provide examination capability for fuel assemblies, fuel pins and test pins irradiated in the FFTF. Various functions of the FMEF are described, with emphasis on experimental data-gathering capabilities in the facility's Nondestructive and Destructive examination cell complex

Ethanol: The fuel of the future and its environmental impact

International Nuclear Information System (INIS)

Marek, N.J.; Evanoff, J.

1999-01-01

There are several major environmental benefits associated with using biomass-derived ethanol as a transportation fuel. First, because ethanol is produced from plant material (primarily corn) that uses atmospheric CO 2 for the process of photosynthesis, the combustion of biomass-derived ethanol can be viewed as recycling of CO 2 back into the atmosphere, thereby closing the carbon cycle. Further, emission tests on vehicles using E-85 (a blend of 85% denatured ethanol and 15% gasoline) show significant reductions in hydrocarbon and CO emission levels when compared to their gasoline counterparts. Finally, a recent study comparing greenhouse gas emissions from vehicles using E-10 (a blend of 10% ethanol and 90% gasoline, commonly called gasohol) and E-85 fuel to those using gasoline and diesel fuel has been completed by Argonne National Laboratory. Using the most recent energy input data available, the study concluded that corn-derived ethanol reduces greenhouse gases by 2--3% for E-10, and by over 30% for vehicles using E-85 fuel. Additionally, the state of Illinois, with several other corporate and privates partners, is testing the use of a new fuel formulation called OxyDiesel, a blend of 15% ethanol, diesel fuel, and a special blending additive, that holds considerable promise in reducing harmful tailpipe and greenhouse gas emissions from heavy-duty diesel engines in trucks, buses, and other diesel engine applications

Comparison of thermal capabilities of the fuel assemblies for the WWR-M reactor

International Nuclear Information System (INIS)

Kirsanov, G.A.; Konoplev, K.A.; Findeisen, A.; Shishkina, Zh.A.

1989-01-01

On the basis of measurement results of the WWR-M2, WWR-M3 and WWR-M5 fuel element can temperature in the WWR-M reactor core their thermal capabilities are compared. The use of the WWR-M5 fuel assemblies instead of the WWR-M2 ones in the WWR-M reactor permits to increase specific heat loading by a factor of 2.7. The possibility to increase fuel can temperature up to 110 deg C is confirmed experimentally which corresponds to specific heat loading of 900 kW/l

Computer-controlled on-line gamma analysis for krypton-85

International Nuclear Information System (INIS)

Canuette, R.P.

1980-03-01

85 Kr will be evolved from spent nuclear fuel during both the voloxidation and dissolution processes, so a reliable method for on-line analysis of 85 Kr in the off-gas system is needed. Tritium, 14 C, and 129 I were trapped, and the activity of 85 Kr was then measured using a Li-drifted Ge detector. Equipment used to carry out this analysis is described; the PET computer is used. The 85 Kr evolution rate was correlated with the fuel dissolution rate; the close correlation permits one to monitor the fuel dissolution process. 11 figures

Tolerância do Tifton 85 (Cynodon spp. e da Brachiaria brizantha ao glyphosate Tifton 85 (Cynodon spp. and Brachiaria brizantha tolerance to glyphosate

Directory of Open Access Journals (Sweden)

M.V. Santos

2008-06-01

Full Text Available Objetivou-se avaliar a tolerância de Tifton 85 e Brachiaria brizantha ao glyphosate e verificar o controle de B. brizantha em área de pastagem de Tifton 85 já estabelecida. O delineamento experimental foi em blocos casualizados, com quatro repetições, em que se testaram as doses: 0, 720, 1.440, 2.160 e 2.880 g ha-1 de glyphosate. Cada parcela possuía dimensões de 3,5 m de comprimento por 3,0 m de largura, totalizando 10,5 m², com área útil de 7,5 m ². A eficiência do herbicida no controle de B. brizantha e o nível de intoxicação nas plantas de Tifton 85 foram avaliados 15, 30 e 60 dias após aplicação (DAA, mediante escala de 0 a 100, em que 0 é ausência de controle e/ou intoxicação e 100, controle total ou morte das plantas. Para avaliação da produção e do potencial de rebrota das forrageiras, as plantas de ambas as espécies foram colhidas aos 300 DAA e secas em estufa. Observou-se controle acima de 90% das plantas de B. brizantha a partir das doses de 1.473,75 e 1.721,25 g ha-1 de glyphosate, aos 30 e 60 DAA, respectivamente. As porcentagens de intoxicação das plantas de Tifton 85, referente a estas doses de controle de B. brizantha, foram, respectivamente, de 24,90 e 4,13% aos 30 e 60 DAA. Além disso, aos 60 DAA, para a maior dose avaliada (2.880 g ha-1 de glyphosate foi observada intoxicação das plantas de Tifton 85 de apenas 18,22%. Aos 300 DAA, observou-se ausência de produção de massa seca de B. brizantha a partir da dose de 2.160 g ha-1 do herbicida, devido ao eficiente controle. Os resultados evidenciam maior tolerância das plantas de Tifton 85 ao glyphosate em relação às plantas de B. brizantha, possibilitando o controle desta espécie em pastagem estabelecida de Tifton 85, sem causar danos à forrageira cultivada.This study aimed to evaluate Tifton 85 and Brachiaria brizantha tolerance glyphosate and verity Brachiaria brizantha control in an established Tifton 85 pasture area. Rates of 0; 720; 1

Handbook for Handling, Storing, and Dispensing E85 and Other Ethanol-Gasoline Blends (Book)

Energy Technology Data Exchange (ETDEWEB)

Moriarty, K.

2013-09-01

This document serves as a guide for blenders, distributors, sellers, and users of E85 and other ethanol blends above E10. It provides basic information on the proper and safe use of E85 and other ethanol blends and includes supporting technical and policy references.

Contingency strategy for insufficient full core off load capability in spent fuel pool for Chinshan nuclear power station

International Nuclear Information System (INIS)

Huang, Pinghue

2012-01-01

The spent fuel pool (SFP) at Taiwan Power Company's (TUC's) Chinshan plant lost the full core off load (FCO) capability in 2010, even with the second SFP repacking project to expand the capacity as reported in 12PBNC. The TEPC had originally planned to move some spent fuel assemblies from SFP to dry storage facility, however, the dry storage project had seriously fell behind. Thus, it is required to address insufficient FCO capability, and the following contingency measures have been employed: The first step was to explore whether there was a specific regulatory requirement for FCO capability, and none were identified. Also, the industrial experiences were explored. The refueling strategy is changed from FCO to in-core shuffling. A feasibility evaluation performed indicates the Technical Specifications require: alternate method of decay heat removal, and verification of shutdown margin for each in vessel fuel movement. Specific methods have been successfully established. A safety evaluation for operation without FCO capability was performed, and no safety concerns were identified. The risk for operation without FCO capability was assessed. The previous operational experiences were identified. Moreover, such works are not expected in subsequent cycles. The new fuel vault is used to store new fuel assemblies. The criticality analysis has been performed and some new approaches are proposed to enhance the storage flexibility as reported in 17PBNC. An inter-unit transfer cask has been designed to transfer spent fuel from the SFP of one unit to the other. The FCO capability can be effectively extended for three more years with this consideration. The TPC discussed the contingency strategy with the ROCAEC in May 2006, and the ROCAEC's concurrence was attained. With the proposed strategy, Chinshan units have been operating smoothly

Contingency strategy for insufficient full core off load capability in spent fuel pool for Chinshan nuclear power station

Energy Technology Data Exchange (ETDEWEB)

Huang, Pinghue [Taiwan Power Company, Taipei (China)

2012-03-15

The spent fuel pool (SFP) at Taiwan Power Company's (TUC's) Chinshan plant lost the full core off load (FCO) capability in 2010, even with the second SFP repacking project to expand the capacity as reported in 12PBNC. The TEPC had originally planned to move some spent fuel assemblies from SFP to dry storage facility, however, the dry storage project had seriously fell behind. Thus, it is required to address insufficient FCO capability, and the following contingency measures have been employed: The first step was to explore whether there was a specific regulatory requirement for FCO capability, and none were identified. Also, the industrial experiences were explored. The refueling strategy is changed from FCO to in-core shuffling. A feasibility evaluation performed indicates the Technical Specifications require: alternate method of decay heat removal, and verification of shutdown margin for each in vessel fuel movement. Specific methods have been successfully established. A safety evaluation for operation without FCO capability was performed, and no safety concerns were identified. The risk for operation without FCO capability was assessed. The previous operational experiences were identified. Moreover, such works are not expected in subsequent cycles. The new fuel vault is used to store new fuel assemblies. The criticality analysis has been performed and some new approaches are proposed to enhance the storage flexibility as reported in 17PBNC. An inter-unit transfer cask has been designed to transfer spent fuel from the SFP of one unit to the other. The FCO capability can be effectively extended for three more years with this consideration. The TPC discussed the contingency strategy with the ROCAEC in May 2006, and the ROCAEC's concurrence was attained. With the proposed strategy, Chinshan units have been operating smoothly.

Structure and origin of the 85 degrees E ridge

Digital Repository Service at National Institute of Oceanography (India)

Ramana, M.V.; Subrahmanyam, V.; Chaubey, A.K.; Ramprasad, T.; Sarma, K.V.L.N.S.; Krishna, K.S.; Desa, M.; Murty, G.P.S.; Subrahmanyam, C

The submerged 85 degrees E Ridge in the Bay of Bengal trends approximately N-S between 19 degrees N and 6 degrees N latitudes. Off the southeast coast of Sri Lanka it takes an arcuate shape and seems to terminate with the northweard extension...

Advanced materials for alternative fuel capable directly fired heat engines

Energy Technology Data Exchange (ETDEWEB)

Fairbanks, J.W.; Stringer, J. (eds.)

1979-12-01

The first conference on advanced materials for alternative fuel capable directly fired heat engines was held at the Maine Maritime Academy, Castine, Maine. It was sponsored by the US Department of Energy, (Assistant Secretary for Fossil Energy) and the Electric Power Research Institute, (Division of Fossil Fuel and Advanced Systems). Forty-four papers from the proceedings have been entered into EDB and ERA and one also into EAPA; three had been entered previously from other sources. The papers are concerned with US DOE research programs in this area, coal gasification, coal liquefaction, gas turbines, fluidized-bed combustion and the materials used in these processes or equipments. The materials papers involve alloys, ceramics, coatings, cladding, etc., and the fabrication and materials listing of such materials and studies involving corrosion, erosion, deposition, etc. (LTN)

Capabilities for processing shipping casks at spent fuel storage facilities

International Nuclear Information System (INIS)

Baker, W.H.; Arnett, L.M.

1978-01-01

Spent fuel is received at a storage facility in heavily shielded casks transported either by rail or truck. The casks are inspected, cooled, emptied, decontaminated, and reshipped. The spent fuel is transferred to storage. The number of locations or space inside the building provided to perform each function in cask processing will determine the rate at which the facility can process shipping casks and transfer spent fuel to storage. Because of the high cost of construction of licensed spent fuel handling and storage facilities and the difficulty in retrofitting, it is desirable to correctly specify the space required. In this paper, the size of the cask handling facilities is specified as a function of rate at which spent fuel is received for storage. The minimum number of handling locations to achieve a given throughput of shipping casks has been determined by computer simulation of the process. The simulation program uses a Monte Carlo technique in which a large number of casks are received at a facility with a fixed number of handling locations in each process area. As a cask enters a handling location, the time to process the cask at that location is selected at random from the distribution of process time. Shipping cask handling times are based on experience at the General Electric Storage Facility, Morris, Illinois. Shipping cask capacity is based on the most recent survey available of the expected capability of reactors to handle existing rail or truck casks

E-Learning Capability Maturity Level in Kingdom of Bahrain

Science.gov (United States)

Al-Ammary, Jaflah; Mohammed, Zainab; Omran, Fatima

2016-01-01

Despite the effectiveness of using e-learning, educational institutions are still facing many challenges with the e-learning infrastructure and technical aspects, practices and capabilities, and improvement in learning outcome. Hence, a need for framework to benchmark the e-learning capability maturity level and measure the extent to what it is…

Fuel price impacts and compliance costs associated with the Renewable Fuel Standard (RFS)

International Nuclear Information System (INIS)

Christensen, Adam; Siddiqui, Sauleh

2015-01-01

US policy instruments concerning vehicle biofuels are currently being revisited. For example, as part of an on-going annual Renewable Fuel Standard (RFS) implementation, the Environmental Protection Agency (EPA) requests stakeholder feedback/analysis of programmatic effects, including impacts on gasoline/diesel prices and compliance costs. Motivated by the need for regulatory-specific feedback, a novel regional market model is developed that quantifies price impacts across different regional markets for a number of market variables, including several types of compliance certificates known as Renewable Identification Numbers (RINs). An analysis of the most recent EPA proposal suggests that the D4 (biodiesel) RIN price could rise to >$1.00/RIN. Sensitivity results show that the D4 RIN price is highly sensitive to soybean oil prices, while D5/D6 RIN prices are most sensitive to the volume of E85 consumed. It was found that the projected costs associated with the RFS in 2017 could be reduced by approximately 50% if an additional 600 million gallons of E85 were consumed. The analysis also suggests that the RFS does not dramatically affect the retail price of either gasoline and diesel fuels paid by consumers. - Highlights: • The most recent EPA could cause the biodiesel RIN price to rise to >$1.00/RIN. • D5/D6 RIN prices are most sensitive to the volume of E85 consumed. • Retail prices for fuel do not change dramatically. • 2017 compliance costs could fall by 50% if more E85 were consumed.

Krypton 85 at La Hague; Krypton 85 a La Hague

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

The gaseous effluents from the fuel reprocessing plant of Cogema-La Hague (France) are regularly measured and controlled. This paper reports on three press releases: the one of Cogema from November 6, 1998 concerning the impact of these effluents and the results of {sup 85}Kr measurements performed in the vicinity of the facility, and the two communiques of the French office of protection against ionizing radiations (OPRI) from November 13 and 20, 1998 relative to the environmental and human impacts of the {sup 85}Kr releases from the La Hague facility. (J.S.)

Potential for beneficial use of krypton-85

International Nuclear Information System (INIS)

Tingey, G.L.; Jensen, G.A.; McClanahan, E.D.; Lytle, J.M.; Rising, K.R.

1983-03-01

Large quantities of krypton-85 (about 42 MCi) are contained in stored power-reactor fuels and about 1 MCi/year in fuels processed at each of the Savannah River and Hanford defense fuel-processing plants. This nuclear byproduct could be a significant material resource if used in specialized applications. Recently a technique for implanting krypton in a growing sputter-deposited metallic film has been developed. This yields a stable, high-concentration source of krypton-85 which may have applications for small power generators. Metal deposits containing up to 14 at. % have been prepared that would give a heat source of 0.9 W/cm 3 if fully enriched krypton-85 were implanted. Potential applications for up to 10-W batteries include power for runway lighting and other specialized military applications in remote locations, power for telephone or radiocommunications in the far North, and power for monitoring equipment for tracking animals. Krypton-85 has the advantage of being environmentally the most acceptable heat-producing radioisotope available for power production. 1 figure

Toxic emissions from mobile sources: a total fuel-cycle analysis for conventional and alternative fuel vehicles.

Science.gov (United States)

Winebrake, J J; Wang, M Q; He, D

2001-07-01

Mobile sources are among the largest contributors of four hazardous air pollutants--benzene, 1,3-butadiene, acetaldehyde, and formaldehyde--in urban areas. At the same time, federal and state governments are promoting the use of alternative fuel vehicles as a means to curb local air pollution. As yet, the impact of this movement toward alternative fuels with respect to toxic emissions has not been well studied. The purpose of this paper is to compare toxic emissions from vehicles operating on a variety of fuels, including reformulated gasoline (RFG), natural gas, ethanol, methanol, liquid petroleum gas (LPG), and electricity. This study uses a version of Argonne National Laboratory's Greenhouse Gas, Regulated Emissions, and Energy Use in Transportation (GREET) model, appropriately modified to estimate toxic emissions. The GREET model conducts a total fuel-cycle analysis that calculates emissions from both downstream (e.g., operation of the vehicle) and upstream (e.g., fuel production and distribution) stages of the fuel cycle. We find that almost all of the fuels studied reduce 1,3-butadiene emissions compared with conventional gasoline (CG). However, the use of ethanol in E85 (fuel made with 85% ethanol) or RFG leads to increased acetaldehyde emissions, and the use of methanol, ethanol, and compressed natural gas (CNG) may result in increased formaldehyde emissions. When the modeling results for the four air toxics are considered together with their cancer risk factors, all the fuels and vehicle technologies show air toxic emission reduction benefits.

Co-Optimization of Fuels & Engines: Misfueling Mitigation

Energy Technology Data Exchange (ETDEWEB)

Sluder, C. Scott [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Moriarty, Kristi [National Renewable Energy Lab. (NREL), Golden, CO (United States); Jehlik, Forrest [Argonne National Lab. (ANL), Argonne, IL (United States); West, Brian H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-04-06

This report examines diesel/gasoline misfueling, leaded/unleaded gasoline misfueling, E85/E15/E10 misfueling, and consumer selection of regular grade fuel over premium grade fuel in an effort to evaluate misfueling technologies that may be needed to support the introduction of vehicles optimized for a new fuel in the marketplace. This is one of a series of reports produced as a result of the Co-Optimization of Fuels & Engines (Co-Optima) project, a Department of Energy-sponsored multi-agency project to accelerate the introduction of affordable, scalable, and sustainable biofuels and high-efficiency, low-emission vehicle engines.

Crescimento do capim-tifton 85 sob doses de nitrogênio e alturas de corte Growth analysis of Tifton 85 bermudagrass under nitrogen fertilization and plant height

Directory of Open Access Journals (Sweden)

Odilon Gomes Pereira

2012-01-01

Full Text Available Objetivou-se avaliar os índices de crescimento do capim-tifton 85 adubado com quatro doses de nitrogênio (0, 33, 66, 100, e 133 kg/ha de N e colhido em três alturas da planta (30, 40 e 50 cm. O delineamento experimental utilizado foi inteiramente casualizado em esquema de parcelas subdivididas com três repetições. As doses de nitrogênio corresponderam às parcelas e as alturas na data de corte, às subparcelas. Para todas as variáveis analisadas, a interação dose de N × altura da planta não foi significativa. A taxa assimilatória líquida e a taxa de crescimento relativo do capim-tifton 85 aumentaram com as doses de nitrogênio. A razão de área foliar (RAF decresceu linearmente com a altura de corte das plantas, mas aumentou, também de forma linear, com a dose de nitrogênio. De modo linear, a razão de peso foliar decresceu com a altura de corte da planta forrageira e aumentou com a dose de nitrogênio. A área foliar específica do capim-tifton 85 foi influenciada de forma linear e positiva apenas pela adubação nitrogenada. O índice de área foliar (IAF do capim-tifton 85 aumentou cerca de 0,05 unidade a cada centímetro de incremento na altura de corte das plantas. Houve resposta quadrática da dose de nitrogênio no IAF do capim-tifton 85. O acréscimo na altura do capim-tifton 85 na época do corte reduz a participação de lâmina foliar na forragem. A adubação nitrogenada aumenta a taxa de crescimento do capim-tifton 85, portanto, para assegurar colheita eficiente da forragem, ao aumentar a dose de nitrogênio, é necessário reduzir o intervalo de colheita.The objective this study was to evaluate the growth rates of Tifton 85 bermudagrass under four nitrogen levels (0, 33, 66, 100, and 133 kg/ha N and harvested at three plant heights (30, 40 and 50 cm. The experimental design was completely randomized in a split plot scheme with three replications. Nitrogen rates were set in the plots and plants heights in the

Developing A/E Capabilities

International Nuclear Information System (INIS)

Gonzalez, A.; Gurbindo, J.

1987-01-01

During the last few years, the methods used by EMPRESARIOS AGRUPADOS and INITEC to perform Architect-Engineering work in Spain for nuclear projects has undergone a process of significant change in project management and engineering approaches. Specific practical examples of management techniques and design practices which represent a good record of results will be discussed. They are identified as areas of special interest in developing A/E capabilities for nuclear projects . Command of these areas should produce major payoffs in local participation and contribute to achieving real nuclear engineering capabities in the country. (author)

Nuclear fuel fabrication - developing indigenous capability

International Nuclear Information System (INIS)

Gupta, U.C.; Jayaraj, R.N.; Meena, R.; Sastry, V.S.; Radhakrishna, C.; Rao, S.M.; Sinha, K.K.

1997-01-01

Nuclear Fuel Complex (NFC), established in early 70's for production of fuel for PHWRs and BWRs in India, has made several improvements in different areas of fuel manufacturing. Starting with wire-wrap type of fuel bundles, NFC had switched over to split spacer type fuel bundle production in mid 80's. On the upstream side slurry extraction was introduced to prepare the pure uranyl nitrate solution directly from the MDU cake. Applying a thin layer of graphite to the inside of the tube was another modification. The Complex has developed cost effective and innovative techniques for these processes, especially for resistance welding of appendages on the fuel elements which has been a unique feature of the Indian PHWR fuel assemblies. Initially, the fuel fabrication plants were set-up with imported process equipment for most of the pelletisation and assembly operations. Gradually with design and development of indigenous equipment both for production and quality control, NFC has demonstrated total self reliance in fuel production by getting these special purpose machines manufactured indigenously. With the expertise gained in different areas of process development and equipment manufacturing, today NFC is in a position to offer know-how and process equipment at very attractive prices. The paper discusses some of the new processes that are developed/introduced in this field and describes different features of a few PLC based automatic equipment developed. Salient features of innovative techniques being adopted in the area Of UO 2 powder production are also briefly indicated. (author)

Disposal of Kr-85 separated from the dissolver off-gas of a reprocessing plant for LWR fuels

International Nuclear Information System (INIS)

Nommensen, O.

1981-08-01

The principle of the radiation protection to keep the radiation load of the population as low as possible requires the development of methods for retaining the radionuclide Krypton 85 seperated off the dissolver waste gas of future reprocessing plants for LWR-nuclear fuel elements. In a recommendation of the RSK the long-termed storage of the Kr-85 in a pressure gas bottle and the marine disposal we considered to be disposal methods low in risk. The present work develops a concept for both of the disposal methods and demonstrates their technical feasibility. The comparison of the cost estimations effected for both of the disposal methods shows that the costs related with the marine disposal of the pressure gas bottles amounting to 1.90 DM/kg of reprocessed U fall by the factor 10 below the costs that result from the surface storage of the bottles. In both cases was referred to a reprocessing capacity of 1400 t U/a corresponding to 50 GW installed nuclear power, thereby accumulating approximately 629 PBq (17 MCi) Kr-85 per year. Both concepts project the seperated radioactive inert gas to be filled in pressure gas bottles in a low temperature rectification plant. Each of the 85 bottles to be filled per year contains 7.4 PBq (200 kCi) Kr-85. (orig./HP) [de

Environmental aspects of ethanol-based fuels from Brassica carinata. A case study of second generation ethanol

International Nuclear Information System (INIS)

Gonzalez-Garcia, Sara; Moreira, M'a Teresa; Feijoo, Gumersindo; Gasol, Carles M.; Gabarrell, Xavier; Rieradevall, Joan

2009-01-01

One of the main challenges faced by mankind in the 21st century is to meet the increasing demand for energy requirements by means of a more sustainable energy supply. In countries that are net fossil fuel importers, expectation about the benefit of using alternative fuels on reducing oil imports is the primary driving force behind efforts to promote its production and use. Spain is scarce in domestic energy sources and more than 50% of the energy used is fossil fuel based. The promotion of renewable energies use is one of the principal vectors in the Spanish energy policy. Selected herbaceous crops such as Brassica carinata are currently under study as potential energy sources. Its biomass can be considered as potential feedstock to ethanol conversion by an enzymatic process due to the characteristics of its composition, rich in cellulose and hemicellulose. This paper aims to analyse the environmental performance of two ethanol-based fuel applications (E10 and E85) in a passenger car (E10 fuel: a mixture of 10% ethanol and 90% gasoline by volume; E85 fuel: a mixture of 85% ethanol and 15% gasoline by volume) as well as their comparison with conventional gasoline as transport fuel. Two types of functional units are applied in this study: ethanol production oriented and travelling distance oriented functional units in order to reflect the availability or not of ethanol supply. E85 seems to be the best alternative when ethanol production based functional unit is considered in terms of greenhouse gas (GHG) emissions and E10 in terms of non-renewable energy resources use. Nevertheless, E85 offers the best environmental performance when travelling distance oriented functional unit is assumed in both impacts. In both functional unit perspectives, the use of ethanol-based fuels reduces the global warming and fossil fuels consumption. However, the contributions to other impact indicators (e.g. acidification, eutrophication and photochemical oxidants formation) were lower

A review of e-maintenance capabilities and challenges

OpenAIRE

Adolfo Crespo Marquez; Benoit Iung

2008-01-01

Within the era of e-manufacturing and e-business, e-maintenance provides the opportunity for a new maintenance generation. E-maintenance integrates existing telemaintenance principles, with web-services and modern e-collaboration principles. Collaboration allows not only to share and exchange information but also knowledge and (e)-intelligence. This paper outlines the basic capabilities provided by e-maintenance to companies as well as describes emerging challenges to benefit from these new o...

Verification of the depletion capabilities of the MCNPX code on a LWR MOX fuel assembly

International Nuclear Information System (INIS)

Cerba, S.; Hrncir, M.; Necas, V.

2012-01-01

The study deals with the verification of the depletion capabilities of the MCNPX code, which is a linked Monte-Carlo depletion code. For such a purpose the IV-B phase of the OECD NEA Burnup credit benchmark has been chosen. The mentioned benchmark is a code to code comparison of the multiplication coefficient k eff and the isotopic composition of a LWR MOX fuel assembly at three given burnup levels and after five years of cooling. The benchmark consists of 6 cases, 2 different Pu vectors and 3 geometry models, however in this study only the fuel assembly calculations with two Pu vectors were performed. The aim of this study was to compare the obtained result with data from the participants of the OECD NEA Burnup Credit project and confirm the burnup capability of the MCNPX code. (Authors)

46 CFR 56.50-85 - Tank-vent piping.

Science.gov (United States)

2010-10-01

... of the tanks to vent pipes. (2) Tanks having a comparatively small surface, such as fuel oil settling... 46 Shipping 2 2010-10-01 2010-10-01 false Tank-vent piping. 56.50-85 Section 56.50-85 Shipping... APPURTENANCES Design Requirements Pertaining to Specific Systems § 56.50-85 Tank-vent piping. (a) This section...

A review of e-maintenance capabilities and challenges

Directory of Open Access Journals (Sweden)

Adolfo Crespo Marquez

2008-02-01

Full Text Available Within the era of e-manufacturing and e-business, e-maintenance provides the opportunity for a new maintenance generation. E-maintenance integrates existing telemaintenance principles, with web-services and modern e-collaboration principles. Collaboration allows not only to share and exchange information but also knowledge and (e-intelligence. This paper outlines the basic capabilities provided by e-maintenance to companies as well as describes emerging challenges to benefit from these new operational improvement opportunities

Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicles

Science.gov (United States)

primary fuel or to improve the efficiency of conventional vehicle designs. Hybrid Electric Vehicles Icon cost and emissions with a conventional vehicle. Select Fuel/Technology Electric Hybrid Electric Plug-in Hybrid Electric Natural Gas (CNG) Flex Fuel (E85) Biodiesel (B20) Propane (LPG) Next Vehicle Cost

VOC composition of current motor vehicle fuels and vapors, and collinearity analyses for receptor modeling.

Science.gov (United States)

Chin, Jo-Yu; Batterman, Stuart A

2012-03-01

The formulation of motor vehicle fuels can alter the magnitude and composition of evaporative and exhaust emissions occurring throughout the fuel cycle. Information regarding the volatile organic compound (VOC) composition of motor fuels other than gasoline is scarce, especially for bioethanol and biodiesel blends. This study examines the liquid and vapor (headspace) composition of four contemporary and commercially available fuels: gasoline (gasoline), ultra-low sulfur diesel (ULSD), and B20 (20% soy-biodiesel and 80% ULSD). The composition of gasoline and E85 in both neat fuel and headspace vapor was dominated by aromatics and n-heptane. Despite its low gasoline content, E85 vapor contained higher concentrations of several VOCs than those in gasoline vapor, likely due to adjustments in its formulation. Temperature changes produced greater changes in the partial pressures of 17 VOCs in E85 than in gasoline, and large shifts in the VOC composition. B20 and ULSD were dominated by C(9) to C(16)n-alkanes and low levels of the aromatics, and the two fuels had similar headspace vapor composition and concentrations. While the headspace composition predicted using vapor-liquid equilibrium theory was closely correlated to measurements, E85 vapor concentrations were underpredicted. Based on variance decomposition analyses, gasoline and diesel fuels and their vapors VOC were distinct, but B20 and ULSD fuels and vapors were highly collinear. These results can be used to estimate fuel related emissions and exposures, particularly in receptor models that apportion emission sources, and the collinearity analysis suggests that gasoline- and diesel-related emissions can be distinguished. Copyright © 2011 Elsevier Ltd. All rights reserved.

Refueling Behavior of Flexible Fuel Vehicle Drivers in the Federal Fleet

Energy Technology Data Exchange (ETDEWEB)

Daley, R.; Nangle, J.; Boeckman, G.; Miller, M.

2014-05-01

Federal fleets are a frequent subject of legislative and executive efforts to lead a national transition to alternative fuels and advanced vehicle technologies. Section 701 of the Energy Policy Act of 2005 requires that all dual-fueled alternative fuel vehicles in the federal fleet be operated on alternative fuel 100% of the time when they have access to it. However, in Fiscal Year (FY) 2012, drivers of federal flex fuel vehicles (FFV) leased through the General Services Administration refueled with E85 24% of the time when it was available--falling well short of the mandate. The U.S. Department of Energy's National Renewable Energy Laboratory completed a 2-year Laboratory Directed Research and Development project to identify the factors that influence the refueling behavior of federal FFV drivers. The project began with two primary hypotheses. First, information scarcity increases the tendency to miss opportunities to purchase E85. Second, even with perfect information, there are limits to how far drivers will go out of their way to purchase E85. This paper discusses the results of the project, which included a June 2012 survey of federal fleet drivers and an empirical analysis of actual refueling behavior from FY 2009 to 2012. This research will aid in the design and implementation of intervention programs aimed at increasing alternative fuel use and reducing petroleum consumption.

14 CFR 31.85 - Required basic equipment.

Science.gov (United States)

2010-01-01

... following equipment is required: (a) For all balloons: (1) [Reserved] (2) An altimeter. (3) A rate of climb indicator. (b) For hot air balloons: (1) A fuel quantity gauge. If fuel cells are used, means must be... AIRWORTHINESS STANDARDS: MANNED FREE BALLOONS Operating Limitations and Information § 31.85 Required basic...

Dating of the 85 degrees E Ridge (northeastern Indian Ocean) using marine magnetic anomalies

Digital Repository Service at National Institute of Oceanography (India)

Michael, L.; Krishna, K.S.

underneath the eastern Con- rad Rise on the Antarctic plate. Subsequent geophysical RESEARCH ARTICLES CURRENT SCIENCE, VOL. 100, NO. 9, 10 MAY 2011 1315 studies 5,8 opined that short-lived volcanic activity had ini- tiated the 85°E Ridge in Mahanadi.... Satellite-derived free-air gravity anomaly map of the north- eastern Indian Ocean 24 . Curved strip line indicates continuity of the 85°E Ridge from the Mahanadi Basin to ANS. Few bathymetry con- tours derived from ETOPO5 data are shown in the map. N...

Effects of direct injection timing and blending ratio on RCCI combustion with different low reactivity fuels

International Nuclear Information System (INIS)

Benajes, Jesús; Molina, Santiago; García, Antonio; Monsalve-Serrano, Javier

2015-01-01

Highlights: • E85 requires notable lower premixed energy ratios to achieve a stable combustion. • E10-95 leads to shorter and advanced combustion with higher maximum RoHR peaks. • E20-95, E10-98 and E10-95 reach EURO VI NOx and soot levels for all the engine loads. • E10-95 allows a significant reduction in HC and CO emissions. - Abstract: This work investigates the effects of the direct injection timing and blending ratio on RCCI performance and engine-out emissions at different engine loads using four low reactivity fuels: E10-95, E10-98, E20-95 and E85 (port fuel injected) and keeping constant the same high reactivity fuel: diesel B7 (direct injected). The experiments were conducted using a heavy-duty single-cylinder research diesel engine adapted for dual-fuel operation. All the tests were carried out at 1200 rpm. To assess the blending ratio effect, the total energy delivered to the cylinder coming from the low reactivity fuel was kept constant for the different fuel blends investigated by adjusting the low reactivity fuel mass as required in each case. In addition, a detailed analysis of the air/fuel mixing process has been developed by means of a 1-D in-house developed spray model. Results suggest that notable higher diesel amount is required to achieve a stable combustion using E85. This fact leads to higher NOx levels and unacceptable ringing intensity. By contrast, EURO VI NOx and soot levels are fulfilled with E20-95, E10-98 and E10-95. Finally, the higher reactivity of E10-95 results in a significant reduction in CO and HC emissions, mainly at low load

Mechanisms of spray formation and combustion from a multi-hole injector with E85 and gasoline

Energy Technology Data Exchange (ETDEWEB)

Aleiferis, P.G.; Serras-Pereira, J.; van Romunde, Z. [Department of Mechanical Engineering, University College London (United Kingdom); Caine, J. [Ford Motor Company, Dunton Engineering Centre (United Kingdom); Wirth, M. [Ford Werke GmbH, Merkenich, Cologne (Germany)

2010-04-15

The spray formation and combustion characteristics of gasoline and E85 (85% ethanol, 15% gasoline) have been investigated using a multi-hole injector with asymmetric nozzle-hole arrangement. Experiments were carried out in a quiescent optical chamber using high-speed shadowgraphy (9 kHz) to characterise the spray sensitivity to both injector temperature and ambient pressure in the range of 20-120 C and 0.5, 1.0 bar. Spray-tip penetrations and 'umbrella' spray cone angles were calculated for all conditions. Phase Doppler Anemometry was also used to measure droplet sizes in the core of one of the spray plumes, 25 mm below the injector tip. To study the effect of fuel properties on vaporisation and mixture preparation under realistic operating conditions, a separate set of experiments was carried out in a direct-injection spark-ignition optical engine. The engine was run at 1500 RPM under cold and fully warmed-up conditions (20 C and 90 C) at part load and full load (0.5 and 1.0 bar intake pressure). Floodlit laser Mie-scattering images of the sprays on two orthogonal planes corresponding to the swirl and tumble planes of in-cylinder flow motion were acquired to study the full injection event and post-injection mixing stage. These were used to make comparisons with the static chamber sprays and to quantify the liquid-to-vapour phase evaporation process for both fuels by calculating the projected 'footprint' of the sprays at different conditions. Analysis of the macroscopic structure and turbulent primary break-up properties of the sprays was undertaken in light of jet exit conditions described in terms of non-dimensional numbers. The effects on stoichiometric combustion were investigated by imaging the natural flame chemiluminescence through the engine's piston crown (swirl plane) and by post-processing to derive flame growth rates and trajectories of flame motion. (author)

Expansion of the capabilities of the GA-4 legal weight truck spent fuel shipping cask

International Nuclear Information System (INIS)

Zimmer, A.; Razvi, J.; Johnson, L.; Welch, B.; Lancaster, D.

2004-01-01

General Atomics (GA) has developed the Model GA-4 Legal Weight Truck Spent Fuel Cask, a high capacity cask for the transport of four PWR spent fuel assemblies, and obtained a Certificate of Compliance (CoC No. 9226) in 1998 from the US Nuclear Regulatory Commission (NRC). The currently authorized contents in this CoC however, are much more limiting than the actual capability of the GA-4 cask to transport spent PWR fuel assemblies. The purpose of this paper is to show how the authorized contents can be significantly expanded by additional analyses without any changes to the physical design of the package. Using burnup credit per ISG-8 Rev. 2, the authorized contents can be significantly expanded by increasing the maximum enrichment as the burnup increases. Use of burnup credit eliminates much of the criticality imposed limits on authorized package contents, but shielding still limits the use of the cask for the higher burnup, short cooled fuel. By downloading to two assemblies and using shielding inserts, even the high burnup fuel with reasonable cooling times can be transported

Características morfogênicas e estruturais do capim-tifton 85 sob doses de nitrogênio e alturas de corte Morphogenic and structural characteristics of tifton 85 bermudagrass under different nitrogen doses and harvesting heights

Directory of Open Access Journals (Sweden)

Odilon Gomes Pereira

2011-09-01

Full Text Available Objetivou-se avaliar características morfogênicas e estruturais do capim-tifton 85 adubado com nitrogênio nas doses de 0, 33, 66, 100 ou 133 kg/ha.ano em três alturas à data de corte (30, 40 ou 50 cm. O delineamento foi inteiramente casualizado em esquema de parcelas subdivididas com três repetições. As doses de nitrogênio (N corresponderam às parcelas e as alturas ao tempo de corte, às subparcelas. A taxa de aparecimento foliar do capim-tifton 85 foi influenciada de forma negativa pela altura da planta na época do corte e de maneira positiva pela dose de nitrogênio. A taxa de senescência foliar e o número total de folhas por perfilho diminuíram, enquanto a taxa de alongamento foliar aumentou com a adubação nitrogenada. Por outro lado, a taxa de senescência foliar e o número total de folhas por perfilho aumentaram com a altura das plantas na época da colheita. Já o número de folhas vivas por perfilho não foi influenciado pela dose de nitrogênio nem pela altura da planta na época do corte. Para uma mesma altura do capim-tifton 85 na época da colheita, a adubação nitrogenada aumenta o fluxo de tecidos e a frequência de desfolhação. Na condição de desfolhação intermitente, o capim-tifton 85 deve ser colhido com altura de até 30 cm.The objective of this study was to evaluate the morphogenic and structural characteristics of tifton 85 bermudagrass under different nitrogen doses (0, 33, 66, 100 or 133 kg/ha.year of N and three different plant heights (30, 40 or 50 cm at harvesting time. A split plot scheme in a completely randomized design with three replications was used. The nitrogen (N doses stood for the portions and the haversting heights, for the subportions. The leaf appearance rate of tifton 85 bermudagrass was negatively influenced by plant height at harvesting time, but positively influenced by N dose. Leaf senescence rate and total number of leaves per tiller decreased, whereas leaf elongation rate

Improved capability of U-ZrH fuels

Energy Technology Data Exchange (ETDEWEB)

Gietzen, A J [General Atomic Company, San Diego, CA (United States)

1983-08-01

This paper provides a brief background on TRIGA fuels and a summary of the development of U-ZrH fuels utilizing higher uranium loadings in the alloy. Most of the development work was reported two years ago; however, in this paper some emphasis will be placed upon applications that General Atomic Company is now making with these higher alloy fuels. They are referred to as higher uranium content alloys because their development was not really LEU development; the TRIGA fuel has used low enrichment since its inception.

Environmental behaviour and dosimetry of Krypton-85

International Nuclear Information System (INIS)

Patek, P.

1980-12-01

Although 85 Kr has only small influence on the total radiation burden to man, monitoring and safety considerations have to be done, especially regarding the operation of fuel reprocessing plants. The natural, military and civilian sources of 85 Kr are discussed and a survey is given on the possibilities of Krypton removal from off-gas streams. Regarding the environmental behaviour of the released Krypton-amounts it was shown, that only the atmospheric dispersion is of influence to the succeeding irradiation of the population. Krypton is transferred to man only by inhalation and remains with different halflives in the human body. The highest absorbed dose is caused by beta-rays to the skin and in the airways of the lungs. While the highest dose equivalent rates to the most exposed individuals are reached by local sources from fuel reprocessing plants, the highest collective effective dose equivalent commitment is reached for global dispersed 85 Kr. (author)

RIA testing capability of the transient reactor test facility

International Nuclear Information System (INIS)

Crawford, D.C.; Swanson, R.W.

1999-01-01

The advent of high-burnup fuel implementation in LWRs has generated international interest in high-burnup LWR fuel performance. Recent testing under simulated RIA conditions has demonstrated that certain fuel designs fail at peak fuel enthalpy values that are below existing regulatory criteria. Because many of these tests were performed with non-prototypically aggressive test conditions (i.e., with power pulse widths less than 10 msec FWHM and with non-protoypic coolant configurations), the results (although very informative) do not indisputably identify failure thresholds and fuel behavior. The capability of the TREAT facility to perform simulated RIA tests with prototypic test conditions is currently being evaluated by ANL personnel. TREAT was designed to accommodate test loops and vehicles installed for in-pile transient testing. During 40 years of TREAT operation and fuel testing and evaluation, experimenters have been able to demonstrate and determine the transient behavior of several types of fuel under a variety of test conditions. This experience led to an evolution of test methodology and techniques which can be employed to assess RIA behavior of LWR fuel. A pressurized water loop that will accommodate RIA testing of LWR and CANDU-type fuel has completed conceptual design. Preliminary calculations of transient characteristics and energy deposition into test rods during hypothetical TREAT RIA tests indicate that with the installation of a pressurized water loop, the facility is quite capable of performing prototypic RIA testing. Typical test scenarios indicate that a simulated RIA with a 72 msec FWHM pulse width and energy deposition of 1200 kJ/kg (290 cal/gm) is possible. Further control system enhancements would expand the capability to pulse widths as narrow as 40 msec. (author)

Krypton 85 at La Hague

International Nuclear Information System (INIS)

1998-11-01

The gaseous effluents from the fuel reprocessing plant of Cogema-La Hague (France) are regularly measured and controlled. This paper reports on three press releases: the one of Cogema from November 6, 1998 concerning the impact of these effluents and the results of 85 Kr measurements performed in the vicinity of the facility, and the two communiques of the French office of protection against ionizing radiations (OPRI) from November 13 and 20, 1998 relative to the environmental and human impacts of the 85 Kr releases from the La Hague facility. (J.S.)

Ultra-Trace Analysis of Krypton-85

International Nuclear Information System (INIS)

Daerr, H.; Kalinowski, M.; Kohler, M.; Sahling, P.

2010-01-01

To strengthen the efficiency and effectiveness of nuclear safeguards for detecting undeclared nuclear material and activities we propose to use the radioactive krypton isotope Krypton-85 as a tracer for clandestine plutonium production. The main idea is to detect inexplicable atmospheric Kr85 concentration using the novel technology atom trap trace analysis (ATTA) in order to detect an undeclared reprocessing facility. The Additional Protocol (INFCIRC/540, 1997) establishes the possibility to take environmental samples. Krypton-85 has a combination of unique features which makes it an ideal tracer for plutonium separation activities anywhere in the world. It is always generated along with plutonium and 99.9% remains within the fuel cladding. Due to its half-life of 10.76 years, significant amounts of krypton-85 still remain in the spent fuel even after long cooling times. Krypton is not removed from the atmosphere by any processes like chemical reactions or wash-out. Furthermore, there are no other relevant sources of krypton-85 besides of reprocessing. The novel technology of atom trap trace analysis (ATTA) has been demonstrated by the physics group at Argonne National Laboratory in 1999. This is an ultra-sensitive trace analysis technique able to detect single krypton atoms. We are setting up an ATTA apparatus in our laboratory, which is designed to fulfill all requirements to detect clandestine plutonium production. Our goal is to determine Krypton-85 concentration of one liter samples of atmospheric air with an analysis time of 3 hours. This sample volume reduction is a significant step, since one liter can be taken as a grab sample by sucking it directly into pre-evacuated bottles at atmospheric pressure. The small samples size and the short analysis time of ATTA will make it possible to use krypton-85 as a tracer for clandestine plutonium production with routine operation. (author)

An eHealth Capabilities Framework for Graduates and Health Professionals: Mixed-Methods Study

Science.gov (United States)

McGregor, Deborah; Keep, Melanie; Janssen, Anna; Spallek, Heiko; Quinn, Deleana; Jones, Aaron; Tseris, Emma; Yeung, Wilson; Togher, Leanne; Solman, Annette; Shaw, Tim

2018-01-01

Background The demand for an eHealth-ready and adaptable workforce is placing increasing pressure on universities to deliver eHealth education. At present, eHealth education is largely focused on components of eHealth rather than considering a curriculum-wide approach. Objective This study aimed to develop a framework that could be used to guide health curriculum design based on current evidence, and stakeholder perceptions of eHealth capabilities expected of tertiary health graduates. Methods A 3-phase, mixed-methods approach incorporated the results of a literature review, focus groups, and a Delphi process to develop a framework of eHealth capability statements. Results Participants (N=39) with expertise or experience in eHealth education, practice, or policy provided feedback on the proposed framework, and following the fourth iteration of this process, consensus was achieved. The final framework consisted of 4 higher-level capability statements that describe the learning outcomes expected of university graduates across the domains of (1) digital health technologies, systems, and policies; (2) clinical practice; (3) data analysis and knowledge creation; and (4) technology implementation and codesign. Across the capability statements are 40 performance cues that provide examples of how these capabilities might be demonstrated. Conclusions The results of this study inform a cross-faculty eHealth curriculum that aligns with workforce expectations. There is a need for educational curriculum to reinforce existing eHealth capabilities, adapt existing capabilities to make them transferable to novel eHealth contexts, and introduce new learning opportunities for interactions with technologies within education and practice encounters. As such, the capability framework developed may assist in the application of eHealth by emerging and existing health care professionals. Future research needs to explore the potential for integration of findings into workforce development

Applications developed for byproduct 85Kr and tritium

International Nuclear Information System (INIS)

Remini, W.C.; Case, F.N.; Haff, K.W.; Tiegs, S.M.

1983-01-01

The radionuclides, krypton-85 and tritium, both of which are gases under ordinary conditions, are used in many applications in industries and by the military forces. Krypton-85 is produced during the fissioning of uranium and is released during the dissolution of spent-fuel elements. It is a chemically inert gas that emits 0.695-MeV beta rays and a small yield of 0.54-MeV gammas over a half life of 10.3 years. Much of the 85 Kr currently produced is released to the atmosphere; however, large-scale reprocessing of fuel will require collection of the gas and storage as a waste product. An alternative to storage is utilization, and since the chemical and radiation characteristics of 85 Kr make this radionuclide a relatively low hazard from the standpoint of contamination and biological significance, a number of uses have been developed. Tritium is produced as a byproduct of the nuclear-weapons program, and it has a half life of 12.33 years. It has a 0.01861-MeV beta emission and no gamma emission. The absence of a gamma-ray energy eliminates the need for external shielding of the devices utilizing tritium, thus making them easily transportable. Many of the applications require only small quantities of 85 Kr or tritium; however, these uses are important to the technology base of the nation. A significant development that has the potential for beneficial utilization of large quantities of 85 Kr and of tritium involves their use in the production of low-level lighting devices. Since these lights are free from external fuel supplies, have a long half life (> 10 years), are maintenance-free, reliable, and easily deployed, both military and civilian airfield-lighting applications are being studied

Climate aspects of radioactive trace gases, especially krypton-85

International Nuclear Information System (INIS)

Kollert, R.; Butzin, M.

1990-01-01

The amount of krypton 85 currently present in the atmosphere is 3.300 Peta Bq. This atmospheric krypton contamination stems from atom bomb tests of the past and from nuclear power plants as well as spent fuel reprocessing plants. The paper investigates the air-electric and air-chemical impact of Kr-85 on the atmosphere and makes a forecast of the future Kr-85 contamination. (DG) [de

Energy and emission benefits of alternative transportation liquid fuels derived from switchgrass: a fuel life cycle assessment.

Science.gov (United States)

Wu, May; Wu, Ye; Wang, Michael

2006-01-01

We conducted a mobility chains, or well-to-wheels (WTW), analysis to assess the energy and emission benefits of cellulosic biomass for the U.S. transportation sector in the years 2015-2030. We estimated the life-cycle energy consumption and emissions associated with biofuel production and use in light-duty vehicle (LDV) technologies by using the Greenhouse gases, Regulated Emissions, and Energy use in Transportation (GREET) model. Analysis of biofuel production was based on ASPEN Plus model simulation of an advanced fermentation process to produce fuel ethanol/protein, a thermochemical process to produce Fischer-Tropsch diesel (FTD) and dimethyl ether (DME), and a combined heat and power plant to co-produce steam and electricity. Our study revealed that cellulosic biofuels as E85 (mixture of 85% ethanol and 15% gasoline by volume), FTD, and DME offer substantial savings in petroleum (66-93%) and fossil energy (65-88%) consumption on a per-mile basis. Decreased fossil fuel use translates to 82-87% reductions in greenhouse gas emissions across all unblended cellulosic biofuels. In urban areas, our study shows net reductions for almost all criteria pollutants, with the exception of carbon monoxide (unchanged), for each of the biofuel production option examined. Conventional and hybrid electric vehicles, when fueled with E85, could reduce total sulfur oxide (SO(x)) emissions to 39-43% of those generated by vehicles fueled with gasoline. By using bio-FTD and bio-DME in place of diesel, SO(x) emissions are reduced to 46-58% of those generated by diesel-fueled vehicles. Six different fuel production options were compared. This study strongly suggests that integrated heat and power co-generation by means of gas turbine combined cycle is a crucial factor in the energy savings and emission reductions.

Internationalisation of construction business and e-commerce: Innovation, integration and dynamic capabilities

Directory of Open Access Journals (Sweden)

Thayaparan Gajendran

2013-06-01

Full Text Available Despite the role of internet and web based applications in delivering competitive advantage through e-business process is widely acknowledged, little is done by way of research to use the dynamic capability framework, in exploring the role of ecommerce in the construction business internationalisation. The aim of this paper is to present a literature based theoretical exploration using dynamic capability view to discuss internationalising construction businesses through electronic commerce (e-commerce platforms. This paper contextualises the opportunities for internationalising construction, using a mix of supply chain paradigms, embedded with e-commerce platforms. The paper concludes by identifying the potential of dynamic capabilities of a firm, exploiting the innovation and integration potential of different e-business systems, in contributing to the internationalisation of construction businesses. It proposes that contracting firms with developed dynamic capabilities, has the potential to exploit e-commerce platforms to channel upstream activities to an international destination, and also offers the firm’s products/services to international markets.

Search for narrow resonances in e+e- annihilation between 1.85 and 3.1 GeV with the KEDR detector

International Nuclear Information System (INIS)

Anashin, V.V.; Aulchenko, V.M.; Baldin, E.M.; Barladyan, A.K.; Barnyakov, A.Yu.; Barnyakov, M.Yu.; Baru, S.E.; Basok, I.Yu.; Beloborodova, O.L.; Blinov, A.E.; Blinov, V.E.; Bobrov, A.V.; Bobrovnikov, V.S.; Bogomyagkov, A.V.; Bondar, A.E.; Buzykaev, A.R.; Eidelman, S.I.; Grigoriev, D.N.; Glukhovchenko, Yu.M.; Gulevich, V.V.

2011-01-01

We report results of a search for narrow resonances in e + e - annihilation at center-of-mass energies between 1.85 and 3.1 GeV performed with the KEDR detector at the VEPP-4M e + e - collider. The upper limit on the leptonic width of a narrow resonance Γ ee R .Br(R→hadr)<120 eV has been obtained (at 90% C.L.).

New measurement capabilities of mass spectrometry in the nuclear fuel cycle

International Nuclear Information System (INIS)

Perrin, R.E.

1979-01-01

Three recent developments, when combined, have the potential for greatly improving accountability measurements in the nuclear fuel cycle. The techniques are particularly valuable when measuring the contents of vessels which are difficult to calibrate by weight or volume. Input dissolver accountability measurements, inparticular, benefit from the application of these techniques. Los Alamos Scientific Laboratory has developed the capability for isotopic analysis of U and Pu samples at the nanogram level with an accuracy of 0.1 relative %. The Central Bureau for Nuclear Materials Measurement in Geel, Belgium has developed the capability of preparing mixed, solid metal U and Pu spikes with an accuracy of better than 0.1 relative %. Idaho Nuclear Energy Laboratory and C.K. Mathews at Bhabha Atomic Research have demonstrated a technique for determining the ratio of sample size to total solution measured which is independent of both the weight and the volume of the solution being measured. The advantages and limitations of these techniques are discussed. An analytical scheme which takes advantage of the special features of these techniques is proposed. 4 refs

An eHealth Capabilities Framework for Graduates and Health Professionals: Mixed-Methods Study.

Science.gov (United States)

Brunner, Melissa; McGregor, Deborah; Keep, Melanie; Janssen, Anna; Spallek, Heiko; Quinn, Deleana; Jones, Aaron; Tseris, Emma; Yeung, Wilson; Togher, Leanne; Solman, Annette; Shaw, Tim

2018-05-15

The demand for an eHealth-ready and adaptable workforce is placing increasing pressure on universities to deliver eHealth education. At present, eHealth education is largely focused on components of eHealth rather than considering a curriculum-wide approach. This study aimed to develop a framework that could be used to guide health curriculum design based on current evidence, and stakeholder perceptions of eHealth capabilities expected of tertiary health graduates. A 3-phase, mixed-methods approach incorporated the results of a literature review, focus groups, and a Delphi process to develop a framework of eHealth capability statements. Participants (N=39) with expertise or experience in eHealth education, practice, or policy provided feedback on the proposed framework, and following the fourth iteration of this process, consensus was achieved. The final framework consisted of 4 higher-level capability statements that describe the learning outcomes expected of university graduates across the domains of (1) digital health technologies, systems, and policies; (2) clinical practice; (3) data analysis and knowledge creation; and (4) technology implementation and codesign. Across the capability statements are 40 performance cues that provide examples of how these capabilities might be demonstrated. The results of this study inform a cross-faculty eHealth curriculum that aligns with workforce expectations. There is a need for educational curriculum to reinforce existing eHealth capabilities, adapt existing capabilities to make them transferable to novel eHealth contexts, and introduce new learning opportunities for interactions with technologies within education and practice encounters. As such, the capability framework developed may assist in the application of eHealth by emerging and existing health care professionals. Future research needs to explore the potential for integration of findings into workforce development programs. ©Melissa Brunner, Deborah Mc

Developing an energy efficient steam reforming process to produce hydrogen from sulfur-containing fuels

Science.gov (United States)

Simson, Amanda

Hydrogen powered fuel cells have the potential to produce electricity with higher efficiency and lower emissions than conventional combustion technology. In order to realize the benefits of a hydrogen fuel cell an efficient method to produce hydrogen is needed. Currently, over 90% of hydrogen is produced from the steam reforming of natural gas. However, for many applications including fuel cell vehicles, the use of a liquid fuel rather than natural gas is desirable. This work investigates the feasibility of producing hydrogen efficiently by steam reforming E85 (85% ethanol/15% gasoline), a commercially available sulfur-containing transportation fuel. A Rh-Pt/SiO2-ZrO2 catalyst has demonstrated good activity for the E85 steam reforming reaction. An industrial steam reforming process is often run less efficiently, with more water and at higher temperatures, in order to prevent catalyst deactivation. Therefore, it is desirable to develop a process that can operate without catalyst deactivation at more energy efficient conditions. In this study, the steam reforming of a sulfur-containing fuel (E85) was studied at near stoichiometric steam/carbon ratios and at 650C, conditions at which catalyst deactivation is normally measured. At these conditions the catalyst was found to be stable steam reforming a sulfur-free E85. However, the addition of low concentrations of sulfur significantly deactivated the catalyst. The presence of sulfur in the fuel caused catalyst deactivation by promoting ethylene which generates surface carbon species (coke) that mask catalytic sites. The amount of coke increased during time on stream and became increasingly graphitic. However, the deactivation due to both sulfur adsorption and coke formation was reversible with air treatment at 650°C. However, regenerations were found to reduce the catalyst life. Air regenerations produce exotherms on the catalyst surface that cause structural changes to the catalyst. During regenerations the

Measuring the Amount of Effects of Capability Approach on Developing E-government

Directory of Open Access Journals (Sweden)

behroz Zarei

2013-07-01

Full Text Available In capability approach (C.A., the concepts of developed and undeveloped and their realization instruments are different from other common approaches. Just those who are provided with personal capabilities and environmental conditions can be the messengers of development. In this approach background of our country in planning is ignored and resolved the challenges of development in e- government.  So at first, main challenges in developing e-government are identified, then models of C.A. and factors affecting it are extracted and classified. Next, the amount of effects of human capabilities on different challenges of e-government is surveyed based on QFD and ranked regarding Shannon Entropy. The results showed in e-government developing, considering the capabilities of people along with different ideas of the government can be influential. The important capabilities are as follows: the ability to create a democratic, free environment in the information community, accessing to this information, the ability to learn the electronic knowledge and the ability to offer services with electronic quality and the ability to preserve one’s rights in an electronic environment.

Effects of High Octane Ethanol Blends on Four Legacy Flex-Fuel Vehicles, and a Turbocharged GDI Vehicle

Energy Technology Data Exchange (ETDEWEB)

Thomas, John F [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); West, Brian H [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Huff, Shean P [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-03-01

The U.S. Department of Energy (DOE) is supporting engine and vehicle research to investigate the potential of high-octane fuels to improve fuel economy. Ethanol has very high research octane number (RON) and heat of vaporization (HoV), properties that make it an excellent spark ignition engine fuel. The prospects of increasing both the ethanol content and the octane number of the gasoline pool has the potential to enable improved fuel economy in future vehicles with downsized, downsped engines. This report describes a small study to explore the potential performance benefits of high octane ethanol blends in the legacy fleet. There are over 17 million flex-fuel vehicles (FFVs) on the road today in the United States, vehicles capable of using any fuel from E0 to E85. If a future high-octane blend for dedicated vehicles is on the horizon, the nation is faced with the classic chicken-and-egg dilemma. If today’s FFVs can see a performance advantage with a high octane ethanol blend such as E25 or E30, then perhaps consumer demand for this fuel can serve as a bridge to future dedicated vehicles. Experiments were performed with four FFVs using a 10% ethanol fuel (E10) with 88 pump octane, and a market gasoline blended with ethanol to make a 30% by volume ethanol fuel (E30) with 94 pump octane. The research octane numbers were 92.4 for the E10 fuel and 100.7 for the E30 fuel. Two vehicles had gasoline direct injected (GDI) engines, and two featured port fuel injection (PFI). Significant wide open throttle (WOT) performance improvements were measured for three of the four FFVs, with one vehicle showing no change. Additionally, a conventional (non-FFV) vehicle with a small turbocharged direct-injected engine was tested with a regular grade of gasoline with no ethanol (E0) and a splash blend of this same fuel with 15% ethanol by volume (E15). RON was increased from 90.7 for the E0 to 97.8 for the E15 blend. Significant wide open throttle and thermal efficiency performance

An analysis of fast reactor fuel assembly performance taking into account their mechanical interaction in the core and refuelling line capabilities

International Nuclear Information System (INIS)

Buksha, Yu.K.; Zabudko, L.M.; Kravchenko, I.N.; Matveenko, L.V.; Meshkov, M.N.

1984-01-01

An approach to assessment of fast reactor fuel assembly performance has been considered. A concept of passive restraint of fuel assemblies in a reactor adopted in the USSR is described. Some methods for calculating the interassembly interactions during operation are briefly outlined, some calculated results are presented. A problem of fuel assembly performance during refuelling taking into account the refuelling line capabilities is considered. Some results from fuel assemblies operation experience in the BN-600 reactor are given. (author)

Developing A/E capabilities; areas of special interest

International Nuclear Information System (INIS)

Gonzalez, A.; Gurbindo, J.

1988-01-01

During the last few years, the methods used by Empresarios Agrupados and INITEC to perform Architect-Engineering work in Spain for nuclear projects has undergone a process of significant change in project management and engineering approaches. Specific practical examples of management techniques and design practices which represent a good record of results will be discussed. They are identified as areas of special interest in developing A/E capabilities for nuclear projects. Command of these areas should produce major payoffs in local participation and contribute to achieving real nuclear engineering capabilities in the country

Issues Associated with IAEA Involvement in Assured Nuclear Fuel Supply Arrangements

Energy Technology Data Exchange (ETDEWEB)

Kessler, Carol E.; Mathews, Carrie E.

2008-02-08

Assured nuclear fuel supply has been discussed at various times as a mechanism to help limit expansion of enrichment and reprocessing (E&R) capability beyond current technology holders. Given the events in the last few years in North Korea and Iran, concern over weapons capabilities gained from acquisition of E&R capabilities has heightened and brought assured nuclear fuel supply (AFS) again to the international agenda. Successful AFS programs can be valuable contributions to strengthening the nonproliferation regime and helping to build public support for expanding nuclear energy.

Ambient krypton-85 air sampling at Hanford

International Nuclear Information System (INIS)

Trevathan, M.S.; Price, K.R.

1985-01-01

In the fall of 1982, the Environmental Evaluations Section of Pacific Northwest Laboratory (PNL) initiated a network of continuous 85 Kr air samplers located on and around the Hanford Site. This effort was in response to the resumption of operations at a nuclear fuel reprocessing plant located onsite where 85 Kr was to be released during fuel dissolution. Preoperational data were collected using noble gas samplers designed by the Environmental Protection Agency-Las Vegas (EPA-LV). The samplers functioned erratically resulting in excessive maintenance costs and prompted a search for a new sampling system. State-of-the-art 85 Dr sampling methods were reviewed and found to be too costly, too complex and inappropriate for field application, so a simple bag collection system was designed and field tested. The system is composed of a reinforced, heavy plastic bag, connected to a variable flow pump and housed in a weatherproof enclosure. At the end of the four week sampling period the air in the bag is transferred by a compressor into a pressure tank for easy transport to the laboratory for analysis. After several months of operation, the air sampling system has proven its reliability and sensitivity to ambient levels of 85 Kr

Ambient krypton-85 air sampling at Hanford

International Nuclear Information System (INIS)

Trevathan, M.S.; Price, K.R.

1984-10-01

In the fall of 1982, the Environmental Evaluations Section of Pacific Northwest Laboratory (PNL) initiated a network of continuous krypton-85 air samplers located on and around the Hanford Site. This effort was in response to the resumption of operations at a nuclear fuel reprocessing plant located onsite where krypton-85 was to be released during fuel dissolution. Preoperational data were collected using noble gas samplers designed by the Environmental Protection Agency-Las Vegas (EPA-LV). The samplers functioned erratically resulting in excessive maintenance costs and prompted a search for a new sampling system. State of the art krypton-85 sampling methods were reviewed and found to be too costly, too complex and inappropriate for field application, so a simple bag collection system was designed and field tested. The system is composed of a reinforced, heavy plastic bag, connected to a variable flow pump and housed in a weatherproof enclosure. At the end of the four week sampling period the air in the bag is transferred by a compressor into a pressure tank for easy transport to the laboratory for analysis. After several months of operation, the air sampling system has proven its reliability and sensitivity to ambient levels of krypton-85. 3 references, 3 figures, 1 table

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-06-19

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

Present status of reactor physics in the United States and Japan-III. 2. Nuclear Fuel Management Optimization Capabilities

International Nuclear Information System (INIS)

Karve, Atul A.; Keller, Paul M.; Turinsky, Paul J.; Maldonado, G. Ivan

2001-01-01

approach is that many histories, i.e., combinations of decision variables, must be evaluated, which implies that many core physics calculations are required to determine the family of near-optimum decisions. To reduce computer execution time, highly efficient, core physics models with only the fidelity required for the assigned task are utilized. Ideally, one would like to utilize the same core physics models for all nuclear problems for consistency and ease of usage, which may someday occur with increases in computational power and advances in computational reactor physics. In considering core physics models, a unique aspect for nuclear fuel management optimization applications is that many repetitive calculations need to be completed during the optimization search. This implies that considerable overhead can be tolerated to reduce the computational time per history since the overhead will be amortized over many histories. This feature can imply the employment of different solution approaches than normally utilized. How various suboptimum problems integrate in an attempt to address the global optimization problem is now explained. The out-of-core optimization OCEON-P code has a number of decision variables, but the only decision that carries-forward in the reload design process is the cycling scheme, i.e., batch sizes in each cycle of the planning horizon. Note that OCEON-P is the only optimization code within the suite that truly does multicycle optimization and so can meaningfully evaluate and minimize levelized fuel cycle cost. The FORMOSA-L code optimizes the lattice, normally constrained to follow a specified reactivity versus burnup. This constraint provides the linkage to the core-wide analysis but is problematic to obtain. There currently does not exist within the suite of codes one that addresses the suboptimum problem of bundle design, which other researchers have addressed to a limited extent. With our current capabilities, a number of different bundle designs

Long term storage techniques for 85Kr

International Nuclear Information System (INIS)

Foster, B.A.; Pence, D.T.; Staples, B.A.

1975-01-01

As new nuclear fuel reprocessing plants go on stream, the collection of fission product 85 Kr will be required to avoid potential local release problems and long-term atmospheric buildup. Storage of the collected 85 Kr for a period of at least 100 years will be necessary to allow approximately 99.9 percent decay before it is released. A program designed to develop and evaluate proposed methods for long-term storage of 85 Kr is discussed, and the results of a preliminary evaluation of three methods, high pressure steel cylinders, zeolite encapsulation, and clathrate inclusion are presented. (U.S.)

How "Green" Is Your Fuel? Creation and Comparison of Automotive Biofuels

Science.gov (United States)

Wagner, Eugene P.; Koehle, Maura A.; Moyle, Todd M.; Lambert, Patrick D.

2010-01-01

In recent years, biofuel development and use has risen significantly. This undergraduate laboratory experiment educates students on the various alternative fuels that are being developed for automotive applications and the advantages and disadvantages of each. Students replicate commercially available alternative fuels, E85 and biodiesel, as well…

Spent fuel storage requirements. An update of DOE/RL-85-2

International Nuclear Information System (INIS)

1986-10-01

Utility projections of spent fuel storage capacities indicate that some commercial light water reactors (LWRs) have inadequate capacity to handle projected spent fuel discharges. This report presents estimates of potential near-term requirements for additional LWR spent fuel storage capacity, based on information supplied by utilities operating commercial nuclear power plants. These estimates provide information needed for planning the Department of Energy's (DOE) activities to be carried out under the DOE's Commercial Spent Fuel Management (CSFM) Program, in conjunction with the requirements of the Nuclear Waste Policy Act of 1982. This report is the latest in a series published by the DOE on LWR spent fuel storage requirements. The estimates in this report cover the period from the present through the year 2000. Although the DOE objective is to begin accepting spent fuel for final disposal in 1998, types of fuel and the receipt rates to be shipped are not yet known. Hence, this report makes no assumption regarding such fuel shipments. The report also assesses the possible impacts of increased fuel exposure and spent fuel transshipment on the requirements for additional storage capacity

Optimally Controlled Flexible Fuel Powertrain System

Energy Technology Data Exchange (ETDEWEB)

Hakan Yilmaz; Mark Christie; Anna Stefanopoulou

2010-12-31

The primary objective of this project was to develop a true Flex Fuel Vehicle capable of running on any blend of ethanol from 0 to 85% with reduced penalty in usable vehicle range. A research and development program, targeting 10% improvement in fuel economy using a direct injection (DI) turbocharged spark ignition engine was conducted. In this project a gasoline-optimized high-technology engine was considered and the hardware and configuration modifications were defined for the engine, fueling system, and air path. Combined with a novel engine control strategy, control software, and calibration this resulted in a highly efficient and clean FFV concept. It was also intended to develop robust detection schemes of the ethanol content in the fuel integrated with adaptive control algorithms for optimized turbocharged direct injection engine combustion. The approach relies heavily on software-based adaptation and optimization striving for minimal modifications to the gasoline-optimized engine hardware system. Our ultimate objective was to develop a compact control methodology that takes advantage of any ethanol-based fuel mixture and not compromise the engine performance under gasoline operation.

Carbonaceous Aerosols Emitted from Light-Duty Vehicles Operating on Ethanol Fuel Blends

Science.gov (United States)

Air pollution is among the many environmental and public health concerns associated with increased ethanol use in vehicles. Jacobson [2007] showed for the U.S. market that full conversion to e85 ([85% ethanol, 15% gasoline]—the maximum standard blend used in modern dual fuel veh...

Development of a Fissile Materials Irradiation Capability for Advanced Fuel Testing at the MIT Research Reactor

International Nuclear Information System (INIS)

Hu Linwen; Bernard, John A.; Hejzlar, Pavel; Kohse, Gordon

2005-01-01

A fissile materials irradiation capability has been developed at the Massachusetts Institute of Technology (MIT) Research Reactor (MITR) to support nuclear engineering studies in the area of advanced fuels. The focus of the expected research is to investigate the basic properties of advanced nuclear fuels using small aggregates of fissile material. As such, this program is intended to complement the ongoing fuel evaluation programs at test reactors. Candidates for study at the MITR include vibration-packed annular fuel for light water reactors and microparticle fuels for high-temperature gas reactors. Technical considerations that pertain to the design of the MITR facility are enumerated including those specified by 10 CFR 50 concerning the definition of a research reactor and those contained in a separate license amendment that was issued by the U.S. Nuclear Regulatory Commission to MIT for these types of experiments. The former includes limits on the cross-sectional area of the experiment, the physical form of the irradiated material, and the removal of heat. The latter addresses experiment reactivity worth, thermal-hydraulic considerations, avoidance of fission product release, and experiment specific temperature scrams

Cermet fuels for space power systems

International Nuclear Information System (INIS)

Barner, J.O.; Coomes, E.P.; Williford, R.E.; Neimark, L.A.

1986-01-01

A refractory-metal matrix, UN-fueled cermet is a very promising fuel candidate for a wide range of multi-megawatt space reactor systems, e.g., steady-state, flexible duty-cycle, or bimodal, single- or two-phase liquid-metal cooled reactors, or thermionic reactors. Cermet fuel is especially promising for reactor designs that require operational strategies which incorporate rapid power changes because of its anticipated capability to withstand thermal shock

Interactions between California's Low Carbon Fuel Standard and the National Renewable Fuel Standard

International Nuclear Information System (INIS)

Whistance, Jarrett; Thompson, Wyatt; Meyer, Seth

2017-01-01

This study investigates the economic interactions between a national renewable fuel policy, namely the Renewable Fuel Standard (RFS) in the United States, and a sub-national renewable fuel policy, the Low Carbon Fuel Standard (LCFS) in California. The two policies have a similar objective of reducing greenhouse gas emissions, but the policies differ in the manner in which those objectives are met. The RFS imposes a hierarchical mandate of renewable fuel use for each year whereas the LCFS imposes a specific annual carbon-intensity reduction with less of a fuel specific mandate. We model the interactions using a partial-equilibrium structural model of agricultural and energy markets in the US and Rest-of-World regions. Our results suggest the policies are mutually reinforcing in that the compliance costs of meeting one of the requirements is lower in the presence of the other policy. In addition, the two policies combine to create a spatial shift in renewable fuel use toward California even though overall renewable fuel use remains relatively unchanged. - Highlights: • Results suggest the RFS and LCFS are mutually reinforcing. • Overall level of renewable fuel use is similar across scenarios. • Renewable fuel use shifts toward California in the presence of the LCFS. • Higher ethanol blend (e.g. E85) use also shifts toward California.

Alcohol Fuel in Passenger Car

Directory of Open Access Journals (Sweden)

Adam Polcar

2016-01-01

Full Text Available The present article studies the effects of combustion of high-percentage mixture of bioethanol and gasoline on the output parameters of a passenger car engine. The car engine has not been structurally modified for the combustion of fuels with higher ethanol content. The mixture used consisted of E85 summer blend and Natural 95 gasoline in a ratio of 50:50. The parameters monitored during the experiment included the air-fuel ratio in exhaust gasses, the power output and torque of the engine and also the specific energy consumption and efficiency of the engine. As is apparent from the results, E85+N95 (50:50 mixture combustion results in lean-burn (λ > 1 due to the presence of oxygen in bioethanol. The lean-burn led to a slight decrease in torque and power output of the engine. However, due to the positive physicochemical properties of bioethanol, the decrease has not been as significant as would normally be expected from the measured air-fuel ratio. These findings are further confirmed by the calculated energy required to produce 1 kWh of energy, and by the higher efficiency of the engine during the combustion of a 50% bioethanol mixture.

Fleet Conversion in Local Government: Determinants of Driver Fuel Choice for Bi-Fuel Vehicles

Science.gov (United States)

Johns, Kimberly D.; Khovanova, Kseniya M.; Welch, Eric W.

2009-01-01

This study evaluates the conversion of one local government's fleet from gasoline to bi-fuel E-85, compressed natural gas, and liquid propane gas powered vehicles at the midpoint of a 10-year conversion plan. This study employs a behavioral model based on the theory of reasoned action to explore factors that influence an individual's perceived and…

Ohio's First Ethanol-Fueled Light-Duty Fleet: Final Study Results

Energy Technology Data Exchange (ETDEWEB)

Battelle

1998-10-01

In 1996, the State of Ohio established a project to demonstrate the use of an ethanol blend (E85, which is 85% transportation-grade ethanol and 15% gasoline) as a transportation fuel in flexible-fuel vehicles (FFVs). The study included ten FFVs and three gasoline vehicles (used as control vehicles) operated by five state agencies. The project included 24 months of data collection on vehicle operations. This report presents the data collection and analysis from the study, with a focus on the last year.

Experimental study on the 300W class planar type solid oxide fuel cell stack: Investigation for appropriate fuel provision control and the transient capability of the cell performance

International Nuclear Information System (INIS)

Komatsu, Y; Brus, G; Szmyd, J S; Kimijima, S

2012-01-01

The present paper reports the experimental study on the dynamic behavior of a solid oxide fuel cell (SOFC). The cell stack consists of planar type cells with standard power output 300W. A Major subject of the present study is characterization of the transient response to the electric current change, assuming load-following operation. The present studies particularly focus on fuel provision control to the load change. Optimized fuel provision improves power generation efficiency. However, the capability of SOFC must be restricted by a few operative parameters. Fuel utilization factor, which is defined as the ratio of the consumed fuel to the supplied fuel is adopted for a reference in the control scheme. The fuel flow rate was regulated to keep the fuel utilization at 50%, 60% and 70% during the current ramping. Lower voltage was observed with the higher fuel utilization, but achieved efficiency was higher. The appropriate mass flow control is required not to violate the voltage transient behavior. Appropriate fuel flow manipulation can contribute to moderate the overshoot on the voltage that may appear to the current change. The overshoot on the voltage response resulted from the gradual temperature behavior in the SOFC stack module.

Experimental study on the 300W class planar type solid oxide fuel cell stack: Investigation for appropriate fuel provision control and the transient capability of the cell performance

Science.gov (United States)

Komatsu, Y.; Brus, G.; Kimijima, S.; Szmyd, J. S.

2012-11-01

The present paper reports the experimental study on the dynamic behavior of a solid oxide fuel cell (SOFC). The cell stack consists of planar type cells with standard power output 300W. A Major subject of the present study is characterization of the transient response to the electric current change, assuming load-following operation. The present studies particularly focus on fuel provision control to the load change. Optimized fuel provision improves power generation efficiency. However, the capability of SOFC must be restricted by a few operative parameters. Fuel utilization factor, which is defined as the ratio of the consumed fuel to the supplied fuel is adopted for a reference in the control scheme. The fuel flow rate was regulated to keep the fuel utilization at 50%, 60% and 70% during the current ramping. Lower voltage was observed with the higher fuel utilization, but achieved efficiency was higher. The appropriate mass flow control is required not to violate the voltage transient behavior. Appropriate fuel flow manipulation can contribute to moderate the overshoot on the voltage that may appear to the current change. The overshoot on the voltage response resulted from the gradual temperature behavior in the SOFC stack module.

Canadian Fusion Fuels Technology Project activities report

International Nuclear Information System (INIS)

1985-01-01

The Canadian Fusion Fuels Technology Project was formally established in 1982. The project is directed toward the further development of Canadian capabilities in five major areas: tritium technology, breeder technology, materials technology, equipment development and safety and the environment. The project is funded by three partners - Government of Canada (50%), Ontario Provincial Government (25%) and Ontario Hydro (25%). The fiscal year 1984/85 represents the third year of operation of the project. In 1984/85, 108 contracts were awarded totalling $4 million. Supplementary funding by subcontractors added approximately $1.9 million to the total project value. More than 200 people participated in the technical work involved in the project. Sixteen people were on attachment to foreign facilities for terms ranging from 1 month to 2.5 years. Five patents were applied for including a tritium discrimination monitor, a new radio-chemical tritium separation method, a new variation of fuel cleanup by gas chromatography, a passive tritium permeation system using bimetallic membranes, and a new breeder process using lithium salts dissolved in heavy water

Atmospheric krypton-85 during 1962 and 1963

Energy Technology Data Exchange (ETDEWEB)

Ehhalt, D.; Muennich, K. O.; Roether, W.; Schoelch, J.; Stich, W.

1963-11-15

The krypton-85 found in the atmosphere presumably originates from two different sources, namely fission bomb tests and processing of burned-out fuel elements from nuclear reactors. This paper discusses the impact of the sources of krypton in the atmosphere in greater detail.

Emission consequences of introducing bio ethanol as a fuel for gasoline cars

DEFF Research Database (Denmark)

Winther, Morten Mentz; Møller, Flemming; Jensen, Thomas Christian

2012-01-01

This article describes the direct vehicle emission impact of the future use of bio ethanol as a fuel for gasoline cars in Denmark arising from the vehicle specific fuel consumption and emission differences between neat gasoline (E0) and E5/E85 gasoline-ethanol fuel blends derived from emission......% in 2030. As predicted by the vehicle specific emission differences the calculated emission impacts of using bio ethanol are small for NOx, VOC and CO. Instead, for FS, BS1 and BS2 large emission reductions are due to the gradually cleaner new sold gasoline cars and the decline in total mileage until...

Dynamic simulation of a direct carbonate fuel cell power plant

Energy Technology Data Exchange (ETDEWEB)

Ernest, J.B. [Fluor Daniel, Inc., Irvine, CA (United States); Ghezel-Ayagh, H.; Kush, A.K. [Fuel Cell Engineering, Danbury, CT (United States)

1996-12-31

Fuel Cell Engineering Corporation (FCE) is commercializing a 2.85 MW Direct carbonate Fuel Cell (DFC) power plant. The commercialization sequence has already progressed through construction and operation of the first commercial-scale DFC power plant on a U.S. electric utility, the 2 MW Santa Clara Demonstration Project (SCDP), and the completion of the early phases of a Commercial Plant design. A 400 kW fuel cell stack Test Facility is being built at Energy Research Corporation (ERC), FCE`s parent company, which will be capable of testing commercial-sized fuel cell stacks in an integrated plant configuration. Fluor Daniel, Inc. provided engineering, procurement, and construction services for SCDP and has jointly developed the Commercial Plant design with FCE, focusing on the balance-of-plant (BOP) equipment outside of the fuel cell modules. This paper provides a brief orientation to the dynamic simulation of a fuel cell power plant and the benefits offered.

CaracterÃsticas produtivas e parÃmetros bromatolÃgicos de pastagens de Tifton 85 (Cynodon spp) e Coastcross (Cynodon dactylon) e desempenho de bovinos da raÃa PurunÃ

OpenAIRE

Marcos Antonio Teixeira

2014-01-01

O objetivo deste trabalho foi avaliar o desempenho animal da raÃa Purunà e de pastagens de Tifton 85 (Cynodon spp) e Coastcross (Cynodon dactylon) com e sem irrigaÃÃo sendo o experimento realizado no municÃpio de Santa Tereza do Oeste/PR. Inicialmente, avaliou-se a produÃÃo de matÃria seca (MS) e composiÃÃo bromatolÃgica das pastagens de capim tifton 85 e coastcross sem irrigaÃÃo e com irrigaÃÃo. O delineamento experimental foi em blocos casualizados, em esquema fatorial com parcelas subd...

The development of a commercial MOX fuel manufacturing capability in the U.K

International Nuclear Information System (INIS)

Macphee, D.S.; Young, M.P.

1995-01-01

BNFL is implementing a strategy to establish a commercial MOX manufacturing capability within the UK. The design and provision of the fabrication plants is incorporating the considerable experience within the Company of MOX technology, fuel fabrication and nuclear plant design. The first phase of the strategy is complete with the successful operation of the Demonstration Facility. The development programmes supporting the increased scale of operation for a commercial scale facility are substantially complete. Design and construction of a 120t HM/year plant is well advanced supported by a substantial in-house design and project management team. (author)

Krypton-85 Monitoring at BfS in Germany and Technical Solutions for Safeguards

International Nuclear Information System (INIS)

Schlosser, C.; Klingberg, F.

2015-01-01

The radioactive noble gas isotope krypton-85 with a half-life of 10.76 years is produced by nuclear fission. The main source of krypton-85 in the atmosphere are releases from reprocessing plants for nuclear fuel in the Northern Hemisphere. This volatile isotope is not retained in such plants and thus a very good indicator for the processing of irradiated nuclear fuel. This includes reprocessing for military purposes. Additionally, Kr-85 could be used as tracer for the validation of Atmospheric Transport Models. The German Federal Office for Radiation Protection (BfS) operates a noble gas laboratory and a global network which continuously monitors the krypton-85 activity concentrations in ground level air since the 1970s. The atmospheric activity concentration has continuously been increasing since the installation of reprocessing plants for nuclear fuels in the early 1950s until 2003. In the first decades it came mostly from military applications and later from civil reprocessing. Since 2003 the atmospheric krypton-85 background level in the Northern Hemisphere is nearly constant with a value of around 1.5 Bq/m 3 in Central Europe. The baseline is superimposed by spikes as a result from discharges of two European reprocessing plants of nuclear fuel, Sellafield and La Hague. The laboratory of the BfS and the techniques used will be presented. Long time series will be discussed and the use of ATM for source location demonstrated. (author)

The study of capability natural uranium as fuel cycle input for long life gas cooled fast reactors with helium as coolant

Energy Technology Data Exchange (ETDEWEB)

Ariani, Menik, E-mail: menikariani@gmail.com; Satya, Octavianus Cakra; Monado, Fiber [Department of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University, jl Palembang-Prabumulih km 32 Indralaya OganIlir, South of Sumatera (Indonesia); Su’ud, Zaki [Nuclear and Biophysics Research Division, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, jlGanesha 10, Bandung (Indonesia); Sekimoto, Hiroshi [CRINES, Tokyo Institute of Technology, 2-12-11N1-17 Ookayama, Meguro-Ku, Tokyo (Japan)

2016-03-11

The objective of the present research is to assess the feasibility design of small long-life Gas Cooled Fast Reactor with helium as coolant. GCFR included in the Generation-IV reactor systems are being developed to provide sustainable energy resources that meet future energy demand in a reliable, safe, and proliferation-resistant manner. This reactor can be operated without enrichment and reprocessing forever, once it starts. To obtain the capability of consuming natural uranium as fuel cycle input modified CANDLE burn-up scheme was adopted in this system with different core design. This study has compared the core with three designs of core reactors with the same thermal power 600 MWth. The fuel composition each design was arranged by divided core into several parts of equal volume axially i.e. 6, 8 and 10 parts related to material burn-up history. The fresh natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of the region (i) into region (i+1) region after the end of 10 years burn-up cycle. The calculation results shows that for the burn-up strategy on “Region-8” and “Region-10” core designs, after the reactors start-up the operation furthermore they only needs natural uranium supply to the next life operation until one period of refueling (10 years).

A survey of methods for separating and immobilizing krypton-85 arising from a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Taylor, P.

1990-12-01

This report reviews the literature on methods to separate and immobilize krypton-85 arising from dissolution or prior treatment of nuclear fuel in a reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future applications in Canada. Cryogenic distillation is the most fully demonstrated method of separation of krypton from off-gases, but it is complex. In particular, it requires pretreatment of the gas stream to eliminate several other components before the final distillation. The most highly developed alternative process is fluorocarbon adsorption, while several other processes have been investigated on a bench scale. The simplest method of storing radioactive krypton is in compressed-gas cylinders, but the risks of accidental release are increased by the corrosive nature of the decay product, rubidium. Encapsulation in either a metal matrix or a hydrothermally vitrified zeolite appears to offer the most secure immobilization of krypton. Processes for both types of material have been demonstrated inactively on a scale approaching that required for treatment of off-gases from a commercial-scale fuel reprocessing plant. Low-operating temperatures and pressures of the metal encapsulation process, compared with encapsulation in zeolites, represent a definite advantage, but electrical power requirements for the former process are relatively high. It appears that suitable technology is available for separation and immobilization of radioactive krypton, should the need arise in Canada in the future

Nuclear Fuels & Materials Spotlight Volume 5

International Nuclear Information System (INIS)

Petti, David Andrew

2016-01-01

As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system. • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.

The distribution, atmospheric transfer, and assessment of krypton-85; Distribution, transfert atmospherique et bilan du krypton-85

Energy Technology Data Exchange (ETDEWEB)

Pannetier, R [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1968-06-01

Techniques for sampling and measuring krypton-85 have been developed which allowed to determine its geographical distribution. From its use as a tracer, an evaluation of the air masses which cross over the subtropical fronts has been derived. Besides, the stratospheric character of air pollution by krypton-85 at the level of the antarctic soil has been shown out. Levels of krypton-85 seem to point out to an underestimation of the assessment of nuclear explosion fission energies as adopted by the United Nations Scientific committee on the effects of atomic radiation and emphasize the need to set limits as soon as possible to the amounts of krypton-85 released to the atmosphere by fuel-reprocessing plants. (author) [French] La mise au point de techniques de prelevement et de mesure du krypton-85 atmospherique a permis de determiner sa repartition geographique. De son utilisation comme traceur on deduit une evaluation des masses d'air qui traversent les fronts subtropicaux. Par ailleurs, le caractere stratospherique de la pollution de l'air par le krypton-85 au niveau du sol antarctique est mis en evidence. Le bilan du krypton-85 semble reveler une sous-estimation du bilan des energies de fission des explosions adopte par le Comite scientifique des Nations Unies et souligne la necessite de limiter des que possible les quantites de krypton-85 rejetees dans l'atmosphere par les usines de traitement de combustibles irradies. (auteur)

MELCOR Modeling of Air-Cooled PWR Spent Fuel Assemblies in Water empty Fuel Pools

Energy Technology Data Exchange (ETDEWEB)

Herranz, L. E.; Lopez, C.

2013-07-01

The OECD Spent Fuel Project (SFP) investigated fuel degradation in case of a complete Loss-Of- Coolant-Accident in a PWR spent fuel pool. Analyses of the SFP PWR ignition tests have been conducted with the 1.86.YT.3084.SFP MELCOR version developed by SNL. The main emphasis has been placed on assessing the MELCOR predictive capability to get reasonable estimates of time-to-ignition and fire front propagation under two configurations: hot neighbor (i.e., adiabatic scenario) and cold neighbor (i.e., heat transfer to adjacent fuel assemblies). A detailed description of hypotheses and approximations adopted in the MELCOR model are provided in the paper. MELCOR results accuracy was notably different between both scenarios. The reasons are highlighted in the paper and based on the results understanding a set of remarks concerning scenarios modeling is given.

Computer code SICHTA-85/MOD 1 for thermohydraulic and mechanical modelling of WWER fuel channel behaviour during LOCA and comparison with original version of the SICHTA code

International Nuclear Information System (INIS)

Bujan, A.; Adamik, V.; Misak, J.

1986-01-01

A brief description is presented of the expansion of the SICHTA-83 computer code for the analysis of the thermal history of the fuel channel for large LOCAs by modelling the mechanical behaviour of fuel element cladding. The new version of the code has a more detailed treatment of heat transfer in the fuel-cladding gap because it also respects the mechanical (plastic) deformations of the cladding and the fuel-cladding interaction (magnitude of contact pressure). Also respected is the change in pressure of the gas filling of the fuel element, the mechanical criterion is considered of a failure of the cladding and the degree is considered of the blockage of the through-flow cross section for coolant flow in the fuel channel. The LOCA WWER-440 model computation provides a comparison of the new SICHTA-85/MOD 1 code with the results of the original 83 version of SICHTA. (author)

The distribution, atmospheric transfer, and assessment of krypton-85

International Nuclear Information System (INIS)

Pannetier, R.

1968-06-01

Techniques for sampling and measuring krypton-85 have been developed which allowed to determine its geographical distribution. From its use as a tracer, an evaluation of the air masses which cross over the subtropical fronts has been derived. Besides, the stratospheric character of air pollution by krypton-85 at the level of the antarctic soil has been shown out. Levels of krypton-85 seem to point out to an underestimation of the assessment of nuclear explosion fission energies as adopted by the United Nations Scientific committee on the effects of atomic radiation and emphasize the need to set limits as soon as possible to the amounts of krypton-85 released to the atmosphere by fuel-reprocessing plants. (author) [fr

40 CFR 600.209-85 - Calculation of fuel economy values for labeling.

Science.gov (United States)

2010-07-01

... (CONTINUED) ENERGY POLICY FUEL ECONOMY AND CARBON-RELATED EXHAUST EMISSIONS OF MOTOR VEHICLES Fuel Economy Regulations for 1977 and Later Model Year Automobiles-Procedures for Calculating Fuel Economy Values § 600.209... 40 Protection of Environment 29 2010-07-01 2010-07-01 false Calculation of fuel economy values for...

Telematics Options and Capabilities

Energy Technology Data Exchange (ETDEWEB)

Hodge, Cabell [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

2017-09-05

This presentation describes the data tracking and analytical capabilities of telematics devices. Federal fleet managers can use the systems to keep their drivers safe, maintain a fuel efficient fleet, ease their reporting burden, and save money. The presentation includes an example of how much these capabilities can save fleets.

Dietas contendo silagem de milho (Zea maiz L. e feno de capim-tifton 85 (Cynodon spp. em diferentes proporções para bovinos Corn silage and tifton 85 bermudagrass hay-based diets for steers

Directory of Open Access Journals (Sweden)

Ana Clara Rodrigues Cavalcante

2004-12-01

Full Text Available Avaliaram-se o consumo, a digestibilidade, o pH e concentração de amônia ruminais e a taxa de passagem em bovinos alimentados com dietas contendo feno de capim-tifton 85 (TIF e silagem de milho (SM em diferentes proporções. Utilizaram-se quatro animais castrados, com peso médio de 523kg, fistulados no rúmen, distribuídos em um quadrado latino 4 x 4, recebendo 60% de volumoso e 40% de concentrado, na base da matéria seca. O volumoso consistiu das seguintes proporções (%: 100 TIF:0 SM; 67 TIF:33 SM; 33 TIF:67 SM e 0 TIF:100 SM. Os consumos de matéria seca (MS, de matéria orgânica (MO e de matéria orgânica digestível (MOD, de proteína bruta (PB, de fibra em detergente neutro (FDN e de carboidratos totais (CHOT e digeríveis (CHOD não foram influenciados pelas diferentes proporções de feno de capim-tifton 85: silagem de milho nas dietas, registrando-se valores médios de 9,2; 8,7; 6,4; 1,1; 3,7; 7,3 e 5,4 kg/dia, respectivamente. O consumo de extrato etéreo (EE elevou linearmente com o aumento da silagem de milho nas dietas. As digestibilidades aparentes da MS, MO, PB, EE e CHO também não foram influenciadas pelas diferentes proporções de silagem de milho, obtendo-se, respectivamente, valores médios de 71,8; 73,0; 69,5; 69,2 e 73,9%. Para a digestibilidade da FDN, observou-se efeito quadrático, estimando-se valor máximo de 65,2% para dietas contendo 30,98% de silagem de milho. Estimou-se concentração máxima de amônia de 12,0 mg/100 ml e valor mínimo de pH de 5,98 às 2,44 e 6,82 horas após a alimentação, respectivamente. A taxa de passagem não foi influenciada pelas diferentes proporções de feno:silagem, no volumoso, apresentando valor médio de 4,2%/hora.The intake, digestibility, ruminal pH and ammonia concentrations and passage rate were evaluated in steers fed corn silage (CS and Tifton 85 bermudagrass hay (T85H-based diets, at different forage proportions. Four rumen fistulated steers with 523 kg of live

Irradiation temperature memorization by retention of krypton-85. Application to the temperature determination for the internal cladding surface of fuel elements in PWR

International Nuclear Information System (INIS)

Fremiot, Claude

1977-01-01

The temperature of the inner surface of the cladding fuel elements, which can not be measured directly, can be determined after irradiation. During its stage within the reactor, the cladding is bombarded by krypton-85 fission product, which is trapped in the metallic lattice defects. The experience shows that the krypton release during postirradiation heating takes place at the irradiation temperature. This method was applied for PWR fuel element. A very simple model for retention and release of the krypton is proposed. The krypton trap-energy in zircaloy partakes in this model. This technique can be ordered amongst the Hot'Lab' control methods and expert appraisements. It is pointed out that the principal interest in that method is the fact that it does not need any fuel element instrumentation. At the present, this method is being used by CEA for routine-control. [fr

Results of post-irradiation examination of WWER fuel assembly structural components made of E110 and E635 alloys

International Nuclear Information System (INIS)

Smirnov, A.; Markov, D.; Smirnov, V.; Polenok, V.; Ivashchenko, A.; Strozhuk, A.

2006-01-01

The paper presents the main examination results on the condition of fuel rods claddings, guide tubes and spacer grids of the WWER FA made of E110 and E635 alloys operated under standard operating conditions. The paper is based on the data obtained during the examination of 28 WWER-1000 FA and 12 WWER-400 FA. E110 alloy is shown to be suitable material for the WWER fuel rod claddings under the normal operating conditions. E635 alloy is attractive to manufacturing of the skeleton components. The currently used combination (E110 as a material of fuel rods claddings and E635 - as a material of the skeleton components) is the optimal solution for the WWER fuel assembly because the advantages of the both alloys are used. (authors)

Simulations of Atmospheric Krypton-85 to Assess the Detectability of Clandestine Nuclear Reprocessing

International Nuclear Information System (INIS)

Ross, O.; Ahlswede, J.; Annewandter, R.; Kalinowski, M.B.; Rast, S.; Schluenzen, K.H.

2010-01-01

The results of this study were achieved in the project 'Simulation of Atmospheric Noble Gas Concentrations to Assess Sampling Procedures for the Detection of Clandestine Nuclear Reprocessing' (IAEA GER 1643) in the joint programme of IAEA and Federal Government of Germany. In the first year of the project the detectability of additional krypton-85 sources was investigated using atmospheric transport modelling. Krypton-85 is released into the air during reprocessing of spent nuclear fuel rods. Therefore the krypton-85 signature can possibly be used for the detection of undeclared plutonium separation. First, the global krypton-85 background produced by known reprocessing facilities from 1971 until 2006 was simulated with the atmospheric general circulation model ECHAM5 using annual emission data. The model results were evaluated by extensive comparison with measurements performed by the German Federal Office for Radiation Protection. Of particular interest for an assessment of the detectability of unknown sources is the background variability. The variability of concentrations is very high over central Europe, where the large reprocessing plants La Hague and Sellafield are located, and it is very low on the Southern Hemisphere, where no nuclear reprocessing takes place. The analysis of concentration time series on various time scales allows partly a distinction between fluctuations caused by the variability of the sources from variations due to atmospheric dynamics. Furthermore the detection sensitivity to a set of arbitrarily specified source locations is analysed with a Lagrangian particle dispersion model. This, in combination with the location specific background variability, is giving first benchmarks on the capability of using krypton-85 for IAEA Safeguards based on the Additional Protocols foreseeing environmental sampling. (author)

Cross checking of the new capabilities of the fuel cycle scenario code TR-EVOL - 5229

International Nuclear Information System (INIS)

Merino-Rodriguez, I.; Garcia-Martinez, M.; Alvarez-Velarde, F.

2015-01-01

This work is intended to cross check the new capabilities of the fuel cycle scenario code TR-EVOL by means of comparing its results with those published in bibliography. This process has been divided in two stages as follows. The first stage is dedicated to check the improvements in the material management part of the fuel cycle code (the nuclear fuel mass balance estimation). The Spanish nuclear fuel cycle has been chosen as the model for the mass balance comparison given that the fuel mass per reactor is available in bibliography. The second stage has been focused in verifying the validity of the TR-EVOL economic module. The economic model verification has been carried out by making use of the ARCAS EU project and its economic assessments for advanced reactors and scenarios involving fast reactors and ADS. As conclusions, the main finding from the first stage includes that TR-EVOL provides a prediction of mass values quite accurate after the improvements and when using the proper parameters as input for the code. For the second stage, results were highly satisfactory since a difference smaller than 3% can be found regarding results published by the ARCAS project (NRG estimations). Furthermore, concerning the Decommissioning, Dismantling and Disposal cost, results are highly acceptable (7% difference in the comparison with the final disposal in a once-through scenario and around 11% in a final disposal with a reprocessing strategy) given the difficulties to find in bibliography detailed information about the costs of the final disposals and the significant uncertainties involved in design concepts and related unit costs

HTGR fuel and fuel cycle technology

International Nuclear Information System (INIS)

Lotts, A.L.; Homan, F.J.; Balthesen, E.; Turner, R.F.

1977-01-01

Significant advances have occurred in the development of HTGR fuel and fuel cycle. These accomplishments permit a wide choice of fuel designs, reactor concepts, and fuel cycles. Fuels capable of providing helium outlet temperatures of 750 0 C are available, and fuels capable of 1000 0 C outlet temperatures may be expected from extension of present technology. Fuels have been developed for two basic HTGR designs, one using a spherical (pebble bed) element and the other a prismatic element. Within each concept a number of variations of geometry, fuel composition, and structural materials are permitted. Potential fuel cycles include both low-enriched and high-enriched Th- 235 U, recycle Th- 233 U, and Th-Pu or U-Pu cycles. This flexibility offered by the HTGR is of great practical benefit considering the rapidly changing economics of power production. The inflation of ore prices has increased optimum conversion ratios, and increased the necessity of fuel recycle at an early date. Fuel element makeup is very similar for prismatic and spherical designs. Both use spherical fissile and fertile particles coated with combinations of pyrolytic carbon and silicon carbide. Both use carbonaceous binder materials, and graphite as the structural material. Weak-acid resin (WAR) UO 2 -UC 2 fissile fuels and sol-gel-derived ThO 2 fertile fuels have been selected for the Th- 233 U cycle in the prismatic design. Sol-gel-derived UO 2 UC 2 is the reference fissile fuel for the low-enriched pebble bed design. Both the United States and Federal Republic of Germany are developing technology for fuel cycle operations including fabrication, reprocessing, refabrication, and waste handling. Feasibility of basic processes has been established and designs developed for full-scale equipment. Fuel and fuel cycle technology provide the basis for a broad range of applications of the HTGR. Extension of the fuels to higher operating temperatures and development and commercial demonstration of fuel

Nuclear Fuels & Materials Spotlight Volume 5

Energy Technology Data Exchange (ETDEWEB)

Petti, David Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-10-01

As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system. • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.

Review of global environmental-transport models for 3H, 14C, 85Kr, and 129I

International Nuclear Information System (INIS)

Kocher, D.C.; Killough, G.G.

1983-01-01

Global environmental transport models for the long-lived and mobile radionuclides 3 H, 14 C, 85 Kr, and 129 I are reviewed from the perspective of their application to collective dose assessments following releases, e.g., from the nuclear fuel cycle. Contributions to the collective dose commitment from first-pass local and regional exposures are compared. Current global models for 14 C and 85 Kr appear to be satisfactory for dose assessment purposes. Global modeling for 3 H is more difficult than for 14 C and 85 Kr, because of the different physico-chemical forms in which atmospheric releases occur. Global models for 129 I models indicate the primary importance of retention in surface soils for collective doses during the first 10 4 years following atmospheric releases and the importance of long-term transport to ocean sediments for reducing the dose commitment

High reliability fuel in the US

International Nuclear Information System (INIS)

Neuhold, R.J.; Leggett, R.D.; Walters, L.C.; Matthews, R.B.

1986-05-01

The fuels development program of the United States is described for liquid metal reactors (LMR's). The experience base, status and future potential are discussed for the three systems - oxide, metal and carbide - that have proved to have high reliability. Information is presented showing burnup capability of the oxide fuel system in a large core, e.g., FFTF, to be 150 MWd/kgM with today's technology with the potential for a capability as high as 300 MWd/kgM. Data provided for the metal fuel system show 8 at. % being routinely achieved as the EBR-II driver fuel with good potential for extending this to 15 at. % since special test pins have already exceeded this burnup level. The data included for the carbide fuel system are from pin and assembly irradiations in EBR-II and FFTF, respectively. Burnup to 12 at. % appears readily achievable with burnups to 20 at. % being demonstrated in a few pins. Efforts continue on all three systems with the bulk of the activity on metal and oxide

Study on the possibility of sea-disposal of krypton-85

International Nuclear Information System (INIS)

Dalen, A. van; Vons, L.H.; Verkerk, B.

1980-01-01

Results of a feasibility study, performed under a contract with the Commission of the European Communities, regarding technical and radiological aspects of sea-disposal of all krypton-85 retained in a large fuel reprocessing facility, are presented. The design of a double-walled, essentially spherical container is described that provides both double containment of the compressed gas and permanent 'disposable' radiation shielding. Three sizes have been studied, i.e. with internal volumes of 0.01, 0.05 and 0.1 m 3 , each designed to hold 0.1 m 3 (STP) of krypton, and each containing approximately 400 TBq of 85 Kr per 0.001 m 3 sphere volume. This results in an internal heat production of 17.5 kW/m 3 . Calculations of temperatures and stresses that would result from the conditions of the required fire test for B(U) transport packages showed that the design would allow the containers to pass this test. Radiological consequences have been considered for disposal of petabecquerel amounts of 85 Kr as a function of undamaged container lifetime on the sea bed. Finally, an indication is given of the necessary amendments to the London Convention in order to allow sea-disposal of these large amounts of radioactive krypton. (author)

Influence of oxygen-metal ratio on mixed-oxide fuel performance

International Nuclear Information System (INIS)

Lawrence, L.A.; Leggett, R.D.

1979-04-01

The fuel oxygen-to-metal ratio (O/M) is recognized as an important consideration for performance of uranium--plutonium oxide fuels. An overview of the effects of differing O/M's on the irradiation performance of reference design mixed-oxide fuel in the areas of chemical and mechanical behavior, thermal performance, and fission gas behavior is presented. The pellet fuel has a nominal composition of 75 wt% UO 2 + 25 wt% PuO 2 at a pellet density of approx. 90% TD. for nominal conditions this results in a smeared density of approx. 85%. The cladding in all cases is 20% CW type 316 stainless steel with an outer diameter of 5.84 to 6.35 mm. O/M has been found to significantly influence fuel pin chemistry, mainly FCCI and fission product and fuel migration. It has little effect on thermal performance and overall mechanical behavior or fission gas release. The effects of O/M (ranging from 1.938 to 1.984) in the areas of fuel pin chemistry, to date, have not resulted in any reduction in fuel pin performance capability to goal burnups of approx. 8 atom% or more

FFTF reload core nuclear design for increased experimental capability

International Nuclear Information System (INIS)

Rothrock, R.B.; Nelson, J.V.; Dobbin, K.D.; Bennett, R.A.

1976-01-01

In anticipation of continued growth in the FTR experimental irradiations program, the enrichments for the next batches of reload driver fuel to be manufactured have been increased to provide a substantially enlarged experimental reactivity allowance. The enrichments for these fuel assemblies, termed ''Cores 3 and 4,'' were selected to meet the following objectives and constraints: (1) maintain a reactor power capability of 400 MW (based on an evaluation of driver fuel centerline melting probability at 15 percent overpower); (2) provide a peak neutron flux of nominally 7 x 10 15 n/cm 2 -sec, with a minimum acceptable value of 95 percent of this (i.e., 6.65 x 10 15 n/cm 2 -sec); and (3) provide the maximum experimental reactivity allowance that is consistent with the above constraints

Development and Validation of Capabilities to Measure Thermal Properties of Layered Monolithic U-Mo Alloy Plate-Type Fuel

Science.gov (United States)

Burkes, Douglas E.; Casella, Andrew M.; Buck, Edgar C.; Casella, Amanda J.; Edwards, Matthew K.; MacFarlan, Paul J.; Pool, Karl N.; Smith, Frances N.; Steen, Franciska H.

2014-07-01

The uranium-molybdenum (U-Mo) alloy in a monolithic form has been proposed as one fuel design capable of converting some of the world's highest power research reactors from the use of high enriched uranium to low enriched uranium. One aspect of the fuel development and qualification process is to demonstrate appropriate understanding of the thermal-conductivity behavior of the fuel system as a function of temperature and expected irradiation conditions. The purpose of this paper is to verify functionality of equipment installed in hot cells for eventual measurements on irradiated uranium-molybdenum (U-Mo) monolithic fuel specimens, refine procedures to operate the equipment, and validate models to extract the desired thermal properties. The results presented here demonstrate the adequacy of the equipment, procedures, and models that have been developed for this purpose based on measurements conducted on surrogate depleted uranium-molybdenum (DU-Mo) alloy samples containing a Zr diffusion barrier and clad in aluminum alloy 6061 (AA6061). The results are in excellent agreement with thermal property data reported in the literature for similar U-Mo alloys as a function of temperature.

Kr-85 signatures for various plutonium production schemes

Energy Technology Data Exchange (ETDEWEB)

Stanoszek, Paul [Carl Friedrich von Weizsaecker-Centre for Science and Peace Research (Germany)

2009-07-01

Kr-85 is considered to be the best atmospheric indicator of unreported weapon-grade material production. This fact is based on the half-life of 10.76 years of Kr-85 and its chemical inactivity, which makes it even detectable after extended periods of cooling time. Kr-85 is produced as fission product during nuclear reactor operation and remains in the fuel until reprocessing starts. In order to determine the detectability of plutonium production the Kr-85 source term has to be assessed. The important issue of this presentation is the question on the minimum signal that an inspector can expect under the assumption that a proliferator minimizes his Kr-85 generation in order to circumvent a Kr-85 detection. A further assumption is that for nuclear weapon production a burn-up of typically around 2 MWd/kg is used. In addition, if clandestine plutonium production takes place, the source term might be used to estimate the amount of separated plutonium. The methodology of this study is based on a linkage between MCNPX and MATLAB. All results for actinide concentrations and Kr-85 are evaluated for different enrichments of U-235 and compared to known literature data. The Kr-85 source term per kilogram plutonium depends on the enrichments. As a result the lowest Kr-85 source term is found for depleted uranium.

A study of the stabilities, microstructures and fuel characteristics of tri-fuel (diesel-biodiesel-ethanol) using various fuel preparation methods

Science.gov (United States)

Lee, K. H.; Mukhtar, N. A. M.; Yohaness Hagos, Ftwi; Noor, M. M.

2017-10-01

In this study, the work was carried out to investigate the effects of ethanol proportions on the stabilities and physicochemical characteristics of tri-fuel (Diesel-Biodiesel-Ethanol). For the first time, tri-fuel emulsions and blended were compared side by side. The experiment was done with composition having 5%, 10%, 15%, 20% and 25 % of ethanol with fixed 10% of biodiesel from palm oil origin on a volume basis into diesel. The results indicated that the phase stabilities of the emulsified fuels were higher compared to the blended fuels. In addition, tri-fuel composition with higher proportion of ethanol were found unstable with high tendency to form layer separation. It was found that tri-fuel emulsion with 5% ethanol content (D85B10E5) was of the best in stability with little separation. Furthermore, tri-fuel with lowest ethanol proportion indicated convincing physicochemical characteristics compared to others. Physicochemical characteristics of tri-fuel blending yield almost similar results to tri-fuel emulsion but degrading as more proportion ethanol content added. Emulsion category had cloudy look but on temporarily basis. Under the microscope, tri-fuel emulsion and blending droplet were similar for its active moving about micro-bubble but distinct in term of detection of collision, average disperse micro-bubble size, the spread and organization of the microstructure.

Effects of control technology on the projected krypton-85 environmental inventory

International Nuclear Information System (INIS)

Oscarson, E.E.

1973-01-01

Growth projections for the USA nuclear power industry may be used to make projections of future radioactive material inventories available for potential release to the environment. Since krypton-85 is produced in reactors, the potential routes of release to the environment are at the reactors or the fuel reprocessing plants. The present generation of reactors and fuel reprocessing plants do not use any systems to limit the release of krypton-85 into the biosphere. Clean-up systems are currently being designed and could be introduced when necessary. The cumulative inventory of krypton-85 in the environment is dependent upon the time of introduction of these clean-up systems and their efficiencies, in addition to the total quantity produced. Annual and cumulative inventories of krypton-85 are projected to increase dramatically over the next 50 years. If controls are assumed to be initiated at various years, a series of graphs of different cumulative environmental inventories and the associated doses and health effects are drawn. Varying the year of introduction and the efficiency of these systems allows one to speculate as to the optimum time for control implementation

ISO New England Dual Fuel Capabilities to Limit Natural Gas and Electricity Interdependencies

Energy Technology Data Exchange (ETDEWEB)

Adder, Justin M. [National Energy Technology Lab. (NETL), Pittsburgh, PA, (United States)

2016-04-22

Since 2000, natural gas has seen tremendous growth as a fuel source for electricity generation in the United States (U.S.) with annual installations exceeding 20 GW in all but four years. It also accounts for an increasingly significant share of the nation’s electricity generation, growing from around 15 percent in the early part of the 2000s to between 26 and 29 percent in the last three years. (1) Increasing reliance on natural gas has led to concerns that an extreme weather event – which may cause curtailments in gas delivery – or a natural gas infrastructure failure could lead to local or regional electric reliability issues. (2) These concerns stem from differences in delivery methods of natural gas to electric generating units (EGUs) contrasted with the fuel delivery and storage methods for traditional baseload power systems (i.e. coal and nuclear units).1 (3) Although it seems that there is an abundance of natural gas in a post-shale gas world, infrastructure limitations and differences in electric and natural gas markets persist that differentiate natural gas-fired generators from traditional baseload power generators. Such concerns can be partially mitigated by modifying natural gas EGUs for operation on secondary fuels and installing on-site fuel storage for the secondary fuel, thus ensuring continuity of operation in the case of a gas delivery problem.2 This report examines technical, regulatory, and market issues associated with operating power plants primarily fueled with natural gas, on a secondary fuel, such as fuel oil or liquefied natural gas (LNG). In addition, a regional case study was completed to identify the current and near-term potential for dual fuel operation in New England, along with a market impact analysis of potential cost savings during an extreme weather event. The New England Independent System Operator (ISO-NE) was selected as the study area based on a preponderance of natural gas-fired generators contributing to the

Enhanced CANDU 6 (EC6): a proven mid-sized reactor with fuel cycle capability

International Nuclear Information System (INIS)

Hopwood, J.; Soulard, M.; Hastings, I.J.

2011-01-01

Atomic Energy of Canada (AECL) is finalizing development of the Enhanced CANDU 6 (EC6), which incorporates the CANDU 6's well-proven features, and adds enhancements that make the reactor even more safe and easier to operate. The EC6 is the only mid-sized reactor (700 MWe class) with a proven pedigree that meets modern reactor expectations and regulatory standards. It is sized for smaller grids and also has outstanding fuel-cycle capability. Changes are incremental and consistent with the CANDU 6 project approach. The EC6 utilizes modern computers and a distributed control system housed in an advanced control room which, along with automated testing and on-line diagnostics, make the plant easier and safer to operate, with minimal operator intervention. Containment and seismic capability are upgraded to meet modern standards. The first deployment of the EC6 is anticipated in Canada; international markets are also being pursued. AECL is performing a comprehensive review of the EC6 design in the wake of the Fukushima accident, will review lessons learned, and incorporate any necessary improvements into new build design. (author)

Enhanced CANDU 6 (EC6): a proven mid-sized reactor with fuel cycle capability

International Nuclear Information System (INIS)

Hopwood, J.; Soulard, M.; Hastings, I.J.

2011-01-01

Atomic Energy of Canada (AECL) is finalizing development of the Enhanced CANDU 6 (EC6), which incorporates the CANDU 6's well-proven features, and enhancements that make the reactor even more safe and easier to operate. The EC6 is the only mid-sized reactor (700 MWe class) with a proven pedigree that meets modern reactor expectations and regulatory standards. It is sized for smaller grids and also has outstanding fuel-cycle capability. Changes are incremental and consistent with the CANDU 6 project approach. The EC6 utilizes modern computers and a distributed control system housed in an advanced control room which, along with automated testing and on-line diagnostics, make the plant easier and safer to operate, with minimal operator intervention. Containment and seismic capability are upgraded to meet modern standards. The first deployment of the EC6 is anticipated in Canada; international markets are also being pursued. AECL is performing a comprehensive review of the EC6 design in the wake of the Fukushima accident, will review lessons learned, and incorporate any necessary improvements into new build design. (author)

A database system for enhancing fuel records management capabilities

International Nuclear Information System (INIS)

Rieke, Phil; Razvi, Junaid

1994-01-01

The need to modernize the system of managing a large variety of fuel related data at the TRIGA Reactors Facility at General Atomics, as well as the need to improve NRC nuclear material reporting requirements, prompted the development of a database to cover all aspects of fuel records management. The TRIGA Fuel Database replaces (a) an index card system used for recording fuel movements, (b) hand calculations for uranium burnup, and (c) a somewhat aged and cumbersome system of recording fuel inspection results. It was developed using Microsoft Access, a relational database system for Windows. Instead of relying on various sources for element information, users may now review individual element statistics, record inspection results, calculate element burnup and more, all from within a single application. Taking full advantage of the ease-of-use features designed in to Windows and Access, the user can enter and extract information easily through a number of customized on screen forms, with a wide variety of reporting options available. All forms are accessed through a main 'Options' screen, with the options broken down by categories, including 'Elements', 'Special Elements/Devices', 'Control Rods' and 'Areas'. Relational integrity and data validation rules are enforced to assist in ensuring accurate and meaningful data is entered. Among other items, the database lets the user define: element types (such as FLIP or standard) and subtypes (such as fuel follower, instrumented, etc.), various inspection codes for standardizing inspection results, areas within the facility where elements are located, and the power factors associated with element positions within a reactor. Using fuel moves, power history, power factors and element types, the database tracks uranium burnup and plutonium buildup on a quarterly basis. The Fuel Database was designed with end-users in mind and does not force an operations oriented user to learn any programming or relational database theory in

Regulatory cross-cutting topics for fuel cycle facilities.

Energy Technology Data Exchange (ETDEWEB)

Denman, Matthew R.; Brown, Jason; Goldmann, Andrew Scott; Louie, David

2013-10-01

This report overviews crosscutting regulatory topics for nuclear fuel cycle facilities for use in the Fuel Cycle Research & Development Nuclear Fuel Cycle Evaluation and Screening study. In particular, the regulatory infrastructure and analysis capability is assessed for the following topical areas: Fire Regulations (i.e., how applicable are current Nuclear Regulatory Commission (NRC) and/or International Atomic Energy Agency (IAEA) fire regulations to advance fuel cycle facilities) Consequence Assessment (i.e., how applicable are current radionuclide transportation tools to support risk-informed regulations and Level 2 and/or 3 PRA) While not addressed in detail, the following regulatory topic is also discussed: Integrated Security, Safeguard and Safety Requirement (i.e., how applicable are current Nuclear Regulatory Commission (NRC) regulations to future fuel cycle facilities which will likely be required to balance the sometimes conflicting Material Accountability, Security, and Safety requirements.)

Nickel-based anode with water storage capability to mitigate carbon deposition for direct ethanol solid oxide fuel cells.

Science.gov (United States)

Wang, Wei; Su, Chao; Ran, Ran; Zhao, Bote; Shao, Zongping; Tade, Moses O; Liu, Shaomin

2014-06-01

The potential to use ethanol as a fuel places solid oxide fuel cells (SOFCs) as a sustainable technology for clean energy delivery because of the renewable features of ethanol versus hydrogen. In this work, we developed a new class of anode catalyst exemplified by Ni+BaZr0.4Ce0.4Y0.2O3 (Ni+BZCY) with a water storage capability to overcome the persistent problem of carbon deposition. Ni+BZCY performed very well in catalytic efficiency, water storage capability and coking resistance tests. A stable and high power output was well maintained with a peak power density of 750 mW cm(-2) at 750 °C. The SOFC with the new robust anode performed for seven days without any sign of performance decay, whereas SOFCs with conventional anodes failed in less than 2 h because of significant carbon deposition. Our findings indicate the potential applications of these water storage cermets as catalysts in hydrocarbon reforming and as anodes for SOFCs that operate directly on hydrocarbons. © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Hazard identification of exhausts from gasoline-ethanol fuel blends using a multi-cellular human lung model.

Science.gov (United States)

Bisig, Christoph; Roth, Michèle; Müller, Loretta; Comte, Pierre; Heeb, Norbert; Mayer, Andreas; Czerwinski, Jan; Petri-Fink, Alke; Rothen-Rutishauser, Barbara

2016-11-01

Ethanol can be produced from biomass and as such is renewable, unlike petroleum-based fuel. Almost all gasoline cars can drive with fuel containing 10% ethanol (E10), flex-fuel cars can even use 85% ethanol (E85). Brazil and the USA already include 10-27% ethanol in their standard fuel by law. Most health effect studies on car emissions are however performed with diesel exhausts, and only few data exists for other fuels. In this work we investigated possible toxic effects of exhaust aerosols from ethanol-gasoline blends using a multi-cellular model of the human lung. A flex-fuel passenger car was driven on a chassis dynamometer and fueled with E10, E85, or pure gasoline (E0). Exhausts obtained from a steady state cycle were directly applied for 6h at a dilution of 1:10 onto a multi-cellular human lung model mimicking the bronchial compartment composed of human bronchial cells (16HBE14o-), supplemented with human monocyte-derived dendritic cells and monocyte-derived macrophages, cultured at the air-liquid interface. Biological endpoints were assessed after 6h post incubation and included cytotoxicity, pro-inflammation, oxidative stress, and DNA damage. Filtered air was applied to control cells in parallel to the different exhausts; for comparison an exposure to diesel exhaust was also included in the study. No differences were measured for the volatile compounds, i.e. CO, NO x , and T.HC for the different ethanol supplemented exhausts. Average particle number were 6×10 2 #/cm 3 (E0), 1×10 5 #/cm 3 (E10), 3×10 3 #/cm 3 (E85), and 2.8×10 6 #/cm 3 (diesel). In ethanol-gasoline exposure conditions no cytotoxicity and no morphological changes were observed in the lung cell cultures, in addition no oxidative stress - as analyzed with the glutathione assay - was measured. Gene expression analysis also shows no induction in any of the tested genes, including mRNA levels of genes related to oxidative stress and pro-inflammation, as well as indoleamine 2,3-dioxygenase 1

The Application of Dynamic Capabilities in E-commerce Innovation Context : The Implications for Chinese E-commerce companies

OpenAIRE

Chen, YongJia; Liang, WeiMin

2007-01-01

This study mainly investigated how Chinese E-commerce companies should cope with E-commerce innovation with specific dynamic capabilities. E-commerce (Electronic Commerce) innovation includes three phases of innovation based on technology and time. They are web-based commerce, mobile commerce (M-commerce) and ubiquitous commerce (U-commerce). They caused not only technological changes but also organizational changes. To cope with E-commerce innovation, a prerequisite is to understand the impa...

Enhancing the ABAQUS Thermomechanics Code to Simulate Steady and Transient Fuel Rod Behavior

International Nuclear Information System (INIS)

Williamson, R.L.; Knoll, D.A.

2009-01-01

A powerful multidimensional fuels performance capability, applicable to both steady and transient fuel behavior, is developed based on enhancements to the commercially available ABAQUS general-purpose thermomechanics code. Enhanced capabilities are described, including: UO2 temperature and burnup dependent thermal properties, solid and gaseous fission product swelling, fuel densification, fission gas release, cladding thermal and irradiation creep, cladding irradiation growth, gap heat transfer, and gap/plenum gas behavior during irradiation. The various modeling capabilities are demonstrated using a 2D axisymmetric analysis of the upper section of a simplified multi-pellet fuel rod, during both steady and transient operation. Computational results demonstrate the importance of a multidimensional fully-coupled thermomechanics treatment. Interestingly, many of the inherent deficiencies in existing fuel performance codes (e.g., 1D thermomechanics, loose thermo-mechanical coupling, separate steady and transient analysis, cumbersome pre- and post-processing) are, in fact, ABAQUS strengths.

Liquefied Gaseous Fuels Spill Test Facility: Overview of STF capabilities

International Nuclear Information System (INIS)

Gray, H.E.

1993-01-01

The Liquefied Gaseous Fuels Spill Test Facility (STF) constructed at the Department of Energy's Nevada Test Site is a basic research tool for studying the dynamics of accidental releases of various hazardous liquids. This Facility is designed to (1) discharge, at a controlled rate, a measured volume of hazardous test liquid on a prepared surface of a dry lake bed (Frenchman Lake); (2) monitor and record process operating data, close-in and downwind meteorological data, and downwind gaseous concentration levels; and (3) provide a means to control and monitor these functions from a remote location. The STF will accommodate large and small-scale testing of hazardous test fluid release rates up to 28,000 gallons per minute. Spill volumes up to 52,800 gallons are achievable. Generic categories of fluids that can be tested are cryogenics, isothermals, aerosol-forming materials, and chemically reactive. The phenomena that can be studied include source definition, dispersion, and pool fire/vapor burning. Other capabilities available at the STF include large-scale wind tunnel testing, a small test cell for exposing personnel protective clothing, and an area for developing mitigation techniques

Spent LWR fuel encapsulation and dry storage demonstration

International Nuclear Information System (INIS)

Bahorich, R.J.; Durrill, D.C.; Cross, T.E.; Unterzuber, R.

1980-01-01

In 1977 the Spent Fuel Handling and Packaging Program (SFHPP) was initiated by the Department of Energy to develop and test the capability to satisfactorily encapsulate typical spent fuel assemblies from commercial light-water nuclear power plants and to establish the suitability of one or more surface and near surface concepts for the interim dry storage of the encapsulated spent fuel assemblies. The E-MAD Facility at the Nevada Test Site, which is operated for the Department of Energy by the Advanced Energy Systems Division (AESD) of the Westinghouse Electric Corporation, was chosen as the location for this demonstration because of its extensive existing capabilities for handling highly radioactive components and because of the desirable site characteristics for the proposed storage concepts. This paper describes the remote operations related to the process steps of handling, encapsulating and subsequent dry storage of spent fuel in support of the Demonstration Program

Siemens capabilities to perform detailed fuel inspections during short outages

International Nuclear Information System (INIS)

Knecht, K.; Reparaz, A.

1999-01-01

Fuel inspection data are used to support development activities such as corrosion resistant cladding and advanced fuel assembly designs that will reach higher burnups. Increased inspection efforts are necessary to optimize fuel management and performance strategies. Additionally, there is an increasing trend to reduce outage time in Germany and abroad. Siemens has recently developed several timesaving systems for rapid inspection of fuel assemblies and core components. Siemens' focus in developing these systems has been to obtain data in reduced reactor outage time while increasing both the volume and the quality of the measured data. Mast sipping for PWRs is used for identifying leaking fuel assemblies and allows early detection of leaks during downloading of the fuel assemblies from the reactor. An In-Core sipping system for BWRs based on a hood technique to allow testing a full core within 16 hours is under development. (authors)

Kr-85m activity as burnup measurement indicator in a pebble bed reactor based on ORIGEN2.1 Computer Simulation

Science.gov (United States)

Husnayani, I.; Udiyani, P. M.; Bakhri, S.; Sunaryo, G. R.

2018-02-01

Pebble Bed Reactor (PBR) is a high temperature gas-cooled reactor which employs graphite as a moderator and helium as a coolant. In a multi-pass PBR, burnup of the fuel pebble must be measured in each cycle by online measurement in order to determine whether the fuel pebble should be reloaded into the core for another cycle or moved out of the core into spent fuel storage. One of the well-known methods for measuring burnup is based on the activity of radionuclide decay inside the fuel pebble. In this work, the activity and gamma emission of Kr-85m were studied in order to investigate the feasibility of Kr-85m as burnup measurement indicator in a PBR. The activity and gamma emission of Kr-85 were estimated using ORIGEN2.1 computer code. The parameters of HTR-10 were taken as a case study in performing ORIGEN2.1 simulation. The results show that the activity revolution of Kr-85m has a good relationship with the burnup of the pebble fuel in each cycle. The Kr-85m activity reduction in each burnup step,in the range of 12% to 4%, is considered sufficient to show the burnup level in each cycle. The gamma emission of Kr-85m is also sufficiently high which is in the order of 1010 photon/second. From these results, it can be concluded that Kr-85m is suitable to be used as burnup measurement indicator in a pebble bed reactor.

Advanced Nuclear Fuels for More Capable and Sustainable Exploration

Data.gov (United States)

National Aeronautics and Space Administration — Molten salt reactors are a subtype of reactor that uses nuclear fuel dissolved in a molten salt liquid medium (such as LiF-BeF2-UF4) as both fuel and coolant. The...

Fuel Exhaling Fuel Cell.

Science.gov (United States)

Manzoor Bhat, Zahid; Thimmappa, Ravikumar; Devendrachari, Mruthyunjayachari Chattanahalli; Kottaichamy, Alagar Raja; Shafi, Shahid Pottachola; Varhade, Swapnil; Gautam, Manu; Thotiyl, Musthafa Ottakam

2018-01-18

State-of-the-art proton exchange membrane fuel cells (PEMFCs) anodically inhale H 2 fuel and cathodically expel water molecules. We show an unprecedented fuel cell concept exhibiting cathodic fuel exhalation capability of anodically inhaled fuel, driven by the neutralization energy on decoupling the direct acid-base chemistry. The fuel exhaling fuel cell delivered a peak power density of 70 mW/cm 2 at a peak current density of 160 mA/cm 2 with a cathodic H 2 output of ∼80 mL in 1 h. We illustrate that the energy benefits from the same fuel stream can at least be doubled by directing it through proposed neutralization electrochemical cell prior to PEMFC in a tandem configuration.

Temperature behavior of 12 wt.% U TRIGA fuel

Energy Technology Data Exchange (ETDEWEB)

Levine, S H; Geisler, G C; Totenbier, R E [Pennsylvania State University (United States)

1974-07-01

Stainless steel clad 12 wt % U TRIGA fuel elements have been used to refuel the Penn State University's Breazeale Reactor (PSBR). When 12 wt % U fuel containing nominally 55 gms of {sup 235}U per fuel element is substituted for the 8.5 wt % U fuel containing nominally 38 gms {sup 235}U, higher fuel temperatures were produced in the 12 wt % U fuel than in the 8.5 wt % U fuel at the same reactor powers. The higher fuel temperature can be related to the higher power densities in the 12 wt % U fuel. The power density is calculated to be 35% higher in the 12 wt % U fuel when 6 of these fuel elements are substituted for 8.5 wt % U fuel in the innermost ring, the B ring. Temperatures have been calculated for the 12 wt % U fuel in the above configuration for both steady state and pulse conditions, assuming a 35% higher fuel density in the 12 wt % U fuel and the results compare favorably with the experimental measurements. This is particularly true when the comparison is made with temperature data taken after exposing the new fuel elements to a series of pulses. These calculations and data will be presented at the meeting. (author)

Capabilities of Universities in Achieving the Agricultural ...

African Journals Online (AJOL)

All (100%) the respondents had no capability in acquiring machines and equipment needed for teaching and conducting researches on climate change. Majority (85%) of the respondents had no capability in terms of human resource development with regards to climate change. Funding/manpower (0.657), organizational ...

Cicerone e l’oratore tinctus litteris (de orat. 2,85: questioni testuali e stilistiche

Directory of Open Access Journals (Sweden)

Francesca Boldrer

2017-05-01

Full Text Available L’espressione metaforica sit enim mihi tinctus litteris usata da Antonio nel dialogo de oratore (2,85 a proposito di un suo possibile allievo di oratoria, viene generalmente intesa come esortativa, ma Antonio disdegnava gli studi teorici e culturali, basando invece la sua scuola sulla pratica forense. Sembra perciò opportuna una interpretazione diversa di sit e dei seguenti congiuntivi in senso concessivo (“ammettiamo che io abbia un allievo impregnato di letteratura”, cui si contrappone nella proposizione successiva l’annuncio da parte di Antonio del suo metodo pratico (fut. temptabo. Inoltre il nesso tinctus litteris è stato oggetto di varie interpretazioni riduttive nel senso di una media o scarsa cultura: più probabilmente indica invece una cultura profonda, corrispondente al diffuso ma prosaico sinonimo imbutus litteris. Il termine tinctus sembra alludere inoltre a Lucrezio, poeta (valorizzato da Cicerone che utilizza spesso tingo, ed implica una metafora cromatica positiva e raffinata. In sintesi l’oratore tinctus litteris, poco apprezzato da Antonio ma comunque accolto nella sua scuola, sembra il ritratto di Cicerone da giovane, che in effetti era stato un suo allievo letterato ed impegnato per tutta la vita a nobilitare l’oratoria sul piano stilistico più dei suoi maestri.    The metaphorical expression sit enim mihi tinctus litteris used by Antonius in the de oratore dialogue (2,85 about one of his aspiring students, is generally understood as an exhortation, although Antonius disdained theoretical and cultural studies, preferring to base his school on forensic practice instead. Sit therefore requires a different interpretation, one that steers the subjunctive mood into its concessive sense (“let’s admit that I have a student steeped in literature”, which is offset by the next sentence where Antonius announces his practical method (temptabo. Moreover, various interpretations of the collocation tinctus litteris

Kinetics of ruminal degradation of alfalfa and Tifton-85 hays, and of corn SilageCinética de degradação ruminal dos fenos de alfafa e Tifton-85 e da silagem de milho

Directory of Open Access Journals (Sweden)

Geraldo Tadeu dos Santos

2011-07-01

Full Text Available The shunt portosystemic or portosystemic deviation (PSD are unique or multiples vascular communications between the systemic circulaton and the portal circulation, that permit blood flow reaches the circulatory system without first passing trhought the hepatic metabolization. May be acquired or congenital and can also be classified as intrahepatic located within the liver or extrahepatic located outside the liver parenquima. The acquired form is usually associated with intra-hepatic disorders. They usually suggest tortuous vessels that communicate with the caudal vena cava in the region of the left kidney. The congenital form is associated with genetic lineage and one of the most affected is Maltese breed. This case report describes the diagnostis and treatment of a eight year-old female Maltese dog presenting extrahepatic Portosystemic Shunt. The patient showed signs of hepatic encephalopathy, such as restlessnees, weakness, deambulation, head tremor and impaired visual. Complementary exam demonstrated: postprandial glicemia near the lower limit of reference, alkaline phosphatase (ALP and alanine aminotransferase (ALT increased and hipoalbuminemia. Ultrasonography revealed the presence of vesical calculus and bilateral kidney, liver decreases and increased echogenicity, gallbladder with anechoic content and high cellularity may suggest liver/ colangiohepatopatia and extrahepatic DPS was detected. The use of Doppler assisted in identifying the location of the bypass communication and the turbulence detecting the extrahepatic DPS. Protein-restricted diet and antibiotic therapy with amoxicillin achieved good results. The clinical treatment was decided make only the clinical and maintain the quality of life of the patient. Objetivou-se avaliar a degradabilidade ruminal e a taxa de degradação in situ da matéria seca (MS, da proteína bruta (PB e da fibra em detergente neutro (FDN, dos fenos de alfafa e Tifton-85 e da silagem de milho. Foram

Capabilities of a DT tokamak fusion neutron source for driving a spent nuclear fuel transmutation reactor

International Nuclear Information System (INIS)

Stacey, W.M.

2001-01-01

The capabilities of a DT fusion neutron source for driving a spent nuclear fuel transmutation reactor are characterized by identifying limits on transmutation rates that would be imposed by tokamak physics and engineering limitations on fusion neutron source performance. The need for spent nuclear fuel transmutation and the need for a neutron source to drive subcritical fission transmutation reactors are reviewed. The likely parameter ranges for tokamak neutron sources that could produce an interesting transmutation rate of 100s to 1000s of kg/FPY (where FPY stands for full power year) are identified (P fus ∼ 10-100 MW, β N ∼ 2-3, Q p ∼ 2-5, R ∼ 3-5 m, I ∼ 6-10 MA). The electrical and thermal power characteristics of transmutation reactors driven by fusion and accelerator spallation neutron sources are compared. The status of fusion development vis-a-vis a neutron source is reviewed. (author)

Upgrading of TREAT experimental capabilities

International Nuclear Information System (INIS)

Dickerman, C.E.; Rose, D.; Bhattacharyya, S.K.

1982-01-01

The TREAT facility at the Argonne National Laboratory site in the Idaho National Engineering Laboratory is being upgraded to provide capabilities for fast-reactor-safety transient experiments not possible at any other experimental facility. Principal TREAT Upgrade (TU) goal is provision for 37-pin size experiments on energetics of core-disruptive accidents (CDA) in fast breeder reactor cores with moderate sodium void coefficients. this goal requires a significant enhancement of the capabilities of the TREAT facility, specifically including reactor control, hardened neutron spectrum incident on the test sample, and enlarged building. The upgraded facility will retain the capability for small-size experiments of the types currently being performed in TREAT. Reactor building and crane upgrading have been completed. TU schedules call for the components of the upgraded reactor system to be finished in 1984, including upgraded TREAT fuel and control system, and expanded coverage by the hodoscope fuel-motion diagnostics system

Alternative Fuels Data Center: City of Chicago Program Encourages Petroleum

Science.gov (United States)

lacked the funds to support such a project, but officials worked with the Chicago Area Clean Cities (CACC networking opportunities. This photo shows a parked compressed natural gas van the City of Chicago's fleet Infrastructure: 11 private E85 fueling stations Related Links Ethanol Natural Gas Chicago Area Clean Cities

Analysis of stationary fuel cell dynamic ramping capabilities and ultra capacitor energy storage using high resolution demand data

Science.gov (United States)

Meacham, James R.; Jabbari, Faryar; Brouwer, Jacob; Mauzey, Josh L.; Samuelsen, G. Scott

Current high temperature fuel cell (HTFC) systems used for stationary power applications (in the 200-300 kW size range) have very limited dynamic load following capability or are simply base load devices. Considering the economics of existing electric utility rate structures, there is little incentive to increase HTFC ramping capability beyond 1 kWs -1 (0.4% s -1). However, in order to ease concerns about grid instabilities from utility companies and increase market adoption, HTFC systems will have to increase their ramping abilities, and will likely have to incorporate electrical energy storage (EES). Because batteries have low power densities and limited lifetimes in highly cyclic applications, ultra capacitors may be the EES medium of choice. The current analyses show that, because ultra capacitors have a very low energy storage density, their integration with HTFC systems may not be feasible unless the fuel cell has a ramp rate approaching 10 kWs -1 (4% s -1) when using a worst-case design analysis. This requirement for fast dynamic load response characteristics can be reduced to 1 kWs -1 by utilizing high resolution demand data to properly size ultra capacitor systems and through demand management techniques that reduce load volatility.

Composite cathode La0.15Bi0.85O1.5-Ag for intermediate-temperature solid oxide fuel cells

International Nuclear Information System (INIS)

Gao Zhan; Mao Zongqiang; Huang Jianbing; Gao Ruifeng; Wang Cheng; Liu Zhixiang

2008-01-01

Composites consisting of silver and lanthanum stabilized bismuth oxide (La 0.15 Bi 0.85 O 1.5 ) were investigated as cathodes for intermediate-temperature solid oxide fuel cells with doped ceria as electrolyte. No stable phases were formed via reaction between La 0.15 Bi 0.85 O 1.5 and Ag. The microstructure of the interfaces between composite cathodes and Ce 0.8 Sm 0.2 O 1.5 electrolytes was studied by scanning electron microscopy after sintering at various temperatures. Impedance spectroscopy measurements revealed that the performance of cathode fired at 700 deg. C was the best. When the optimum fraction of Ag was 50 vol.%, polarization resistance values for the LSB-Ag50 cathode were as low as 0.14 Ω cm 2 at 700 deg. C and 0.18 Ω cm 2 at 650 deg. C. The steady-state polarization investigations on LSB and LSB-Ag50 cathodes were performed using typical three-electrode test cells in air. The results showed that the LSB-Ag50 composite cathode exhibited a lower overpotential and higher exchange current density than LSB, which indicated the electrochemical performance of LSB-Ag50 for the oxygen reduction reaction was superior to the LSB

Tritium distribution between the fuel can and the oxide of fuel elements of light-water reactors

International Nuclear Information System (INIS)

Masson, M.

1986-12-01

The study on the measurement of tritium and other radionuclide contained in zircaloy fuel cans of the water cooled reactor fuel elements had two aims: the first was to estimate with accuracy the distribution of tritium in a fuel element (can + oxide). The measurement of tritium in the zircaloy fuel cans of the BORSSELE fuel elements associated with the measurement of tritium in the oxide allowed the establishment of a complete tritium balance on an industrial spent fuel element. This result has been compared to the values calculated by the code CEA/SEN and will allow to validate or adjust this calculation. The second aim delt with the characterization of the other radionuclides gaseous (Kr85) or not (Cs 134 and 137) contained in the solid zircaloy wastes (hulls) coming from the industrial reprocessing of ''water cooled'' fuel elements. These activity measurements in the hulls allowed to estimate the residual content of tritium, Kr 85 and other radionuclides which may be found in these solid wastes (high-level βγ radioactive wastes). Original experimental methods have been developed to reach these aims (dissolution in ammonium bifluoride medium and quantitative recovery of gases produced, radiochromatography, and liquid scintillation after double distillation). One tries to explain the presence of Kr 85 in the irradiated can [fr

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.

Feasibility study for a DOE research and production fuel multipurpose canister

International Nuclear Information System (INIS)

Lopez, D.A.; Abbott, D.G.

1994-02-01

This is a report of the feasibility of multipurpose canisters for transporting, storing, and sing of Department of Energy research and production spent nuclear fuel. Six representative Department of Energy fuel assemblies were selected, and preconceptual canister designs were developed to accommodate these assemblies. The study considered physical interface, structural adequacy, criticality safety, shielding capability, thermal performance of the canisters, and fuel storage site infrastructure. The external envelope of the canisters was designed to fit within the overpack casks for commercial canisters being developed for the Department of Energy Office of Civilian Radioactive Waste Management. The budgetary cost of canisters to handle all fuel considered is estimated at $170.8M. One large conceptual boiling water reactor canister design, developed for the Office of Civilian Radioactive Waste Management, and two new canister designs can accommodate at least 85% of the volume of the Department of Energy fuel considered. Canister use minimizes public radiation exposure and is cost effective compared with bare fuel handling. Results suggest the need for additional study of issues affecting canister use and for conceptual design development of the three canisters

Alternative Fuels Data Center: New Mexico Transportation Data for

Science.gov (United States)

to alternative fuels and advanced vehicles Recent Additions and Updates Biodiesel Blend Mandate Public Private Biodiesel (B20 and above) 1 4 Compressed Natural Gas (CNG) 8 3 Electric 59 4 Ethanol (E85 GGE Biodiesel (B20) $2.60/gallon $2.37/GGE $2.84/gallon $2.58/GGE Biodiesel (B99-B100) $2.49/gallon

Primary emissions and secondary organic aerosol formation from the exhaust of a flex-fuel (ethanol) vehicle

Science.gov (United States)

Suarez-Bertoa, R.; Zardini, A. A.; Platt, S. M.; Hellebust, S.; Pieber, S. M.; El Haddad, I.; Temime-Roussel, B.; Baltensperger, U.; Marchand, N.; Prévôt, A. S. H.; Astorga, C.

2015-09-01

Incentives to use biofuels may result in increasing vehicular emissions of compounds detrimental to air quality. Therefore, regulated and unregulated emissions from a Euro 5a flex-fuel vehicle, tested using E85 and E75 blends (gasoline containing 85% and 75% of ethanol (vol/vol), respectively), were investigated at 22 and -7 °C over the New European Driving Cycle, at the Vehicle Emission Laboratory at the European Commission Joint Research Centre Ispra, Italy. Vehicle exhaust was comprehensively analyzed at the tailpipe and in a dilution tunnel. A fraction of the exhaust was injected into a mobile smog chamber to study the photochemical aging of the mixture. We found that emissions from a flex-fuel vehicle, fueled by E85 and E75, led to secondary organic aerosol (SOA) formation, despite the low aromatic content of these fuel blends. Emissions of regulated and unregulated compounds, as well as emissions of black carbon (BC) and primary organic aerosol (POA) and SOA formation were higher at -7 °C. The flex-fuel unregulated emissions, mainly composed of ethanol and acetaldehyde, resulted in very high ozone formation potential and SOA, especially at low temperature (860 mg O3 km-1 and up to 38 mg C kg-1). After an OH exposure of 10 × 106 cm-3 h, SOA mass was, on average, 3 times larger than total primary particle mass emissions (BC + POA) with a high O:C ratio (up to 0.7 and 0.5 at 22 and -7 °C, respectively) typical of highly oxidized mixtures. Furthermore, high resolution organic mass spectra showed high 44/43 ratios (ratio of the ions m/z 44 and m/z 43) characteristic of low-volatility oxygenated organic aerosol. We also hypothesize that SOA formation from vehicular emissions could be due to oxidation products of ethanol and acetaldehyde, both short-chain oxygenated VOCs, e.g. methylglyoxal and acetic acid, and not only from aromatic compounds.

Post Irradiation Capabilities at the Idaho National Laboratory

International Nuclear Information System (INIS)

Schulthess, J.L.; Rosenberg, K.E.

2011-01-01

The U.S. Department of Energy (DOE), Office of Nuclear Energy (NE) oversees the efforts to ensure nuclear energy remains a viable option for the United States. A significant portion of these efforts are related to post-irradiation examinations (PIE) of highly activated fuel and materials that are subject to the extreme environment inside a nuclear reactor. As the lead national laboratory, Idaho National Laboratory (INL) has a rich history, experience, workforce and capabilities for performing PIE. However, new advances in tools and techniques for performing PIE now enable understanding the performance of fuels and materials at the nano-scale and smaller level. Examination at this level is critical since this is the scale at which irradiation damage occurs. The INL is on course to adopt these advanced tools and techniques to develop a comprehensive nuclear fuels and materials characterization capability that is unique in the world. Because INL has extensive PIE capabilities currently in place, a strong foundation exist to build upon as new capabilities are implemented and work load increases. In the recent past, INL has adopted significant capability to perform advanced PIE characterization. Looking forward, INL is planning for the addition of two facilities that will be built to meet the stringent demands of advanced tools and techniques for highly activated fuels and materials characterization. Dubbed the Irradiated Materials Characterization Laboratory (IMCL) and Advanced Post Irradiation Examination Capability, these facilities are next generation PIE laboratories designed to perform the work of PIE that cannot be performed in current DOE facilities. In addition to physical capabilities, INL has recently added two significant contributors to the Advanced Test Reactor-National Scientific User Facility (ATR-NSUF), Oak Ridge National Laboratory and University of California, Berkeley.

How does procurement capability maturity affect e-Procurement adoption and leverage purchasing in supply chain

Directory of Open Access Journals (Sweden)

Pongpanga Pongsuwan

2016-11-01

Full Text Available This study refers to the research model of Batenburg (2008 which defined procurement functions to six maturity dimensions; strategy, processes, control, organization, information, e-Technology as the starting point and indicates twenty two items to support capability maturity measurement which is called “Procurement Competitive Capability Maturity”(PCCM. This model is used for a company to assess current practices of procurement function and perceives the level of its capabilities. The data collection is from a survey of fifty-two selected procurement organizations in Southeast Asia (SEA countries; from Thailand, Vietnam, Philippines, Indonesia, Malaysia and Singapore. The objective of this study is to demonstrate the significant value of industry type, size of spending and centralized/decentralized procurement that affect procurement capability maturity. The results show that the industry has no relation to the capability maturity; the size of procurement spend has a positive relation to the capability maturity; and the centralized procurement has higher capability maturity than the decentralized. Moreover, this study extends the knowledge of e-Procurement and digital context to leverage procurement processes and visible procurement integration in an organization and across the supply chain.

USARSKI, Frank. O Budismo e as outras: Encontros e desencontros entre as grandes religiões mundiais. Aparecida: Ideias & Letras, 2009. 304p. ISBN 978-85-7698-053-7

Directory of Open Access Journals (Sweden)

Elisangela Marina de Freitas e Silva

2012-01-01

Full Text Available Resenha do livro USARSKI, Frank. O Budismo e as outras: Encontros e desencontros entre as grandes religiões mundiais. Aparecida: Ideias & Letras, 2009. 304p.ISBN 978-85-7698-053-7

Safety aspects of LWR fuel reprocessing and mixed oxide fuel fabrication plants

International Nuclear Information System (INIS)

Fischer, M.; Leichsenring, C.H.; Herrmann, G.W.; Schueller, W.; Hagenberg, W.; Stoll, W.

1977-01-01

ozon in the cryogenic system to remove krypton 85. Therefore, the off-gas processing and cleanup systems receive particular attention with respect to safety of nuclear fuel cycle facilities. The consequences of credible accidents in mixed oxide fuel fabrication plants, i.e. for instance criticality, explosions, leaks in glove boxes or Pu-nitrate tanks are considered. It is shown that credible accidents can be controlled and release of radioactive contaminants can be minimized by the combination of multiple physical barriers with graduated underpressure, corresponding off-gas systems and process safety systems

Survey of analytical methods for environmental monitoring of krypton-85

International Nuclear Information System (INIS)

Jaquish, R.E.; Moghissi, A.A.

1973-01-01

Numerous methods have been developed for measuring krypton-85 in air as krypton ultimately accumulates in air once it is released into the environment. However, krypton-85 can be present in other media such as natural gas from wells stimulated with nuclear devices or in water when krypton-85 is used for aeration studies. Methods for the measurement of ambient levels of krypton-85 require a concentration of krypton from a large air sample of one m 3 or more. If elevated levels are to be measured, carrier krypton may be used provided the contamination of atmospheric krypton with krypton-85 does not interfere with the measurement. In certain cases, such as in the vicinity of nuclear fuel processing plants, direct measurement techniques may be used. A variety of techniques are employed for krypton-85 counting. At low levels, internal gas counting or organic scintillation is used to measure the beta emission of this radionuclide. At higher levels the gamma emission of krypton-85 may be measured using scintillation or solid state gamma spectroscopic methods. Techniques for collection of the sample, concentration of krypton, and radioactivity measurement of krypton-85 are discussed and various processes are critically evaluated and compared

Fuel Flexible, Low Emission Catalytic Combustor for Opportunity Fuel Applications

Energy Technology Data Exchange (ETDEWEB)

Eteman, Shahrokh

2013-06-30

Limited fuel resources, increasing energy demand and stringent emission regulations are drivers to evaluate process off-gases or process waste streams as fuels for power generation. Often these process waste streams have low energy content and/or highly reactive components. Operability of low energy content fuels in gas turbines leads to issues such as unstable and incomplete combustion. On the other hand, fuels containing higher-order hydrocarbons lead to flashback and auto-ignition issues. Due to above reasons, these fuels cannot be used directly without modifications or efficiency penalties in gas turbine engines. To enable the use of these wide variety of fuels in gas turbine engines a rich catalytic lean burn (RCL®) combustion system was developed and tested in a subscale high pressure (10 atm.) rig. The RCL® injector provided stability and extended turndown to low Btu fuels due to catalytic pre-reaction. Previous work has shown promise with fuels such as blast furnace gas (BFG) with LHV of 85 Btu/ft3 successfully combusted. This program extends on this work by further modifying the combustor to achieve greater catalytic stability enhancement. Fuels containing low energy content such as weak natural gas with a Lower Heating Value (LHV) of 6.5 MJ/m3 (180 Btu/ft3 to natural gas fuels containing higher hydrocarbon (e.g ethane) with LHV of 37.6 MJ/m3 (1010 Btu/ft3) were demonstrated with improved combustion stability; an extended turndown (defined as the difference between catalytic and non-catalytic lean blow out) of greater than 250oF was achieved with CO and NOx emissions lower than 5 ppm corrected to 15% O2. In addition, for highly reactive fuels the catalytic region preferentially pre-reacted the higher order hydrocarbons with no events of flashback or auto-ignition allowing a stable and safe operation with low NOx and CO emissions.

Review of the TREAT Conversion Conceptual Design and Fuel Qualification Plan

Energy Technology Data Exchange (ETDEWEB)

Diamond, David

2017-12-29

The U.S. Department of Energy (DOE) is preparing to re establish the capability to conduct transient testing of nuclear fuels at the Idaho National Laboratory (INL) Transient Reactor Test (TREAT) facility. The original TREAT core went critical in February 1959 and operated for more than 6,000 reactor startups before plant operations were suspended in 1994. DOE is now planning to restart the reactor using the plant's original high-enriched uranium (HEU) fuel. At the same time, the National Nuclear Security Administration (NNSA) Office of Material Management and Minimization Reactor Conversion Program is supporting analyses and fuel fabrication studies that will allow for reactor conversion to low-enriched uranium (LEU) fuel (i.e., fuel with less than 20% by weight 235U content) after plant restart. The TREAT Conversion Program's objectives are to perform the design work necessary to generate an LEU replacement core, to restore the capability to fabricate TREAT fuel element assemblies, and to implement the physical and operational changes required to convert the TREAT facility to use LEU fuel.

A review of ''The potential effects of release of krypton-85''

International Nuclear Information System (INIS)

Saunders, C.P.R.

1993-06-01

A Report into the potential effects of the release of Krypton-85 from the Thermal Oxide Reprocessing Plant (THORP) at Sellafield, was commissioned by British Nuclear Fuels Ltd. The report dealt with the atmospheric impact of the release of Krypton-85 and considered specifically the areas of atmospheric electricity, ionisation, aerosols and conductivity, in terms of the releases of Krypton-85 from THORP. This present review has three objectives: to consider the atmospheric effects of the proposed discharges from THORP, to comment upon the magnitude of the postulated effects from Krypton-85 discharges compared with those from other sources of radioactivity in the atmosphere, and, to comment on the conclusions drawn by the authors of the report. This review was conducted under the aegis of the United Kingdom Inspectorate of Pollution. (author)

Advanced system analysis for indirect methanol fuel cell power plants for transportation applications

International Nuclear Information System (INIS)

Vanderborgh, N.E.; McFarland, R.D.; Huff, J.R.

1990-01-01

The indirect methanol cell fuel concept being actively pursued by the United States Department of Energy and General Motors Corporation is based on electrochemical engine (e.c.e.) an electrical generator capable for usually efficient and clean power production from methanol fuel for the transportation sector. This on-board generator works in consort with batteries to provide electric power to drive propulsion motors for a range of electric vehicles. Success in this technology could do much to improve impacted environmental areas and to convert part of the transportation fleet to natural gas- and coal-derived methanol as the fuel source. These developments parallel work in Europe and Japan where various fuel cell powered vehicles, often fueled with tanked or hydride hydrogen are under active development. This paper describes status of each of these components, and describe a model that predicts the steady state performance of the e.c.e

Interim Report on Fluid-Fuel Thermal Breeder Reactors (Revised)

International Nuclear Information System (INIS)

MacPherson, H. G.; Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W.

1960-01-01

The merits of aqueous-homogeneous ), graphite-moderated molten salt (MSBR) , and graphite-moderated liquid-bismuth (LBBR) breeder reactors operated at nearly comparable fuel-cycle costs (~1.5 mills/kwhr) were evaluated. The net electrical plant capability was assumed to be 1000 MwE, and the fuel and fertile streams were processed continuously on-site. The specific powers based on fuel were 1.2, 1.2, and 0.5 MwE/kg respectively, and 5.9, 3.7, and 5.3 MwE/tonne based on thorium. Net breeding ratios were 1.10, 1.07, and 1.07, giving doubling times of 5-1/2, 11, and 25 full power years . The fuel-cycle costs at the design points selected were 1.4, 1.3, and 1.6 mills/kwhr . The AHBR has an advantage in breeding ratio and doubling time because D 2 O is superior to graphite as a moderator in breeder reactors. MSBR has an advantage in fuel-cycle costs and in inventory of uranium in the fertile stream as a result of using a solution blanket.

An assessment system for the system safety engineering capability maturity model in the case of spent fuel reprocessing

International Nuclear Information System (INIS)

Yang Xiaohua; Liu Zhenghai; Liu Zhiming; Wan Yaping; Bai Xiaofeng

2012-01-01

We can improve the processing, the evaluation of capability and promote the user's trust by using system security engineering capability maturity model (SSE-CMM). SSE-CMM is the common method for organizing and implementing safety engineering, and it is a mature method for system safety engineering. Combining capability maturity model (CMM) with total quality management and statistic theory, SSE-CMM turns systems security engineering into a well-defined, mature, measurable, advanced engineering discipline. Lack of domain knowledge, the size of data, the diversity of evidences, the cumbersomeness of processes, and the complexity of matching evidences with problems are the main issues that SSE-CMM assessment has to face. To improve effectively the efficiency of assessment of spent fuel reprocessing system security engineering capability maturity model (SFR-SSE-CMM), in this paper we de- signed an intelligent assessment software based on domain ontology and that uses methods such as ontology, evidence theory, semantic web, intelligent information retrieval and intelligent auto-matching techniques. This software includes four subsystems, which are domain ontology creation and management system, evidence auto collection system, and a problem and evidence matching system. The architecture of the software is divided into five layers: a data layer, an oncology layer, a knowledge layer, a service layer arid a presentation layer. (authors)

The clean trip - Evaluation of green fuels in pleasure boats; Rena Turen - Utvaerdering av miljoeanpassade braenslen i fritidsbaatar

Energy Technology Data Exchange (ETDEWEB)

Cerne, Olof; Strandberg, Johan; Fridell, Erik; Peterson, Kjell; Allard, Ann-Sofie; Rydberg, Tomas (Swedish Environmental Research Institute Ltd., Stockholm (Sweden)); Vaske, Belinda; Jaegersten, Carl (Chalmers Univ. of Technology, Goeteborg (Sweden)); Oestman, Ninnie (Uppsala Univ., Uppsala (Sweden)); Eklund, Britta (ITM, Stockholm Univ., Stockholm (Sweden))

2008-03-15

This work examines alternative fuels in pleasure boat engines, their effect on engine performance as well as chemical and ecotoxicological characterisation of exhaust emissions to water and air. Three marine diesel engines and one outboard two stroke petrol engine were tested with standard fuels and 'green' fuels, that is for the diesel engine s; GTL (synthetic diesel) and biodiesel (rapeseed methyl ester, RME) and for the outboard engine; alkylate petrol and E85 (ethanol fuel). The outboard engine was converted for the ethanol fuel. GTL generated less particles, hydrocarbons, carbon monoxide and nitrogen oxides than standard diesel. RME generated far less particles and hydrocarbons but slightly more nitrogen oxides. Cooling water from diesel engine s was toxic to zebra fish and crustaeans. GTL and RME generated cooling water that was less toxic to zebra fish compared to standard diesel. One litre of diesel produced 10-20 mg PAH, polyaromatic hydrocarbons, to the cooling water. The traditional two stroke outboard engines are by far the dominating source of emissions from the pleasure crafts. Standard petrol generates high concentrations of harmful pollutants such as benzene, PAHs and formaldehyde. One litre of standard petrol produced 2.3 g PAH in this survey. Alkylate petrol and ethanol fuel, E85, generated far less emissions. The emissions of PAHs from the Swedish pleasure boats annually are 50 tons or more in our estimations. Exhaust from two stroke outboard engines mixed in water is toxic to bacteria, algae and crustaceans. Standard petrol generated the most water toxic to bacteria and crustaceans. Alkylate petrol generated less toxic water to bacteria and crustaceans. For algae there was little difference between the fuels. Despite the fact that most of the fuel in the pleasure crafts are used in open sea, the effects of the emissions can be bigger in lakes and rivers. Traditional two stroke engines are used in lakes that are used for producing

Canadian capabilities in fusion fuels technology and remote handling

International Nuclear Information System (INIS)

1987-10-01

This report describes Canadian expertise in fusion fuels technology and remote handling. The Canadian Fusion Fuels Technology Project (CFFTP) was established and is funded by the Canadian government, the province of Ontario and Ontario Hydro to focus on the technology necessary to produce and manage the tritium and deuterium fuels to be used in fusion power reactors. Its activities are divided amongst three responsibility areas, namely, the development of blanket, first wall, reactor exhaust and fuel processing systems, the development of safe and reliable operating procedures for fusion facilities, and, finally, the application of these developments to specific projects such as tritium laboratories. CFFTP also hopes to utilize and adapt Canadian developments in an international sense, by, for instance, offering training courses to the international tritium community. Tritium management expertise is widely available in Canada because tritium is a byproduct of the routine operation of CANDU reactors. Expertise in remote handling is another byproduct of research and development of of CANDU facilities. In addition to describing the remote handling technology developed in Canada, this report contains a brief description of the Canadian tritium laboratories, storage beds and extraction plants as well as a discussion of tritium monitors and equipment developed in support of the CANDU reactor and fusion programs. Appendix A lists Canadian manufacturers of tritium equipment and Appendix B describes some of the projects performed by CFFTP for offshore clients

A Capabilities Analysis of E-Fulfilment Businesses: transformation in the logistics industry

Directory of Open Access Journals (Sweden)

Janice Burn

2005-11-01

Full Text Available This paper reports on the evaluation of practices of 48 leading e-fulfillment suppliers in the UK. Initial findings suggest that while a comprehensive model of e-fulfilment is validated these organisations are also providing services not previously recognised as e-fulfilment capabilities by the literature. This leads to the development of a staged model of transformation, which implies that the industry will embrace radical change in some sectors and lead to a new definition of e-fulfillment businesses. More in depth investigation leads to a proposed definition, and a methodology to measure the degree of transformation.

Evaluation of Nondestructive Assay/Nondestructive Examination Capabilities for Department of Energy Spent Nuclear Fuel

International Nuclear Information System (INIS)

Luptak, A.J.; Bulmahn, K.D.

1998-01-01

This report summarizes an evaluation of the potential use of nondestructive assay (NDA) and nondestructive examination (NDE) technologies on DOE spent nuclear fuel (SNF). It presents the NDA/NDE information necessary for the National Spent Nuclear Fuel Program (NSNFP) and the SNF storage sites to use when defining that role, if any, of NDA/NDE in characterization and certification processes. Note that the potential role for NDA/NDE includes confirmatory testing on a sampling basis and is not restricted to use as a primary, item-specific, data collection method. The evaluation does not attempt to serve as a basis for selecting systems for development or deployment. Information was collected on 27 systems being developed at eight DOE locations. The systems considered are developed to some degree, but are not ready for deployment on the full range of DOE SNF and still require additional development. The system development may only involve demonstrating performance on additional SNF, packaging the system for deployment, and developing calibration standards, or it may be as extensive as performing additional basic research. Development time is considered to range from one to four years. We conclude that NDA/NDE systems are capable of playing a key role in the characterization and certification of DOE SNF, either as the primary data source or as a confirmatory test. NDA/NDE systems will be able to measure seven of the nine key SNF properties and to derive data for the two key properties not measured directly. The anticipated performance goals of these key properties are considered achievable except for enrichment measurements on fuels near 20% enrichment. NDA/NDE systems can likely be developed to measure the standard canisters now being considered for co-disposal of DOE SNF. This ability would allow the preparation of DOE SNF for storage now and the characterization and certification to be finalize later

Fuels and materials testing capabilities in Fast Flux Test Facility

International Nuclear Information System (INIS)

Baker, R.B.; Chastain, S.A.; Culley, G.E.; Ethridge, J.L.; Lovell, A.J.; Newland, D.J.; Pember, L.A.; Puigh, R.J.; Waltar, A.E.

1989-01-01

The Fast Flux Test Facility (FFTF) reactor, which started operating in 1982, is a 400 MWt sodium-cooled fast neutron reactor located in Hanford, Washington State, and operated by Westinghouse Hanford Co. under contract with U.S. Department of Energy. The reactor has a wide variety of functions for irradiation tests and special tests, and its major purpose is the irradiation of fuel and material for liquid metal reactor, nuclear reactor and space reactor projects. The review first describes major technical specifications and current conditions of the FFTF reactor. Then the plan for irradiation testing is outlined focusing on general features, fuel pin/assembly irradiation tests, and absorber irradiation tests. Assemblies for special tests include the material open test assembly (MOTA), fuel open test assembly (FOTA), closed loop in-reactor assembly (CLIRA), and other special fuel assemblies. An interim examination and maintenance cell (FFTF/IEM cell) and other hot cells are used for nondestructive/destructive tests and physical/mechanical properties test of material after irradiation. (N.K.)

HETEROGENEOUS REBURNING BY MIXED FUELS

Energy Technology Data Exchange (ETDEWEB)

Wei-Yin Chen; Benson B. Gathitu

2005-01-14

Recent studies of heterogeneous reburning, i.e., reburning involving a coal-derived char, have elucidated its variables, kinetics and mechanisms that are valuable to the development of a highly efficient reburning process. Young lignite chars contain catalysts that not only reduce NO, but they also reduce HCN that is an important intermediate that recycles to NO in the burnout zone. Gaseous CO scavenges the surface oxides that are formed during NO reduction, regenerating the active sites on the char surface. Based on this mechanistic information, cost-effective mixed fuels containing these multiple features has been designed and tested in a simulated reburning apparatus. Remarkably high reduction of NO and HCN has been observed and it is anticipated that mixed fuel will remove 85% of NO in a three-stage reburning process.

Research on the combustion, energy and emission parameters of diesel fuel and a biomass-to-liquid (BTL) fuel blend in a compression-ignition engine

International Nuclear Information System (INIS)

Rimkus, Alfredas; Žaglinskis, Justas; Rapalis, Paulius; Skačkauskas, Paulius

2015-01-01

Highlights: • Researched physical–chemical and performance properties of diesel fuel and BTL blend (85/15 V/V). • BTL additive reduced Brake Specific Fuel Consumption, improved engine efficiency. • Simpler BTL molecular chains and lower C/H ratio reduced CO_2 emission and smokiness. • Higher cetane number of BTL reduced heat release in beginning of combustion and NO_x emission. • Advanced start of fuel injection caused reduced fuel consumption and smokiness, increased NO_x emission. - Abstract: This paper presents the comparable research results of the physical–chemical and direct injection (DI) diesel engine properties of diesel fuel and BTL (biomass-to-liquid) blend (85/15 V/V). The energy, ecological and in-cylinder parameters were analysed under medium engine speed and brake torque load regimes; the start of fuel injection was also adjusted. After analysis of the engine bench tests and simulation with AVL BOOST software, it was observed that the BTL additive shortened the fuel ignition delay phase, reduced the heat release in the pre-mixed intensive combustion phase, reduced the nitrogen oxide (NO_x) concentration in the engine exhaust gases and reduced the thermal and mechanical load of the crankshaft mechanism. BTL additive reduced the rates of carbon dioxide (CO_2), incompletely burned hydrocarbons (HC) emission and smokiness due to its chemical composition and combustion features. BTL also reduced Brake Specific Fuel Consumption (BSFC, g/kW h) and improved engine efficiency (η_e); however, the volumetric fuel consumption changed due to the lower density of BTL. The start of fuel injection was adjusted for maximum engine efficiency; concomitantly, reductions in the CO_2 concentration, HC concentration and smokiness were achieved. However, the NO_x and thermo-mechanical engine load increased.

Prediction of air-fuel and oxy-fuel combustion through a generic gas radiation property model

International Nuclear Information System (INIS)

Yin, Chungen

2017-01-01

Highlights: • A gas radiation model for general combustion CFD presented, programmed & verified. • Its general applicability/practical accuracy demonstrated in air-fuel and oxy-fuel. • Useful guidelines for air-fuel and oxy-fuel combustion CFD suggested. • Important to include the impact of CO in gas radiation for oxy-fuel combustion CFD. - Abstract: Thermal radiation plays an important role in heat transfer in combustion furnaces. The weighted-sum-of-gray-gases model (WSGGM), representing a good compromise between computational efficiency and accuracy, is commonly used in computational fluid dynamics (CFD) modeling of combustion processes for evaluating gaseous radiative properties. However, the WSGGMs still have some limitations in practical use, e.g., unable to naturally accommodate different combustion environments, difficult to accurately address the variations in species concentrations in a flame, and inconvenient to account for the impacts of participating species other than H_2O and CO_2. As a result, WSGGMs with different coefficients have been published for specific applications. In this paper, a reliable generic model for gaseous radiation property calculation, which is a computationally efficient exponential wide band model (E-EWBM) applicable to combustion CFD and able to naturally solve all the practical limitations of the WSGGMs, is presented, programmed and verified. The model is then implemented to CFD simulation of a 300 kW air-fuel and a 0.8 MW oxy-fuel combustion furnace, respectively, to demonstrate its computational applicability to general combustion CFD and its capability in producing reliable CFD results for different combustion environments. It is found that the usefulness of the WSGGMs in oxy-fuel combustion CFD is compromised if the important impacts of high levels of CO under oxy-fuel combustion cannot be accounted for. The E-EWBM that appropriately takes the impacts of H_2O, CO_2, CO and CH_4 into account is a good replacement

Biofuels Fuels Technology Pathway Options for Advanced Drop-in Biofuels Production

Energy Technology Data Exchange (ETDEWEB)

Kevin L Kenney

2011-09-01

Advanced drop-in hydrocarbon biofuels require biofuel alternatives for refinery products other than gasoline. Candidate biofuels must have performance characteristics equivalent to conventional petroleum-based fuels. The technology pathways for biofuel alternatives also must be plausible, sustainable (e.g., positive energy balance, environmentally benign, etc.), and demonstrate a reasonable pathway to economic viability and end-user affordability. Viable biofuels technology pathways must address feedstock production and environmental issues through to the fuel or chemical end products. Potential end products include compatible replacement fuel products (e.g., gasoline, diesel, and JP8 and JP5 jet fuel) and other petroleum products or chemicals typically produced from a barrel of crude. Considering the complexity and technology diversity of a complete biofuels supply chain, no single entity or technology provider is capable of addressing in depth all aspects of any given pathway; however, all the necessary expert entities exist. As such, we propose the assembly of a team capable of conducting an in-depth technology pathway options analysis (including sustainability indicators and complete LCA) to identify and define the domestic biofuel pathways for a Green Fleet. This team is not only capable of conducting in-depth analyses on technology pathways, but collectively they are able to trouble shoot and/or engineer solutions that would give industrial technology providers the highest potential for success. Such a team would provide the greatest possible down-side protection for high-risk advanced drop-in biofuels procurement(s).

South Korea's nuclear fuel industry

International Nuclear Information System (INIS)

Clark, R.G.

1990-01-01

March 1990 marked a major milestone for South Korea's nuclear power program, as the country became self-sufficient in nuclear fuel fabrication. The reconversion line (UF 6 to UO 2 ) came into full operation at the Korea Nuclear Fuel Company's fabrication plant, as the last step in South Korea's program, initiated in the mid-1970s, to localize fuel fabrication. Thus, South Korea now has the capability to produce both CANDU and pressurized water reactor (PWR) fuel assemblies. This article covers the nuclear fuel industry in South Korea-how it is structures, its current capabilities, and its outlook for the future

HIGH-TEMPERATURE SAFETY TESTING OF IRRADIATED AGR-1 TRISO FUEL

Energy Technology Data Exchange (ETDEWEB)

Stempien, John D.; Demkowicz, Paul A.; Reber, Edward L.; Chrisensen, Cad L.

2016-11-01

High-Temperature Safety Testing of Irradiated AGR-1 TRISO Fuel John D. Stempien, Paul A. Demkowicz, Edward L. Reber, and Cad L. Christensen Idaho National Laboratory, P.O. Box 1625 Idaho Falls, ID 83415, USA Corresponding Author: john.stempien@inl.gov, +1-208-526-8410 Two new safety tests of irradiated tristructural isotropic (TRISO) coated particle fuel have been completed in the Fuel Accident Condition Simulator (FACS) furnace at the Idaho National Laboratory (INL). In the first test, three fuel compacts from the first Advanced Gas Reactor irradiation experiment (AGR-1) were simultaneously heated in the FACS furnace. Prior to safety testing, each compact was irradiated in the Advanced Test Reactor to a burnup of approximately 15 % fissions per initial metal atom (FIMA), a fast fluence of 3×1025 n/m2 (E > 0.18 MeV), and a time-average volume-average (TAVA) irradiation temperature of about 1020 °C. In order to simulate a core-conduction cool-down event, a temperature-versus-time profile having a peak temperature of 1700 °C was programmed into the FACS furnace controllers. Gaseous fission products (i.e., Kr-85) were carried to the Fission Gas Monitoring System (FGMS) by a helium sweep gas and captured in cold traps featuring online gamma counting. By the end of the test, a total of 3.9% of an average particle’s inventory of Kr-85 was detected in the FGMS traps. Such a low Kr-85 activity indicates that no TRISO failures (failure of all three TRISO layers) occurred during the test. If released from the compacts, condensable fission products (e.g., Ag-110m, Cs-134, Cs-137, Eu-154, Eu-155, and Sr-90) were collected on condensation plates fitted to the end of the cold finger in the FACS furnace. These condensation plates were then analyzed for fission products. In the second test, five loose UCO fuel kernels, obtained from deconsolidated particles from an irradiated AGR-1 compact, were heated in the FACS furnace to a peak temperature of 1600 °C. This test had two

Update and improvement of the global krypton-85 emission inventory.

Science.gov (United States)

Ahlswede, Jochen; Hebel, Simon; Ross, J Ole; Schoetter, Robert; Kalinowski, Martin B

2013-01-01

Krypton-85 is mainly produced in nuclear reactors by fission of uranium and plutonium and released during chopping and dissolution of spent fuel rods in nuclear reprocessing facilities. As noble gas it is suited as a passive tracer for evaluation of atmospheric transport models. Furthermore, research is ongoing to assess its quality as an indicator for clandestine reprocessing activities. This paper continues previous efforts to compile a comprehensive historic emission inventory for krypton-85. Reprocessing facilities are the by far largest emitters of krypton-85. Information on sources and calculations used to derive the annual krypton-85 emission is provided for all known reprocessing facilities in the world. In addition, the emission characteristics of two plants, Tokai (Japan) and La Hague (France), are analysed in detail using emission data with high temporal resolution. Other types of krypton-85 sources are power reactors, naval reactors and isotope production facilities. These sources contribute only little or negligible amounts of krypton-85 compared to the large reprocessing facilities. Taking the decay of krypton-85 into account, the global atmospheric inventory is estimated to about 5500 PBq at the end of 2009. The correctness if the inventory has been proven by meteorological simulations and its error is assumed to be in the range of a few percent. Copyright © 2012 Elsevier Ltd. All rights reserved.

Power ramp rate capabilities of a 5 kW proton exchange membrane fuel cell system with discrete ejector control

Science.gov (United States)

Nikiforow, K.; Pennanen, J.; Ihonen, J.; Uski, S.; Koski, P.

2018-03-01

The power ramp rate capabilities of a 5 kW proton exchange membrane fuel cell (PEMFC) system are studied theoretically and experimentally for grid support service applications. The fuel supply is implemented with a fixed-geometry ejector and a discrete control solution without any anode-side pressure fluctuation suppression methods. We show that the stack power can be ramped up from 2.0 kW to 4.0 kW with adequate fuel supply and low anode pressure fluctuations within only 0.1 s. The air supply is implemented with a centrifugal blower. Air supply ramp rates are studied with a power increase executed within 1 and 0.2 s after the request, the time dictated by grid support service requirements in Finland and the UK. We show that a power ramp-up from 2.0 kW to 3.7 kW is achieved within 1 s with an initial air stoichiometry of 2.5 and within 0.2 s with an initial air stoichiometry of 7.0. We also show that the timing of the power ramp-up affects the achieved ancillary power capacity. This work demonstrates that hydrogen fueled and ejector-based PEMFC systems can provide a significant amount of power in less than 1 s and provide valuable ancillary power capacity for grid support services.

Laboratory sensor design for fiber-optic detection of 85Kr

International Nuclear Information System (INIS)

Geelhood, B.D.; Knopf, M.A.

1994-06-01

The goal of the fiber-optic detection of 85 Kr project is to produce a sensor to detect 85 Kr in real-time from either an airborne or ground-based platform. The 85 Kr gas is a fission product which is released in large quantities during fuel reprocessing and in minor quantities during nuclear reactor operations. Thus an airborne plume of 85 Kr is a radioactive signature of proliferation. Since 85 Kr has a 10.72 year half life, it is difficult for a proliferator to contain the gas for several half lives to avoid releasing the radioactive signature of proliferation. The long half life also results in a plume that can extend several kilometers from the source, which allows initial proliferation monitoring from large distances. The sensor can be used to make stand-alone, real-time measurements of 85 Kr that can be used as direct evidence for proliferation and/or as a screening sensor to determine when to collect air samples for further laboratory analysis. This report provides a summary of the 85 Kr beta sensor design that PNL will use in the laboratory to: (1) demonstrate the measurement technique, (2) establish minimum detection limits, and (3) optimize the sensor design for the final airborne sensor package. The goal of the final airborne sensor package will be to measure 85 Kr at activity levels as low as or as close to ambient background levels as possible with a reasonably sized sensor

Alternative Fuels Data Center: E85 Codes and Standards

Science.gov (United States)

confused with beverage alcohol. Cigarettes and other open ignition sources should never be allowed in Ethanol Incentives and Laws, by State More Ethanol Data | All Maps & Data Case Studies California Ramps Up Biofuels Infrastructure More Ethanol Case Studies | All Case Studies Publications Handbook for

Atomization and spray characteristics of bioethanol and bioethanol blended gasoline fuel injected through a direct injection gasoline injector

International Nuclear Information System (INIS)

Park, Su Han; Kim, Hyung Jun; Suh, Hyun Kyu; Lee, Chang Sik

2009-01-01

The focus of this study was to investigate the spray characteristics and atomization performance of gasoline fuel (G100), bioethanol fuel (E100), and bioethanol blended gasoline fuel (E85) in a direct injection gasoline injector in a gasoline engine. The overall spray and atomization characteristics such as an axial spray tip penetration, spray width, and overall SMD were measured experimentally and predicted by using KIVA-3V code. The development process and the appearance timing of the vortices in the test fuels were very similar. In addition, the numerical results accurately described the experimentally observed spray development pattern and shape, the beginning position of the vortex, and the spray breakup on the spray surface. Moreover, the increased injection pressure induced the occurrence of a clear circular shape in the downstream spray and a uniform mixture between the injected spray droplets and ambient air. The axial spray tip penetrations of the test fuels were similar, while the spray width and spray cone angle of E100 were slightly larger than the other fuels. In terms of atomization performance, the E100 fuel among the tested fuels had the largest droplet size because E100 has a high kinematic viscosity and surface tension.

Fuel-cycle greenhouse gas emissions impacts of alternative transportation fuels and advanced vehicle technologies

International Nuclear Information System (INIS)

Wang, M. Q.

1998-01-01

At an international conference on global warming, held in Kyoto, Japan, in December 1997, the United States committed to reduce its greenhouse gas (GHG) emissions by 7% over its 1990 level by the year 2012. To help achieve that goal, transportation GHG emissions need to be reduced. Using Argonne's fuel-cycle model, I estimated GHG emissions reduction potentials of various near- and long-term transportation technologies. The estimated per-mile GHG emissions results show that alternative transportation fuels and advanced vehicle technologies can help significantly reduce transportation GHG emissions. Of the near-term technologies evaluated in this study, electric vehicles; hybrid electric vehicles; compression-ignition, direct-injection vehicles; and E85 flexible fuel vehicles can reduce fuel-cycle GHG emissions by more than 25%, on the fuel-cycle basis. Electric vehicles powered by electricity generated primarily from nuclear and renewable sources can reduce GHG emissions by 80%. Other alternative fuels, such as compressed natural gas and liquefied petroleum gas, offer limited, but positive, GHG emission reduction benefits. Among the long-term technologies evaluated in this study, conventional spark ignition and compression ignition engines powered by alternative fuels and gasoline- and diesel-powered advanced vehicles can reduce GHG emissions by 10% to 30%. Ethanol dedicated vehicles, electric vehicles, hybrid electric vehicles, and fuel-cell vehicles can reduce GHG emissions by over 40%. Spark ignition engines and fuel-cell vehicles powered by cellulosic ethanol and solar hydrogen (for fuel-cell vehicles only) can reduce GHG emissions by over 80%. In conclusion, both near- and long-term alternative fuels and advanced transportation technologies can play a role in reducing the United States GHG emissions

Fuel-cycle greenhouse gas emissions impacts of alternative transportation fuels and advanced vehicle technologies.

Energy Technology Data Exchange (ETDEWEB)

Wang, M. Q.

1998-12-16

At an international conference on global warming, held in Kyoto, Japan, in December 1997, the United States committed to reduce its greenhouse gas (GHG) emissions by 7% over its 1990 level by the year 2012. To help achieve that goal, transportation GHG emissions need to be reduced. Using Argonne's fuel-cycle model, I estimated GHG emissions reduction potentials of various near- and long-term transportation technologies. The estimated per-mile GHG emissions results show that alternative transportation fuels and advanced vehicle technologies can help significantly reduce transportation GHG emissions. Of the near-term technologies evaluated in this study, electric vehicles; hybrid electric vehicles; compression-ignition, direct-injection vehicles; and E85 flexible fuel vehicles can reduce fuel-cycle GHG emissions by more than 25%, on the fuel-cycle basis. Electric vehicles powered by electricity generated primarily from nuclear and renewable sources can reduce GHG emissions by 80%. Other alternative fuels, such as compressed natural gas and liquefied petroleum gas, offer limited, but positive, GHG emission reduction benefits. Among the long-term technologies evaluated in this study, conventional spark ignition and compression ignition engines powered by alternative fuels and gasoline- and diesel-powered advanced vehicles can reduce GHG emissions by 10% to 30%. Ethanol dedicated vehicles, electric vehicles, hybrid electric vehicles, and fuel-cell vehicles can reduce GHG emissions by over 40%. Spark ignition engines and fuel-cell vehicles powered by cellulosic ethanol and solar hydrogen (for fuel-cell vehicles only) can reduce GHG emissions by over 80%. In conclusion, both near- and long-term alternative fuels and advanced transportation technologies can play a role in reducing the United States GHG emissions.

Safety assessment document for spent fuel handling, packaging, and storage demonstrations at the E-MAD facility on the Nevada Test Site

International Nuclear Information System (INIS)

1985-04-01

The objectives for spent fuel handling and packaging demonstration are to develop the capability to satisfactorily encapsulate typical commercial nuclear reactor spent fuel assemblies and to establish the suitability of interim dry surface and near surface storage concepts. To accomplish these objectives, spent fuel assemblies from a pressurized water reactor have been received, encapsulated in steel canisters, and emplaced in on-site storage facilities and subjected to other tests. As an essential element of these demonstrations, a thorough safety assessment of the demonstration activities conducted at the E-MAD facility has been completed. This document describes the site location and characteristics, the existing E-MAD facility, and the facility modifications and equipment additions made specifically for the demonstrations. The document also summarizes the Quality Assurance Program utilized, and specifies the principal design criteria applicable to the facility modifications, equipment additions, and process operations. Evaluations have been made of the radiological impacts of normal operations, abnormal operations, and postulated accidents. Analyses have been performed to determine the affects on nuclear criticality safety of postulated accidents and credible natural phenomena. The consequences of postulated accidents resulting in fission product gas release have also been estimated. This document identifies the engineered safety features, procedures, and site characteristics that (1) prevent the occurrence of potential accidents or (2) assure that the consequences of postulated accidents are either insignificant or adequately mitigated

Postirradiation examination of Peach Bottom HTGR Driver Fuel Element E06-01

International Nuclear Information System (INIS)

Dyer, F.F.; Wichner, R.P.; Martin, W.J.; Fairchild, L.L.; Kedl, R.J.; de Nordwall, H.J.

1976-04-01

The report presented describes the postirradiation examinations of driver fuel element E06-01, which had been irradiated an equivalent of 384 full-power days in Peach Bottom, Unit 1. The fuel element is described in detail and its temperature and irradiation service history briefly outlined. Results presented include: (1) visual observations; (2) critical dimensions of fuel compacts, sleeve, and spine; (3) axial distributions of gamma-emitting nuclides plus 3 H and 90 Sr; (4) radial distributions of these nuclides in the sleeve and spine at three axial locations in the fueled regions and three locations in the upper reflector; (5) metallographic examination of samples of fuel compact material; and (6) burnup determinations via radiochemical analyses at two compact locations

All-Optical Atom Trap Trace Analysis: Potential Use of 85Kr in Safeguards Activities

International Nuclear Information System (INIS)

Kohler, M.; Sahling, P.; Sieveke, C.; Kirchner, G.

2015-01-01

Sensitive measurement techniques for the detection of anthropogenic tracers demand measurement resolutions down to single atoms, as it has been demonstrated by the first atom trap trace analysis experiments. However, technical limitations had lowered the sample throughput to about 200 per year per machine. We have developed an all-optical apparatus which allows higher sample throughput and small sample sizes at the same time. Krypton-85 as anthropogenic isotope is an ideal tracer for nuclear activities since the only relevant source term is fission. An increased 85Kr concentration in an air sample indicates, that a plume was passing by during sampling. In practice, however, its applicability may be limited by the global and regional background concentrations caused by the emissions of nuclear fuel reprocessing plants. The potential of 85Kr monitoring for safeguards applications has been discussed extensively. Among these is the short range detection of elevated concentrations of 85Kr in the vicinity of reprocessing plants. Our ATTA technique needs sample sizes of about 1 l of air only and thus for the first time will allow simple environmental sampling of 85Kr with high spatial and temporal resolution. The design of such a study including local sampling and tracer transport modelling in proximity to a reprocessing plants is outlined. In addition, such a study could be used also for validating near-field atmospheric dispersion models if the 85Kr source term is known. The potential of environmental analyzes of 85Kr during an IAEA short-notice access is discussed. It is shown that it crucially depends on the emission dynamics after shut-down of fuel dissolution which needs further study. (author)

Methodology and techniques of early detection anomalies 85Kr and 3H in near bottom layer of sea water by water infiltration in spent nuclear fuel in dumpsites of the ship and submarine reactors

International Nuclear Information System (INIS)

Soyfer, V.N.; Goryachev, V.A.; Andreev, D.V.; Barabanov, I.R.; Yanovich, E.A.

2004-01-01

Assessment of the future radioactive environmental contamination threat by releases from the dumped submarine and ship reactors with spent nuclear fuel (SNF) is a project goal. The methodology of search and detection of traces of noble gases ( 85 Kr, 222 Rn) and 3 H (which leaking the first from the SNF) on them plume on a bottom in dumpsites of ship nuclear reactors is advanced. Investigation of releases from the dumped ship reactors with SNF of icebreaker enin in Kara Sea is launched (September 2003). Research has multi-plane character: experiments with SNF, creation of techniques and expeditions. Preliminary observation of current field and hydrological characteristics in zone of marked dumpsites on the shelf has been fulfilled. For an estimation of a gas fission products release (including Kr-85) from the irradiated fuel during the corrosion in conditions a near-bottom layer of the sea in Arctic the special installation has been created in the RRC 'Kurchatov Institute' hot laboratory. Then the following experiment (modeling the conditions a near-bottom layer of the sea in Arctic) was made: First, samples of irradiated VVER-1000 type reactor fuel (UO 2 ) are loaded into capsules filled with pure sea water or sea water with the silt sampled in Kara Sea. The fuel samples have been selected due to similarity of its burnup level (62 MWd/kg) and other parameters to the one of icebreaker 'Lenin' reactor, that had been buried (1965) in Kara sea. The average sample activity was about 1 GBq for 137 Cs. Second, the capsules and the vacuum system are pumped out and checked on tightness by the helium leak tester. Then capsules are filled with the artificial gas mixture without traces of 85 Kr. Temperature of capsules are maintained in a range 0;1 deg C. Each 1-2 month gas samples are taken from the capsules into the previously pumped out flask, then capsules are refilled by the gas mixture. The measurements of 85 Kr concentration in the samples are carried out on low

40 CFR 85.2230 - Steady state test dynamometer-EPA 91.

Science.gov (United States)

2010-07-01

... PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Emission Control System Performance... applicability. The requirements of § 85.2229 apply concurrently for tests conducted under Emission Performance... capable of applying a load to the vehicle's driving tire surfaces at the horsepower and speed levels...

Update and improvement of the global krypton-85 emission inventory

International Nuclear Information System (INIS)

Ahlswede, Jochen; Hebel, Simon; Ross, J. Ole; Schoetter, Robert; Kalinowski, Martin B.

2013-01-01

Krypton-85 is mainly produced in nuclear reactors by fission of uranium and plutonium and released during chopping and dissolution of spent fuel rods in nuclear reprocessing facilities. As noble gas it is suited as a passive tracer for evaluation of atmospheric transport models. Furthermore, research is ongoing to assess its quality as an indicator for clandestine reprocessing activities. This paper continues previous efforts to compile a comprehensive historic emission inventory for krypton-85. Reprocessing facilities are the by far largest emitters of krypton-85. Information on sources and calculations used to derive the annual krypton-85 emission is provided for all known reprocessing facilities in the world. In addition, the emission characteristics of two plants, Tokai (Japan) and La Hague (France), are analysed in detail using emission data with high temporal resolution. Other types of krypton-85 sources are power reactors, naval reactors and isotope production facilities. These sources contribute only little or negligible amounts of krypton-85 compared to the large reprocessing facilities. Taking the decay of krypton-85 into account, the global atmospheric inventory is estimated to about 5500 PBq at the end of 2009. The correctness if the inventory has been proven by meteorological simulations and its error is assumed to be in the range of a few percent. - Highlights: ► Krypton-85 is mainly produced in nuclear reactors and released during reprocessing. ► Krypten-85 can be possibly used as an indicator for clandestine reprocessing. ► This work provides an up-to-date global krypton-85 emission inventory. ► The inventory includes emissions from all possible artificial sources.

A strategic approach to developing e-learning capability for healthcare.

Science.gov (United States)

Clarke, Angie; Lewis, Dina; Cole, Ian; Ringrose, Liz

2005-12-01

This article examines a strategic approach to developing e-learning capability to enhance learning opportunities for the workforce of a healthcare organization. Emphasis is given to the procurement of a bespoke Managed Learning Environment (MLE). Strategic organizational issues impacting on future e-learning developments are considered. The 2-year implementation plan was evaluated through a two phase external research project. The first phase focused on the effectiveness of a training programme designed to build capacity for e-learning within the Northern area and also included a virtual learning environment usability study which informed the MLE specification. The second phase evaluation is ongoing during 2005 and interim findings are presented. The MLE has been piloted and on-line learning packages have been acquired. There has been a phased take-up of e-learning opportunities and e-tutor training. Some virtual Communities of Practice have been established. Key organizational issues have been identified and ongoing findings are informing strategic planning. The healthcare MLE is offering enhanced learning opportunities and assisting area healthcare providers in training their dispersed workforces. Blended learning strategies are most successful. The need for protected time for e-learning is a key issue, financial savings are available. Progress has been slowed by identified organizational constraints-the MLE's benefits are widely recognized.

Fuel manufacturing and utilization

International Nuclear Information System (INIS)

2005-01-01

The efficient utilisation of nuclear fuel requires manufacturing facilities capable of making advanced fuel types, with appropriate quality control. Once made, the use of such fuels requires a proper understanding of their behaviour in the reactor environment, so that safe operation for the design life can be achieved. The International Atomic Energy Agency supports Member States to improve in-pile fuel performance and management of materials; and to develop advanced fuel technologies for ensuring reliability and economic efficiency of the nuclear fuel cycle. It provides assistance to Member States to support fuel-manufacturing capability, including quality assurance techniques, optimization of manufacturing parameters and radiation protection. The IAEA supports the development fuel modelling expertise in Member States, covering both normal operation and postulated and severe accident conditions. It provides information and support for the operation of Nuclear Power Plant to ensure that the environment and water chemistry is appropriate for fuel operation. The IAEA supports fuel failure investigations, including equipment for failed fuel detection and for post-irradiation examination and inspection, as well as fuel repair, it provides information and support research into the basic properties of fuel materials, including UO 2 , MOX and zirconium alloys. It further offers guidance on the relationship with back-end requirement (interim storage, transport, reprocessing, disposal), fuel utilization and management, MOX fuels, alternative fuels and advanced fuel technology

Distribution of equilibrium burnup for an homogeneous core with fuel elements of slightly enriched uranium (0.85% U-235) at Atucha I nuclear power plant

International Nuclear Information System (INIS)

Sidelnik, J.I.; Perez, R.A.; Salom, G.F.

1987-01-01

At Atucha I, the present fuel management with natural uranium comprises three burnup areas and one irradiation path, sometimes performing four steps in the reactor core, according to the requirements. The discharge burnup is 6.0 Mw d/kg U for a waste reactivity of 6.5 m k and a heavy water purity of 99.75%. This is a preliminary study to obtain the distribution of equilibrium burnup of an homogeneous core with slightly enriched uranium (0.85% by weight U-235), using the time-averaged method implemented in the code PUMA and a representative model of one third of core and fixed rod position. It was found a strategy of three areas and two paths that agrees with the present limits of channel power and specific power in fuel rod. The discharge burnup obtained is 11.6 Mw d/kg U. This strategy is calculated with the same method and a full core representation model is used to verify the obtained results. (Author)

Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior

International Nuclear Information System (INIS)

Williamson, R.L.

2011-01-01

Highlights: → The ABAQUS thermomechanics code is enhanced to enable simulation of nuclear fuel behavior. → Comparisons are made between discrete and smeared fuel pellet analysis. → Multidimensional and multipellet analysis is important for accurate prediction of PCMI. → Fully coupled thermomechanics results in very smooth prediction of fuel-clad gap closure. → A smeared-pellet approximation results in significant underprediction of clad radial displacements and plastic strain. - Abstract: A powerful multidimensional fuels performance analysis capability, applicable to both steady and transient fuel behavior, is developed based on enhancements to the commercially available ABAQUS general-purpose thermomechanics code. Enhanced capabilities are described, including: UO 2 temperature and burnup dependent thermal properties, solid and gaseous fission product swelling, fuel densification, fission gas release, cladding thermal and irradiation creep, cladding irradiation growth, gap heat transfer, and gap/plenum gas behavior during irradiation. This new capability is demonstrated using a 2D axisymmetric analysis of the upper section of a simplified multipellet fuel rod, during both steady and transient operation. Comparisons are made between discrete and smeared-pellet simulations. Computational results demonstrate the importance of a multidimensional, multipellet, fully-coupled thermomechanical approach. Interestingly, many of the inherent deficiencies in existing fuel performance codes (e.g., 1D thermomechanics, loose thermomechanical coupling, separate steady and transient analysis, cumbersome pre- and post-processing) are, in fact, ABAQUS strengths.

HANARO fuel irradiation test(II)

Energy Technology Data Exchange (ETDEWEB)

Sohn, D. S.; Kim, H. R.; Chae, H. T.; Lee, B. C.; Lee, C. S.; Kim, B. G.; Lee, C. B.; Hwang, W

2001-04-01

In order to fulfill the requirement to prove HANARO fuel integrity when irradiated at a power greater than 112.8 kW/m, which was imposed during HANARO licensing, and to verify the irradiation performance of HANARO fuel, the in-pile irradiation test of HANARO fuel has been performed. Two types of test fuel, the un-instrumented Type A fuel for higher burnup irradiation in shorter period than the driver fuel and the instrumented Type B fuel for higher linear heat rate and precise measurement of irradiation conditions, have been designed and fabricated. The test fuel assemblies were irradiated in HANARO. The two Type A fuel assemblies were intended to be irradiated to medium and high burnup and have been discharged after 69.9 at% and 85.5 at% peak burnup, respectively. Type B fuel assembly was intended to be irradiatied at high power with different instrumentations and achieved a maximum power higher than 120 kW/m without losing its integrity and without showing any irregular behavior. The Type A fuel assemblies were cooled for about 6 months and transported to the IMEF(Irradiated Material Examination Facility) for consequent evaluation. Detailed non-destructive and destructive PIE (Post-Irradiation Examination), such as the measurement of burnup distribution, fuel swelling, clad corrosion, dimensional changes, fuel rod bending strength, micro-structure, etc., has been performed. The measured results have been analysed/compared with the predicted performance values and the design criteria. It has been verified that HANARO fuel maintains proper in-pile performance and integrity even at the high power of 120 kw/m up to the high burnup of 85 at%.

The eSourcing Capability Model for Service Providers: Knowledge Manage-ment across the Sourcing Life-cycle

OpenAIRE

Laaksonen, Pekka

2011-01-01

Laaksonen, Pekka The eSourcing Capability Model for Service Providers: Knowledge Manage-ment across the Sourcing Life-cycle Jyväskylä: Jyväskylän yliopisto, 2011, 42 s. Tietojärjestelmätiede, kandidaatintutkielma Ohjaaja(t): Käkölä, Timo Tässä kandidaatintutkielmassa selvitettiin sitä, miten the eSourcing Capability Model for Service Providers-mallin käytännöt (practices) ovat liittyneet tietä-myksenhallinnan neljään prosessiin: tiedon luominen, varastointi/noutaminen, jakamine...

Framing car fuel efficiency : linearity heuristic for fuel consumption and fuel-efficiency ratings

NARCIS (Netherlands)

Schouten, T.M.; Bolderdijk, J.W.; Steg, L.

2014-01-01

People are sensitive to the way information on fuel efficiency is conveyed. When the fuel efficiency of cars is framed in terms of fuel per distance (FPD; e.g. l/100 km), instead of distance per units of fuel (DPF; e.g. km/l), people have a more accurate perception of potential fuel savings. People

Structure and evolution of the Afanasy Nikitin seamount, buried hills and 85 degrees E Ridge in the northeastern Indian Ocean

Digital Repository Service at National Institute of Oceanography (India)

Krishna, K.S.

Geophysical data of the Afanasy Nikitin seamount (ANS), partly buried hills and 85 degrees E Ridge in the northeastern Indian Ocean were studied together with published seismic refraction results to understand genesis and evolution of the structures...

Nuclear fuel element

International Nuclear Information System (INIS)

Yamanaka, Tsuneyasu.

1976-01-01

Purpose: To provide a mechanism for the prevention of fuel pellet dislocation in fuel can throughout fuel fablication, fuel transportation and reactor operation. Constitution: A plenum spacer as a mechanism for the prevention of fuel pellet dislocation inserted into a cladding tube comprises split bodies bundled by a frame and an expansion body being capable of inserting into the central cavity of the split bodies. The expansion body is, for example, in a conical shape and the split bodies are formed so that they define in the center portion, when disposed along the inner wall of the cladding tube, a gap capable of inserting the conical body. The plenum spacer is assembled by initially inserting the split bodies in a closed state into the cladding tube after the loading of the pellets, pressing their peripheral portions and then inserting the expansion body into the space to urge the split bodies to the inner surface of the cladding tube. (Kawakami, Y.)

Nuclear Fuel Cycle Evaluation and Screening Findings on Partitioning and Transmutation

International Nuclear Information System (INIS)

Wigeland, R.A.; Taiwo, T.A.; Gehin, J.C.; Jubin, R.; Todosow, M.

2015-01-01

A Nuclear Fuel Cycle Evaluation and Screening (E and S) study has recently been completed in the United States. The study considered the entire fuel cycle, included considerations for both once-through and recycle fuel cycle options, evaluated a set of 40 fuel cycles that allowed a comprehensive assessment of fuel cycle performance, identified a relatively small number of promising fuel cycle options that have the potential for achieving substantial improvements compared to the current nuclear fuel cycle in the United States, and allowed the identification of research and development (R and D) activities needed to support the development of the promising fuel cycle options. Nine high-level criteria (Nuclear Waste Management, Proliferation Risk, Nuclear Material Security Risk, Safety, Environmental Impact, Resource Utilisation, Development and Deployment Risk, Institutional Issues, and Financial Risk and Economics) and associated metrics were used in the study to compare the performance of nuclear fuel cycle options to that of the current fuel cycle practiced in the United States. The study also evaluated a number of fuel cycle characteristics that may have the potential to impact future R and D directions. These included for example: 1) The fuel resources used, i. e., uranium and/or thorium. 2) Impact of extremely high burnup fuels. 3) Minor actinide recycle. 4) The impact of losses during separations (partitioning). 5) Critical versus subcritical (externally-driven) systems for material irradiation. 6) Impact of spectrum of irradiation system, i.e., fast, thermal or intermediate. 7) Waste generation reduction, all of which were quantified in the study. The E and S study has implemented a framework that can be used now and in the future to objectively inform on the potential of alternative nuclear fuel cycles, providing decision-makers and others with perspective on fuel cycle capabilities. (authors)

Description of apparatus for determining radiological source terms of nuclear fuels

International Nuclear Information System (INIS)

Baldwin, D.L.; Woodley, R.E.; Holt, F.E.; Archer, D.V.; Steele, R.T.; Whitkop, P.G.

1985-01-01

New apparatus have been designed, built and are currently being employed to measure the release of volatile fission products from irradiated nuclear fuel. The system is capable of measuring radiological source terms, particularly for cesium-137, cesium-134, iodine-129 and krypton-85, in various atmospheres at temperatures up to 1200 0 C. The design allows a rapid transient heatup from ambient to full temperature, a hold at maximum temperature for a specified period, and rapid cooldown. Released fission products are measured as deposition on a platinum thermal gradient tube or in a filter/charcoal trap. Noble gases pass through to a multi-channel gamma analyzer. 1 ref., 4 figs

Treat upgrade fuel fabrication

International Nuclear Information System (INIS)

Davidson, K.V.; Schell, D.H.

1979-01-01

An extrusion and thermal treatment process was developed to produce graphite fuel rods containing a dispersion of enriched UO 2 . These rods will be used in an upgraded version of the Transient Reactor Test Facility (TREAT). The improved fuel provides a higher graphite matrix density, better fuel dispersion and higher thermal capabilities than the existing fuel

Final summary report of fuel-dynamics tests H2 and E4

International Nuclear Information System (INIS)

Doerner, R.C.; Rothman, A.B.; De Volpi, A.; Dickerman, C.E.; Deitrich, L.W; Stahl, D.; Murphy, W.F.

1976-02-01

Results of two failure experiments using LMFBR-type fuel during simulated unprotected transient overpower accidents are reported and analyzed. In both experiments, a single fresh fuel pin in a Mark-IIA loop was subjected to a temperature-limited, step-reactivity irradiation in the TREAT reactor. Total energy was 490 MJ in Test H2 and 690 MJ in Test E4. Except for their timing, the sequence of events in the failure scenario was the same for both tests. Local coolant boiling began 25-50 msec before failure. Significant upward fuel flow in the center of the pin started as early as 100 msec before cladding failure. Cladding failure was due to melting after contact with molten fuel and occurred at the top of the fuel column. Formation of an outlet flow-channel blockage began about 10 msec after failure and was complete by 50 msec. Inlet blockage began later and was less extensive. No significant amount of fuel sweepout was observed. Fuel remains separated into a small group of 50-1000-μm fragments and a macroscopic group of chunks and clinkers. The final distribution of fuel remains may have resulted from a delayed fuel/steel interaction in the inlet region

Produção e composição do leite de vacas da raça Holandesa alimentadas com fenos de alfafa e de tifton-85 e silagem de milho Milk production and composition of Holstein cows fed with alfafa and tifton-85 hays and corn silage

Directory of Open Access Journals (Sweden)

Clóves Cabreira Jobim

2002-04-01

Full Text Available Estudaram-se os efeitos da ingestão dos fenos de alfafa e tifton-85 e da silagem de milho na produção e composição do leite de vacas da raça Holandesa, multíparas, com peso vivo médio de 460 kg, em início de lactação, num experimento em triplo quadrado latino, simultâneo, com três linhas (vacas e três colunas (volumoso. Não houve efeito (p > 0,05 dos diferentes volumosos na produção e na composição do leite, nem nas porcentagens e produções de gordura, de proteína, de lactose e de sólidos totais. Também a contagem de células somáticas não foi afetada pelos tratamentos. Os resultados da análise econômica mostraram que a silagem de milho proporcionou maior margem líquida por litro de leite/dia produzido.This study was conducted to evaluate the effects of intake of alfalfa and tifton-85 hays and corn silage on the milk production and composition of multiparous Holstein cows, averaging 460 kg in body weight, at the beginning of lactation, using a triple Latin square, simultaneous, with three lines (cows and three columns (forages. There was no effect (p > 0.05 of the different types of forage on the milk production and composition, or on the percentage the production of fat, protein, lactose, total solids, and somatic cell count. The results of the economic analysis showed that the corn silage provided a larger liquid margin for liters of milk produced per day.

Performance evaluation of alternative fuel/engine concepts 1990- 1995. Final report including addendum of diesel vehicles

Energy Technology Data Exchange (ETDEWEB)

Nylund, N.O.; Ikonen, M.; Kytoe, M.; Lappi, M.; Westerholm, M.; Laurikko, J. [VTT Energy, Espoo (Finland). Energy Use

1996-12-31

Annex V within the IEA Agreement on Alternative Motor Fuels is the first subtask to generate new experimental data. The objective of the task is to generate information on the emission potential of alternative fuels in severe operating conditions and to evaluate new emission measurement methods. The work was carried out in three phases, Engine Tests, Vehicle Tests and Addendum of Diesel Vehicles. The work was carried out at VTT (Technical Research Centre of Finland) as a cost shared operation. Participants were Belgium (Parts Two and Three), Canada (Parts One and Two), Finland, Italy (Part One), Japan, the Netherlands Sweden and USA. The United Kingdom also joined at the end of the Annex. The work included 143 different vehicle/fuel/temperature combinations. FTP type emission tests were run on 14 vehicles powered with different gasoline compositions, methanol (M50 and M85), ethanol (E85), LPG, CNG and diesel. Both regulated and unregulated emission components were measured using the most up-to-date emissions measurement technology. The results indicated, that today`s advanced gasoline vehicles must be considered rather clean. Diesel is comparable with gasoline in the case of CO and HC. M85 gives low emissions in warm conditions, but unburned methanol must be controlled. Natural gas and LPG are inherently clean fuels which, using up-to-date engine technology, give low emissions in all conditions. (orig.) (29 refs.)

Krypton-85 enrichment by adsorption-desorption process

International Nuclear Information System (INIS)

Khan, A.A.; Deshingkar, D.S.; Ramarathinam, K.

1975-01-01

The use of activated charcoal columns in conjunction with cryogenic distillation system for concentration of krypton-85 in fuel reprocessing process off-gas stream is reported. Dynamic adsorption of krypton on activated charcoals and its subsequent desorption by applying vacuum were studied. The possible reduction in the quantity of carrier gas to be liquified in the cryogenic system by utilising this process has been discussed on the basis of results of laboratory evaluations. The possibility of elimination of air and oxygen to avoid explosion hazards associated with radiolytic formation and concentration of ozone has also been considered. (author)

Facility Interface Capability Assessment (FICA) project report

International Nuclear Information System (INIS)

Pope, R.B.; MacDonald, R.R.; Viebrock, J.M.; Mote, N.

1995-09-01

The US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified

Facility Interface Capability Assessment (FICA) project report

Energy Technology Data Exchange (ETDEWEB)

Pope, R.B. [ed.] [Oak Ridge National Lab., TN (United States); MacDonald, R.R. [ed.] [Civilian Radioactive Waste Management System, Vienna, VA (United States); Viebrock, J.M.; Mote, N. [Nuclear Assurance Corp., Norcross, GA (United States)

1995-09-01

The US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified.

Fuel handling machine and auxiliary systems for a fuel handling cell

International Nuclear Information System (INIS)

Suikki, M.

2013-10-01

This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

Fuel handling machine and auxiliary systems for a fuel handling cell

Energy Technology Data Exchange (ETDEWEB)

Suikki, M. [Optimik Oy, Turku (Finland)

2013-10-15

This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

Recent enhancements of the INSIGHT integrated in-core fuel management tool

International Nuclear Information System (INIS)

Akio, Yamamoto

2001-01-01

Recent enhancements of the INSIGHT system are described in this paper. The INSIGHT system is an integrated in-core fuel management tool for pressurized water reactors (PWRs) runs on UNIX workstations. The INSIGHT system provides various capabilities which contribute to reduce fuel cycle cost and workload of in-core fuel management tasks, i.e. core follow calculations, interactive loading pattern design, automated multicycle analysis and interface between detailed core calculation codes. To minimize engineers' workload, most of input data for analysis modules are automatically generated by the INSIGHT system through specification of calculation conditions in the graphic user interface. Recent enhancements of the INSIGHT system are mainly focused to improve efficiency of loading pattern optimization and flexibility of multicycle analyses. To increase optimization efficiency, a parallel calculation capability, various optimization theories, extension of heuristic rules, screening by neural networks and so on were incorporated in the loading pattern optimization module. The multicycle analyses module was rewritten to increase flexibility such as cycle dependent specification of loading pattern search methods and so on. The INSIGHT system is currently used by Japanese utilities not only for regular in-core fuel management tasks but also for strategic fuel management studies to reduce fuel cycle cost

Lactose fermentation by engineered Saccharomyces cerevisiae capable of fermenting cellobiose.

Science.gov (United States)

Liu, Jing-Jing; Zhang, Guo-Chang; Oh, Eun Joong; Pathanibul, Panchalee; Turner, Timothy L; Jin, Yong-Su

2016-09-20

Lactose is an inevitable byproduct of the dairy industry. In addition to cheese manufacturing, the growing Greek yogurt industry generates excess acid whey, which contains lactose. Therefore, rapid and efficient conversion of lactose to fuels and chemicals would be useful for recycling the otherwise harmful acid whey. Saccharomyces cerevisiae, a popular metabolic engineering host, cannot natively utilize lactose. However, we discovered that an engineered S. cerevisiae strain (EJ2) capable of fermenting cellobiose can also ferment lactose. This finding suggests that a cellobiose transporter (CDT-1) can transport lactose and a β-glucosidase (GH1-1) can hydrolyze lactose by acting as a β-galactosidase. While the lactose fermentation by the EJ2 strain was much slower than the cellobiose fermentation, a faster lactose-fermenting strain (EJ2e8) was obtained through serial subcultures on lactose. The EJ2e8 strain fermented lactose with a consumption rate of 2.16g/Lh. The improved lactose fermentation by the EJ2e8 strain was due to the increased copy number of cdt-1 and gh1-1 genes. Looking ahead, the EJ2e8 strain could be exploited for the production of other non-ethanol fuels and chemicals from lactose through further metabolic engineering. Copyright © 2016 Elsevier B.V. All rights reserved.

A parametric analysis of future ethanol use in the light-duty transportation sector: Can the US meet its Renewable Fuel Standard goals without an enforcement mechanism?

International Nuclear Information System (INIS)

Westbrook, Jessica; Barter, Garrett E.; Manley, Dawn K.; West, Todd H.

2014-01-01

The modified Renewable Fuel Standard (RFS2) prescribes a volume of biofuels to be used in the United States transportation sector each year through 2022. As the dominant component of the transportation sector, we consider the feasibility of the light-duty vehicle (LDV) parc to provide enough demand for biofuels to satisfy RFS2. Sensitivity studies show that the fuel price differential between gasoline and ethanol blendstocks, such as E85, is the principal factor in LDV biofuel consumption. The numbers of flex fuel vehicles and biofuel refueling stations will grow given a favorable price differential. However, unless the feedstock price differential becomes extreme (biomass prices below $100 per dry ton and oil prices above $215 per barrel), which deviates from historical price trends, LDV parc biofuel consumption will fall short of the RFS2 mandate without an enforcement mechanism. Additionally, such commodity prices might increase biofuel consumption in the short-term, but discourage use of biofuels in the long-term as other technologies that do not rely on any gasoline blendstock may be preferable. Finally, the RFS2 program goals of reducing fossil fuel consumption and transportation greenhouse gas emissions could be achieved through other pathways, such as notable improvements in conventional vehicle efficiency. - Author-Highlights: • At current commodity prices, the LDV fleet will not use enough biofuel to meet RFS2. • RFS2 can be met through the promotion of flex-fuel vehicles and their use of E85 fuel. • The gasoline-E85 price premium is the key factor in encouraging biofuel consumption. • RFS2 is satisfied at extreme oil prices (at least $215/barrel). • This oil price encourages biofuel use in the RFS2 timeframe, but not in the long run

World market of nuclear fuel: new capabilities and difficulties

International Nuclear Information System (INIS)

Maks, A.; Kening, R.

1992-01-01

History of beginning, state and development prospects of the world market of nuclear fuel are considered. In detail is discussed the role of countries, being at the former USSR territory, in the uranium production and its market deliveries

Irradiation performance of U-Pu-Zr metal fuels for liquid-metal-cooled reactors

International Nuclear Information System (INIS)

Tsai, H.; Cohen, A.B.; Billone, M.C.; Neimark, L.A.

1994-10-01

This report discusses a fuel system utilizing metallic U-Pu-Zr alloys which has been developed for advanced liquid metal-cooled reactors (LMRs). Result's from extensive irradiation testing conducted in EBR-II show a design having the following key features can achieve both high reliability and high burnup capability: a cast nominally U-20wt %Pu-10wt %Zr slug with the diameter sized to yield a fuel smear density of ∼75% theoretical density, low-swelling tempered martensitic stainless steel cladding, sodium bond filling the initial fuel/cladding gap, and an as-built plenum/fuel volume ratio of ∼1.5. The robust performance capability of this design stems primarily from the negligible loading on the cladding from either fuel/cladding mechanical interaction or fission-gas pressure during the irradiation. The effects of these individual design parameters, e.g., fuel smear density, zirconium content in fuel, plenum volume, and cladding types, on fuel element performance were investigated in a systematic irradiation experiment in EBR-II. The results show that, at the discharge burnup of ∼11 at. %, variations on zirconium content or plenum volume in the ranges tested have no substantial effects on performance. Fuel smear density, on the other hand, has pronounced but countervailing effects: increased density results in greater cladding strain, but lesser cladding wastage from fuel/cladding chemical interaction

Capabilities of the Power Burst Facility

International Nuclear Information System (INIS)

Spencer, W.A.; Jensen, A.M.; McCardell, R.K.

1982-01-01

The unique and diverse test capabilities of the Power Burst Facility (PBF) are described in this paper. The PBF test reactor, located at the Idaho National Engineering Laboratory, simulates normal, off-normal, and accident operating conditions of light water reactor fuel rods. An overview description is given, with specific detail on design and operating characteristics of the driver core, experiment test loop, fission product detection system, test train assembly facility, and support equipment which make the testing capability of the PBF so versatile

Academic Leaders' Perspectives on Adopting ePortfolios for Developing and Assessing Professional Capabilities in Australian Business Education

Science.gov (United States)

Holt, Dale; McGuigan, Nicholas; Kavanagh, Marie; Leitch, Shona; Ngo, Leanne; Salzman, Scott; Watty, Kim; McKay, Jade

2016-01-01

This paper represents a major stage of data collection and reporting on an Australian Office for Learning and Teaching Innovation and Development grant investigating the adoption of ePortfolios for developing and assessing professional capabilities in Australian undergraduate business education. Assessing desired capabilities with and through…

Gasoline-fueled hybrid vs. conventional vehicle emissions and fuel economy.

Energy Technology Data Exchange (ETDEWEB)

Anderson, J.; Bharathan, D.; He, J.; Plotkin, S.; Santini, D.; Vyas, A.

1999-06-18

This paper addresses the relative fuel economy and emissions behavior, both measured and modeled, of technically comparable, contemporary hybrid and conventional vehicles fueled by gasoline, in terms of different driving cycles. Criteria pollutants (hydrocarbons, carbon monoxide, and nitrogen oxides) are discussed, and the potential emissions benefits of designing hybrids for grid connection are briefly considered. In 1997, Toyota estimated that their grid-independent hybrid vehicle would obtain twice the fuel economy of a comparable conventional vehicle on the Japan 10/15 mode driving cycle. This initial result, as well as the fuel economy level (66 mpg), made its way into the U.S. press. Criteria emissions amounting to one-tenth of Japanese standards were cited, and some have interpreted these results to suggest that the grid-independent hybrid can reduce criteria emissions in the U.S. more sharply than can a conventional gasoline vehicle. This paper shows that the potential of contemporary grid-independent hybrid vehicle technology for reducing emissions and fuel consumption under U.S. driving conditions is less than some have inferred. The importance (and difficulty) of doing test and model assessments with comparable driving cycles, comparable emissions control technology, and comparable performance capabilities is emphasized. Compared with comparable-technology conventional vehicles, grid-independent hybrids appear to have no clear criteria pollutant benefits (or disbenefits). (Such benefits are clearly possible with grid-connectable hybrids operating in zero emissions mode.) However, significant reductions in greenhouse gas emissions (i.e., fuel consumption) are possible with hybrid vehicles when they are used to best advantage.

Externalities of fuel cycles 'ExternE' project. Summary report

International Nuclear Information System (INIS)

Holland, M.; Berry, J.

1994-01-01

There is a growing requirement for policy analysts to take account of the environment in their decision making and to undertake the specified cost-benefit analysis. Within the European Union this is reflected in the 5th Environmental Action Programme, and the Commission's White Paper entitled 'Growth, competitiveness, employment and the ways forward to the 21st century'. This has led to a need for evaluation of environmental externalities. The ExternE Project commenced in 1991 as the European part of a collaborative study between the European Commission and the US Department of Energy. It aims to be the first systematic approach to the evaluation of external costs of a wide range of different fuel cycles. The project will result in an operational accounting framework for the quantification and monetarisation of priority environmental and other externalities. This framework will allow the calculation of the marginal external costs and benefits for specific power plants, at specific sites using specified technologies. There are three major phases in the project. Phase I was undertaken in collaboration with the US Department of Energy. In this phase the teams jointly developed the conceptual approach and methodology and shared scientific information for application to a number of fuel cycles. On the European side work concentrated on the nuclear and coal fuel cycles which together were expected to raise many of the fundamental issues in fuel cycle analysis. The project is currently nearing completion of Phase 2. During this phase the methodology has been applied to a wide range of different fossil, nuclear and renewable fuel cycles for power generation and energy conservation options. Also a series of National Implementation Programmes are underway in which the methodology and accounting framework are being applied to reference sites throughout Europe. In addition the general methodology is being extended to address the evaluation of externalities associated with

Logistic Fuel Processor Development

National Research Council Canada - National Science Library

Salavani, Reza

2004-01-01

... to light gases then steam reform the light gases into hydrogen rich stream. This report documents the efforts in developing a fuel processor capable of providing hydrogen to a 3kW fuel cell stack...

Establishing release limits for 3H, 14C, 85Kr, and 129I

International Nuclear Information System (INIS)

Kocher, D.C.; Killough, G.G.

1983-01-01

Tritium ( 3 H), 14 C, 85 Kr, and 129 I are the most important globally dispersed radionuclides released from the nuclear fuel cycle. In this paper, we investigate whether global transport of these radionuclides could also be important in assessing doses to individuals in critical groups of the population

Reduction of CO2 emissions by influencing fuel prices

International Nuclear Information System (INIS)

Keller, M.; Zbinden, R.; Haan, P.; Gruetter, J.; Ott, W.

2002-01-01

viable option. If, however, the more sensible - as far as ecological issues and CO 2 are concerned - use of biogas is not to be hindered, biogas' handicap must be taken into account when promotional measures are planned (e.g. graduated tax-exemption, delivery agreements). For bio-fuels, the addition of ethanol to petrol (E10: 10% added) seems to be a viable option with significant CO 2 emission reduction potential at comparatively low costs, but not the addition of 85% (E85) because of vehicle modification costs and costs for the additional infrastructure, or the promotion of RME (Rapeseed-Methyl-Ester) because of very high CO 2 emission avoidance costs and negative local environmental effects

Comparative Analysis of Structural Changes In U-Mo Dispersed Fuel of Full-Size Fuel Elements And Mini-Rods Irradiated In The MIR Reactor

Energy Technology Data Exchange (ETDEWEB)

Izhutov, Aleksey L.; Iakovlev, Valeriy V.; Novoselov, Andrey E. and others

2013-12-15

The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel that was irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods and mini-rods with atomized powder dispersed in Al matrix as well as with additions of 2%, 5% and 13% of silicon in the matrix and ZrN protective coating on the fuel particles. The full-size fuel rods were irradiated up to an average burnup of ∼ 60%{sup 235}U; the mini-rods were irradiated to an average burnup of ∼ 85%{sup 235}U. The presented data show a significant increase of the void fraction in the U-Mo alloy as the U-235 burnup rises from ∼ 40% up to ∼ 85%. The effect of irradiation test conditions and U-235 burnup were analyzed with regard to the formation of an interaction layer between the matrix and fuel particles as well as generation of porosity in the U-Mo alloy. Shown here are changes in distribution of U fission products as the U-235 burnup increases from ∼ 40% up to ∼ 85%.

Comparative Analysis of Structural Changes In U-Mo Dispersed Fuel of Full-Size Fuel Elements And Mini-Rods Irradiated In The MIR Reactor

International Nuclear Information System (INIS)

Izhutov, Aleksey L.; Iakovlev, Valeriy V.; Novoselov, Andrey E. and others

2013-01-01

The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel that was irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods and mini-rods with atomized powder dispersed in Al matrix as well as with additions of 2%, 5% and 13% of silicon in the matrix and ZrN protective coating on the fuel particles. The full-size fuel rods were irradiated up to an average burnup of ∼ 60% 235 U; the mini-rods were irradiated to an average burnup of ∼ 85% 235 U. The presented data show a significant increase of the void fraction in the U-Mo alloy as the U-235 burnup rises from ∼ 40% up to ∼ 85%. The effect of irradiation test conditions and U-235 burnup were analyzed with regard to the formation of an interaction layer between the matrix and fuel particles as well as generation of porosity in the U-Mo alloy. Shown here are changes in distribution of U fission products as the U-235 burnup increases from ∼ 40% up to ∼ 85%

Approaches in estimation of external cost for fuel cycles in the ExternE project

International Nuclear Information System (INIS)

Afanas'ev, A.A.; Maksimenko, B.N.

1998-01-01

The purposes, content and main results of studies realized within the frameworks of the International Project ExternE which is the first comprehensive attempt to develop general approach to estimation of external cost for different fuel cycles based on utilization of nuclear and fossil fuels, as well as on renewable power sources are discussed. The external cost of a fuel cycle is treated as social and environmental expenditures which are not taken into account by energy producers and consumers, i.e. these are expenditures not included into commercial cost nowadays. The conclusion on applicability of the approach suggested for estimation of population health hazards and environmental impacts connected with electric power generation growth (expressed in money or some other form) is made

Consumo, digestibilidade e parâmetros ruminais em bovinos de corte alimentados com dietas contendo silagem de sorgo e pré-secado de capim-tifton 85 Intake, digestibility and ruminal parameters in beef cattle fed diets with sorghum silage and tifton 85 haylage

Directory of Open Access Journals (Sweden)

Odilon Gomes Pereira

2007-12-01

Full Text Available Avaliaram-se o consumo e as digestibilidades total e parcial dos nutrientes, a eficiência microbiana, o balanço de nitrogênio, a taxa de passagem da digesta ruminal, o pH e a concentração de amônia ruminal em bovinos de corte alimentados com dietas contendo como fonte de volumoso pré-secado de capim-tifton 85 e silagem de sorgo nas seguintes proporções: 100:0; 68:32; 34:66 e 0:100, respectivamente, com base na MS. Foram utilizados quatro animais mestiços Holandês × Zebu (H × Z, fistulados no rúmen e abomaso, com peso médio de 364 kg, distribuídos em um quadrado latino 4 × 4. A relação volumoso:concentrado foi de 60:40, na base da MS. Os consumos de MS, MO, PB, carboidratos totais (CT, assim como as digestibilidades totais da PB, EE, CNF e FDN não foram influenciados pelas dietas, registrando-se valores médios de 6,01; 5,69; 0,76 e 4,64 kg/dia e 67,94; 82,42; 84,43 e 53,57%, respectivamente. Os consumos de EE, CNF, FDN e NDT e as digestibilidades aparentes totais da MS, MO e CT aumentaram linearmente com o incremento da proporção de silagem de sorgo no volumoso. As digestibilidades ruminais e intestinais de MS, CT, CNF e FDN não foram influenciadas pelas dietas. O pH não foi alterado pelos tempos de coleta nem pelas dietas. A concentração de amônia foi influenciada pelos tempos de coleta, estimando-se valor máximo de 13,14 mg/100 mL, às 2,90 horas após a alimentação. Para as dietas contendo 0; 32; 66 e 100% de silagem de sorgo no volumoso estimaram-se taxas de passagem da digesta ruminal da ordem de 4,10: 4,22; 4,27 e 5,30%/hora, respectivamente. A eficiência microbiana não foi afetada pelo nível de silagem de sorgo na dieta. O uso de silagem pré-secada de capim tifton 85 associada à silagem de sorgo mostrou-se uma boa alternativa de volumoso para bovinos de corte.The intake and the total and partial digestibility of nutrients, the microbial efficiency, the nitrogen balance, the passage rates of ruminal

Reliability and availability requirements analysis for DEMO: fuel cycle system

International Nuclear Information System (INIS)

Pinna, T.; Borgognoni, F.

2015-01-01

The Demonstration Power Plant (DEMO) will be a fusion reactor prototype designed to demonstrate the capability to produce electrical power in a commercially acceptable way. Two of the key elements of the engineering development of the DEMO reactor are the definitions of reliability and availability requirements (or targets). The availability target for a hypothesized Fuel Cycle has been analysed as a test case. The analysis has been done on the basis of the experience gained in operating existing tokamak fusion reactors and developing the ITER design. Plant Breakdown Structure (PBS) and Functional Breakdown Structure (FBS) related to the DEMO Fuel Cycle and correlations between PBS and FBS have been identified. At first, a set of availability targets has been allocated to the various systems on the basis of their operating, protection and safety functions. 75% and 85% of availability has been allocated to the operating functions of fuelling system and tritium plant respectively. 99% of availability has been allocated to the overall systems in executing their safety functions. The chances of the systems to achieve the allocated targets have then been investigated through a Failure Mode and Effect Analysis and Reliability Block Diagram analysis. The following results have been obtained: 1) the target of 75% for the operations of the fuelling system looks reasonable, while the target of 85% for the operations of the whole tritium plant should be reduced to 80%, even though all the tritium plant systems can individually reach quite high availability targets, over 90% - 95%; 2) all the DEMO Fuel Cycle systems can reach the target of 99% in accomplishing their safety functions. (authors)

LEU fuel fabrication in Argentina

International Nuclear Information System (INIS)

Giorsetti, D.R.; Gomez, J.O.; Marajofsky, A.; Kohut, C.

1985-01-01

As an Institution, aiming to meet with its own needs, CNEA has been intensively developing reduced enriched fuel to use in its own research and test reactors. Development of the fabrication technology as well as the design, installation and operation of the manufacturing plant, have been carried out with its own funds. Irradiation and post-irradiation of test miniplates have been taking place within the framework of the RERTR program. During the last years, CNEA has developed three LEU fuel types. In the previous RERTR meetings, we presented the technological results obtained with these fuel types. This paper focuses on CNEA LEU fuel element manufacturing status and the trained personnel we can offer in design and manufacture fuel capability. CNEA has its own fuel manufacturing technology; the necessary facilities to start the fuel fabrication; qualified technicians and professionals for: fuel design and behaviour analysis; fuel manufacturing and QA; international recognition of its fuel development and manufacturing capability through its ORR miniplate irradiation; its own natural uranium and the future possibility to enrich up to 20% U 235 ; the probability to offer a competitive fuel manufacturing cost in the international market; the disposition to cooperate with all countries that wish to take part and aim to reach an self-sufficiency in their own fuel supply needs

Development of Green Fuels From Algae - The University of Tulsa

Energy Technology Data Exchange (ETDEWEB)

Crunkleton, Daniel; Price, Geoffrey; Johannes, Tyler; Cremaschi, Selen

2012-12-03

The general public has become increasingly aware of the pitfalls encountered with the continued reliance on fossil fuels in the industrialized world. In response, the scientific community is in the process of developing non-fossil fuel technologies that can supply adequate energy while also being environmentally friendly. In this project, we concentrate on green fuels which we define as those capable of being produced from renewable and sustainable resources in a way that is compatible with the current transportation fuel infrastructure. One route to green fuels that has received relatively little attention begins with algae as a feedstock. Algae are a diverse group of aquatic, photosynthetic organisms, generally categorized as either macroalgae (i.e. seaweed) or microalgae. Microalgae constitute a spectacularly diverse group of prokaryotic and eukaryotic unicellular organisms and account for approximately 50% of global organic carbon fixation. The PI's have subdivided the proposed research program into three main research areas, all of which are essential to the development of commercially viable algae fuels compatible with current energy infrastructure. In the fuel development focus, catalytic cracking reactions of algae oils is optimized. In the species development project, genetic engineering is used to create microalgae strains that are capable of high-level hydrocarbon production. For the modeling effort, the construction of multi-scaled models of algae production was prioritized, including integrating small-scale hydrodynamic models of algae production and reactor design and large-scale design optimization models.

Steam reforming of fuel to hydrogen in fuel cells

Science.gov (United States)

Fraioli, Anthony V.; Young, John E.

1984-01-01

A fuel cell capable of utilizing a hydrocarbon such as methane as fuel and having an internal dual catalyst system within the anode zone, the dual catalyst system including an anode catalyst supporting and in heat conducting relationship with a reforming catalyst with heat for the reforming reaction being supplied by the reaction at the anode catalyst.

Studies of Modified Hydrogen Storage Intermetallic Compounds Used as Fuel Cell Anodes

Directory of Open Access Journals (Sweden)

Rui F. M. Lobo

2011-12-01

Full Text Available The possibility of substituting Pt/C with the hydrogen storage alloy MlNi3.6Co0.85Al0.3Mn0.3 as the anode active material of a proton exchange membrane fuel cell system has been analyzed. The electrochemical properties indicate that a much more electrochemically active anode is obtained by impregnating the active material loaded anode in a Nafion proton conducting polymer. Such performance improvement might result from the increase of three-phase boundary sites or length in the gas diffusion electrode where the electrochemical reaction occurs. The experimental data revealed that the membrane electrode assembly (MEA shows better results when the anode active material, MlNi3.6Co0.85Al0.3Mn0.3, is treated with a hot alkaline KBH4 solution, and then chemically coated with 3 wt.% Pd. The MEA with the aforesaid modification presents an enhanced surface capability for hydrogen adsorption, and has been studied by molecular beam-thermal desorption spectrometry.

Fuel processing

International Nuclear Information System (INIS)

Allardice, R.H.

1990-01-01

The technical and economic viability of the fast breeder reactor as an electricity generating system depends not only upon the reactor performance but also on a capability to recycle plutonium efficiently, reliably and economically through the reactor and fuel cycle facilities. Thus the fuel cycle is an integral and essential part of the system. Fuel cycle research and development has focused on demonstrating that the challenging technical requirements of processing plutonium fuel could be met and that the sometimes conflicting requirements of the fuel developer, fuel fabricator and fuel reprocessor could be reconciled. Pilot plant operation and development and design studies have established both the technical and economic feasibility of the fuel cycle but scope for further improvement exists through process intensification and flowsheet optimization. These objectives and the increasing processing demands made by the continuing improvement to fuel design and irradiation performance provide an incentive for continuing fuel cycle development work. (author)

Modelling of phenomena associated with high burnup fuel behaviour during overpower transients

International Nuclear Information System (INIS)

Sills, H.E.; Langman, V.J.; Iglesias, F.C.

1995-01-01

Phenomena of importance to the behaviour of high burnup fuel subjected to conditions of rapid overpower (i.e., LWR RIAs) include the change in cladding material properties due to irradiation, pellet-clad interaction (PCI) and 'rim' effects associated with the periphery of high burnup fuel. 'Rim' effects are postulated to be caused by changes in fuel morphology at high burnup. Typical discharge burnups for CANDU fuel are low compared to LWRs. Maximum linear ratings for CANDU fuel are higher than those for LWRs. However, under normal operating conditions, the Zircaloy-4 clad of the CANDU fuel is collapsed onto the fuel stack. Thus, the CANDU fuel performance codes model the transient behaviour of the fuel-to-clad interface and are capable of assessing the potential for pellet-clad mechanical interaction (PCMI) failures for a wide range of overpower conditions. This report provides a discussion of the modelling of the phenomena of importance to high burnup fuel behaviour during rapid overpower transients. (author)

Core fueling to produce peaked density profiles in large tokamaks

International Nuclear Information System (INIS)

Mikkelsen, D.R.; McGuire, K.M.; Schmidt, G.L.; Zweben, S.J.

1994-06-01

Peaking the density profile increases the usable bootstrap current and the average fusion power density; this could reduce the current drive power and increase the net output of power producing tokamaks. The use of neutral beams and pellet injection to produce peaked density profiles is assessed. We show that with radially ''hollow'' diffusivity profiles (and no particle pinch) moderately peaked density profiles can be produced by particle source profiles which are peaked off-axis. The fueling penetration requirements can therefore be relaxed and this greatly improves the feasibility of generating peaked density profiles in large tokamaks. In particular, neutral beam fueling does not require MeV particle energy. Even with beam voltages of ∼200 keV, however, exceptionally good particle confinement, τ p much-gt τ E is required to achieve net electrical power generation. In system with no power production requirement (e.g., neutron sources) neutral beam fueling should be capable of producing peaked density profiles in devices as large as ITER. Fueling systems with low energy cost per particle (such as cryogenic pellet injection) must be used in power producing tokamaks when τ p ∼ τ E . Simulations with pellet injection speeds of 7 km/sec show the peaking factor, n eo /left-angle n e right-angle, approaching 2

Simulation of atmospheric krypton-85 transport to assess the detectability of clandestine nuclear reprocessing

Energy Technology Data Exchange (ETDEWEB)

Ross, Jens Ole

2010-02-02

The radioactive noble gas krypton-85 is released into the atmosphere during reprocessing of spent nuclear fuel or irradiated breeding targets. This is a necessary step for plutonium separation. Therefore the {sup 85}Kr signature of reprocessing could possibly be used for the detection of undeclared nuclear facilities producing nuclear weaponusable material. The {sup 85}Kr content of the atmosphere has grown over the last decades as the emissions from military and civilian nuclear industry could not be compensated by the decay with a half-life of 10.76 years. In this study, the global {sup 85}Kr background distribution due to emissions of known reprocessing facilities for the period from 1971 until 2006 was simulated using the atmospheric general circulation model ECHAM5 applying the newest available annual emission data. The convective tracer transport scheme and the operator splitting for the physical calculations in the model were modified in order to guarantee physically correct results for tracer point sources, in particular non negative concentrations. An on-line routine controlling the {sup 85}Kr -budget in the model enforced exact mass conservation. The results of the simulation were evaluated by extensive comparison with measurements performed by the German Federal Office for Radiation Protection with very good agreement at most observation sites except those in the direct vicinity of {sup 85}Kr sources. Of particular interest for the {sup 85}Kr detection potential was the variability of {sup 85}Kr background concentrations which was evaluated for the first time in a global model. In addition, the interhemispheric transport as simulated by ECHAM5 was analyzed using a two-box model providing a mean exchange time of τ {sub ex} = 10.5 months. The analysis of τ{sub ex} over simulated 35 years indicates that in years with strong South Asian or African Monsoon the interhemispheric transport is faster during the monsoon season. A correlation analysis of

HANARO fuel irradiation test (II): revision

Energy Technology Data Exchange (ETDEWEB)

Sohn, D. S.; Kim, H.; Chae, H. T.; Lee, C. S.; Kim, B. G.; Lee, C. B

2001-04-01

In order to fulfill the requirement to prove HANARO fuel integrity when irradiated at a power greater than 112.8 kW/m, which was imposed during HANARO licensing, and to verify the irradiation performance of HANARO fuel, the in-pile irradiation test of HANARO fuel has been performed. Two types of test fuel, the un-instrumented Type A fuel for higher burnup irradiation in shorter period than the driver fuel and the instrumented Type B fuel for higher linear heat rate and precise measurement of irradiation conditions, have been designed and fabricated. The test fuel assemblies were irradiated in HANARO. The two Type A fuel assemblies were intended to be irradiated to medium and high burnup and have been discharged after 69.9 at% and 85.5 at% peak burnup, respectively. Type B fuel assembly was intended to be irradiated at high power with different instrumentations and achieved a maximum power higher than 120 kW/m without losing its integrity and without showing any irregular behavior. The Type A fuel assemblies were cooled for about 6 months and transported to the IMEF(Irradiated Material Examination Facility) for consequent evaluation. Detailed non-destructive and destructive PIE (Post-Irradiation Examination), such as the measurement of burnup distribution, fuel swelling, clad corrosion, dimensional changes, fuel rod bending strength, micro-structure, etc., has been performed. The measured results have been analysed/compared with the predicted performance values and the design criteria. It has been verified that HANARO fuel maintains proper in-pile performance and integrity even at the high power of 120 kw/m up to the high burnup of 85 at%. This report is the revision of KAERI/TR-1816/2001 on the irradiation test for HANARO fuel.

Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications

International Nuclear Information System (INIS)

Choi, J; Ebbinghaus, B; Meiers, T; Ahn, J

2006-01-01

The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle technologies that are cleaner, more efficient, less waste-intensive, and more proliferation resistant. The need for advanced fuel development is emphasized in on-going DOE-supported programs, e.g., Global Nuclear Energy Initiative (GNEI), Advanced Fuel Cycle Initiative (AFCI), and GEN-IV Technology Development. The Directorates of Energy and Environment (E and E) and Chemistry and Material Sciences (C and MS) at Lawrence Livermore National Laboratory (LLNL) are interested in advanced fuel research and manufacturing using its multi-disciplinary capability and facilities to support a design concept of a small, secure, transportable, and autonomous reactor (SSTAR). The E and E and C and MS Directorates co-sponsored this Laboratory Directed Research and Development (LDRD) Project on Mono-Uranium Nitride Fuel Development for SSTAR and Space Applications. In fact, three out of the six GEN-IV reactor concepts consider using the nitride-based fuel, as shown in Table 1. SSTAR is a liquid-metal cooled, fast reactor. It uses nitride fuel in a sealed reactor vessel that could be shipped to the user and returned to the supplier having never been opened in its long operating lifetime. This sealed reactor concept envisions no fuel refueling nor on-site storage of spent fuel, and as a result, can greatly enhance proliferation resistance. However, the requirement for a sealed, long-life core imposes great challenges to research and development of the nitride fuel and its cladding. Cladding is an important interface between the fuel and coolant and a barrier to prevent fission gas release during normal and accidental conditions. In fabricating the nitride fuel rods and assemblies, the cladding material should be selected based on its the coolant-side corrosion properties, the chemical/physical interaction with the nitride fuel, as well as their thermal and neutronic properties. The US

Fuel assembly

International Nuclear Information System (INIS)

Gjertsen, R.K.; Bassler, E.A.; Huckestein, E.A.; Salton, R.B.; Tower, S.N.

1988-01-01

A fuel assembly adapted for use with a pressurized water nuclear reactor having capabilities for fluid moderator spectral shift control is described comprising: parallel arranged elongated nuclear fuel elements; means for providing for axial support of the fuel elements and for arranging the fuel elements in a spaced array; thimbles interspersed among the fuel elements adapted for insertion of a rod control cluster therewithin; means for structurally joining the fuel elements and the guide thimbles; fluid moderator control means for providing a volume of low neutron absorbing fluid within the fuel assembly and for removing a substantially equivalent volume of reactor coolant water therefrom, a first flow manifold at one end of the fuel assembly sealingly connected to a first end of the moderator control tubes whereby the first ends are commonly flow connected; and a second flow manifold, having an inlet passage and an outlet passage therein, sealingly connected to a second end of the moderator control tubes at a second end of the fuel assembly

Comparative calculations and operation-to-PIE data juxtaposition of the Zaporozhye NPP, WWER-1000 FA-E0325 fuel rods after 4 years of operation up to ∼49 MWd/kgU burnup

International Nuclear Information System (INIS)

Passage, G.; Stefanova, S.; Scheglov, A.; Proselkov, V.

2006-01-01

Operational and PIE data for the Zaporozhe NPP, FA-E0325, WWER-1000 fuel rods were provided in the OECD NEA IFPE Database and were used to perform comparative calculations among several fuel performance codes. The fuel rods had been irradiated for 4 years of operation up to ∼49 MWd/kg U burnup. The fuel rod operation histories are developed for the PINw99, TRANSURANUS (V1M1J03) and TOPRA-2 codes. The initial state fuel rod parameters are analysed and calculations are carried out. The PIE data enable the comparison of experimental measurement with code-calculated values for cladding elongation (49 rods), FGR and gas pressure (35 rods). Cladding diameter creep-down and gap closure results are juxtaposed as well. The capability of the applied codes correctly to predict the WWER fuel rod performance is shown. The WWER-1000 fuel rod data include initial geometrical and design parameters of the fuel rods, as well as description of the operation regime, NPP unit loading history and PIE results at normal conditions. The data are sufficient for modelling all 312 fuel rod and for comparison of calculations with experimental results for a limited number of fuel rods. The comparison between the calculated and measured results discussed in this paper shows that the codes PINw99, TRANSURANUS and TOPRA-2, are capable of adequate predicting the thermophysical and the mechanical performance of the WWER-1000 fuel rods. The PINw99 code predicts conservative BOL FGR values and conservative gas pressure values in the region of burnups higher than 30 MWd/kg U, which can be explained by the underprediction of the cladding gas inner volume and cladding elongation. The improved version PIN2K (not applied in the present study) predicts much better FGR and gas pressure, though, it is still under development in the high burnup FGR modelling part. In the TRANSURANUS code, there are also areas, where refinements are clearly indicated. They are subjects of the ongoing research projects and

Advanced concepts under development in the United States Breeder-Fuel-Reprocessing Program

International Nuclear Information System (INIS)

Burch, W.D.

1981-01-01

Advanced concepts and techniques for the fuel reprocessing step are being developed. These concepts have been incorporated into the conceptual design of a Hot Experimental Facility (HEF), which is intended to demonstrate reprocessing of the first US breeder demonstration reactor. To achieve system reliability and reduce occupational doses, a concept of totally remote operation and maintenance (termed Remotex) has been conceived and is being developed. In this concept, maintenance and mechanical operations are accomplished with remotely operated bilateral force-reflecting electronic master/slave manipulators. Suitable transport systems, coupled with remote closed-circuit television viewing, are provided to extend man's capabilities into the hostile cell environment. New equipment concepts are being developed for the fuel dismantling and shearing step, a high-temperature dry process termed voloxidation to remove tritium, a continuous rotary dissolver, and for an improved centrifugal solvent contractor. Techniques have been developed, using engineering-scale equipment with active tracers for retention of 85 Kr, radioiodine, 14 C, and 3 H

Small-scale irradiated fuel electrorefining

International Nuclear Information System (INIS)

Benedict, R.W.; Krsul, J.R.; Mariani, R.D.; Park, K.; Teske, G.M.

1993-01-01

In support of the metallic fuel cycle development for the Integral Fast Reactor (IFR), a small scale electrorefiner was built and operated in the Hot Fuel Examination Facility (HFEF) at Argonne National Laboratory-West. The initial purpose of this apparatus was to test the single segment dissolution of irradiated metallic fuel via either direct dissolution in cadmium or anodic dissolution. These tests showed that 99.95% of the uranium and 99.99% of the plutonium was dissolved and separated from the fuel cladding material. The fate of various fission products was also measured. After the dissolution experiments, the apparatus was upgraded to stady fission product behavior during uranium electrotransport. Preliminary decontamination factors were estimated for different fission products under different processing conditions. Later modifications have added the following capabilities: Dissolution of multiple fuel segments simultaneously, electrotransport to a solid cathode or liquid cathode and actinide recovery with a chemical reduction crucible. These capabilities have been tested with unirradiated uranium-zirconium fuel and will support the Fuel Cycle Demonstration program

Commercializing fuel cells: managing risks

Science.gov (United States)

Bos, Peter B.

separation of functions between stack convention and fuel processing, i.e. external reforming using low-cost, non-catalytic under-oxidized burners. Even for fuel cell technologies capable of internal reforming, the separation of functions offers the advantage of separate optimization of the fuel cell stack and fuel processor, leading to fuel flexibility and lower systems costs. The combination of small size fuel cells, high market values, low development and demonstration costs, low market entry costs, and availability of off-the-shelf balance-of-system components, provides a low financial and technical risk scenario for fuel cell commercialization.

Fact sheet on fuel manufacturing and utilization

International Nuclear Information System (INIS)

2006-01-01

The Nuclear Fuel Cycle and Materials Section (NFCMS) supports Member States to improve in-pile fuel performance and management of materials; and to develop advanced fuel technologies for ensuring reliability and economic efficiency of the nuclear fuel cycle, provides assistance to Member States to support fuel-manufacturing capability, including quality assurance techniques, optimization of manufacturing parameters and radiation protection, supports the development fuel modeling expertise in Member States, covering both normal operation and postulated and severe accident conditions, provides information and support for the operation of Nuclear Power Plant to ensure that the environment and water chemistry is appropriate for fuel operation, supports fuel failure investigations, including equipment for failed fuel detection and for post-irradiation examination and inspection, as well as fuel repair, provides information and support research into the basic properties of fuel materials, including UO2, MOX, (Th, Pu)O2, (Th, U233)O2 fuels and zirconium alloy cladding and fuel assembly components and offers guidance on the relationship with back-end requirement (interim storage, transport, reprocessing, disposal), fuel utilization and management, MOX fuels, alternative fuels and advanced fuel technology and materials, economic and other aspects of nuclear fuel use (e.g. environmental impact). Recently NFCMS provided support to a Member State manufacturing Gadolinia doped fuel and provided in-mast sipping equipment to a Nuclear Power Plant to allow the determination of fuel failure. Member States interested in fuel performance and manufacture should contact the Technical Cooperation Department of the Agency and Member States interested in knowing more about the Agency's programme on source management should contact: C. Ganguly, Section Head, V. Inozemtsev, J. Killeen

Grid spacers for use in a nuclear fuel assembly

International Nuclear Information System (INIS)

Kuwako, Akira.

1987-01-01

Purpose: To obtain spacers capable of reducing the pressure loss by enlarging coolant flow channels when the fuel temperature is high, while capable of reliably maintaining the fuel pins with no vibrations when the fuel temperature is low. Constitution: This invention concerns grid spacers for constituting fuel assemblies for use in water cooled reactors. Memory shape alloys are disposed at least a portion of a spacer element that takes such a shape as urging the pin when the fuel temperature is low, while enlarging the coolant flow channel to reduce the pressure loss when the fuel temperature is high. (Ikeda, J.)

Recent developments in the modeling of molten carbonate fuel cells

International Nuclear Information System (INIS)

Wilemski, G.

1984-01-01

Modeling of porous electrodes and overall performance of molten carbonate fuel cells is reviewed. Aspects needing improvement are discussed. Some preliminary results on internal methane reforming cells are presented. Successful modeling of molten carbonate fuel cells has been carried out at two levels. The first concerns the prediction of overall cell performance and performance decay, i.e., the calculation of current-voltage curves and their decay rates for various cell operating conditions. The second involves the determination of individual porous electrode performance, i.e., how the electrode overpotential is affected by pore structure, gas composition, degree of electrolyte fill, etc. Both levels are treated mechanistically, as opposed to empirically, using fundamental mathematical descriptions of the relevant physical and chemical phenomena, in order to provide quantitative predictive capability

Sustainably produced ethanol. A premium fuel component; Nachhaltig produziertes Ethanol. Eine Premium Kraftstoffkomponente

Energy Technology Data Exchange (ETDEWEB)

Bernard, Joerg [Suedzucker AG, Obrigheim/Pfalz (Germany)

2012-07-01

Ethanol is the most used biofuel in the world. It is part of the European biofuel strategy, which is intended to preserve finite fossil resources, reduce greenhouse gas emissions and strengthen European agriculture. In addition to its traditional use in E5 fuel, ethanol most recently features in new fuels for petrol engines in Europe: as E10 as an expansion of the already existing concept of ethanol blends, such as in E5, or as ethanol fuel E85, a blend made up primarily of ethanol. There is already extensive international experience for both types of fuel for example in the USA or Brazil. The use of ethanol as a biofuel is linked to sustainability criteria in Europe which must be proven through a certification scheme. In addition to ethanol, the integrated production process also provides vegetable protein which is used in food as well as in animal feed and therefore provides the quality products of processed plants used for sustainable energy and in animal and human food. Ethanol has an effect on the vapour pressure, boiling behaviour and octane number of the fuel blend. Adjusting the blend stock petrol to fulfil the quality requirements of the final fuel is therefore necessary. Increasing the antiknock properties, increasing the heat of evaporation of the fuel using ethanol and the positive effects this has on the combustion efficiency of the petrol engine are particularly important. Investigations on cars or engines that were specifically designed for fuel with a higher ethanol content show significant improvements in using the energy from the fuel and the potential to reduce carbon dioxide emissions if fuels containing ethanol are used. The perspective based purely on an energy equivalent replacement of fossil fuels with ethanol is therefore misleading. Ethanol can also contribute to increasing the energy efficiency of petrol engines as well as being a replacement source of energy. (orig.)

Final report of fuel dynamics Test E7

International Nuclear Information System (INIS)

Doerner, R.C.; Murphy, W.F.; Stanford, G.S.; Froehle, P.H.

1977-04-01

Test data from an in-pile failure experiment of high-power LMFBR-type fuel pins in a simulated $3/s transient-overpower (TOP) accident are reported and analyzed. Major conclusions are that (1) a series of cladding ruptures during the 100-ms period preceding fuel release injected small bursts of fission gas into the flow stream; (2) gas release influenced subsequent cladding melting and fuel release [there were no measurable FCI's (fuel-coolant interactions), and all fuel motion observed by the hodoscope was very slow]; (3) the predominant postfailure fuel motion appears to be radial swelling that left a spongy fuel crust on the holder wall; (4) less than 4 to 6 percent of the fuel moved axially out of the original fuel zone, and most of this froze within a 10-cm region above the original top of the fuel zone to form the outlet blockage. An inlet blockage approximately 1 cm long was formed and consisted of large interconnected void regions. Both blockages began just beyond the ends of the fuel pellets

Formaldehyde, methanol and hydrocarbon emissions from methanol-fueled cars

International Nuclear Information System (INIS)

Williams, R.L.; Lipari, F.; Potter, R.A.

1990-01-01

Exhaust and evaporative emissions tests were conducted on several methanol- and gasoline-fueled vehicles. Separate samples for chromatographic analysis of formaldehyde, methanol, and individual hydrocarbons were collected in each of the three phases of the driving cycle and in each of the two portions of the evaporative emissions test. One vehicle, equipped with an experimental variable-fuel engine, was tested using methanol/gasoline fuel mixtures of 100, 85, 50, 15, and 0 percent methanol. Combustion-generated hydrocarbons were lowest using methanol fuel, and increased several-fold as the gasoline fraction was increased. Gasoline components in the exhaust increased from zero as the gasoline fraction of the fuel was increased. On the other hand, formaldehyde emissions were several times higher using methanol fuel than they were using gasoline. A dedicated methanol car and the variable-fuel car gave similar emissions patterns when they both were tested using methanol fuel. The organic-carbon composition of the exhaust was 85-90 percent methanol, 5-7 percent formaldehyde, and 3-9 percent hydrocarbons. Several cars that were tested using gasoline emitted similar distributions of hydrocarbons, even through the vehicles represented a broad range of current and developmental engine families and emissions control systems

D.E.R. 85 panorama

International Nuclear Information System (INIS)

1986-01-01

This progress report presents the panorama of the studies carried out by the ''Direction des Etudes et des Recherches'' (E.D.F.): nuclear boilers; classical and nuclear thermal power plants, hydraulic power plants; electrical equipment; network analysis environmental impacts; uses of electric power; new aspects of energy; applied informatics and mathematics; normalization and patents. A selection of the publications of 1985 is finally presented [fr

14 CFR 31.45 - Fuel cells.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fuel cells. 31.45 Section 31.45 Aeronautics... STANDARDS: MANNED FREE BALLOONS Design Construction § 31.45 Fuel cells. If fuel cells are used, the fuel cells, their attachments, and related supporting structure must be shown by tests to be capable of...

NAPL migration and ecotoxicity of conventional and renewable fuels in accidental spill scenarios.

Science.gov (United States)

Malk, Vuokko; Barreto Tejera, Eduardo; Simpanen, Suvi; Dahl, Mari; Mäkelä, Riikka; Häkkinen, Jani; Kiiski, Anna; Penttinen, Olli-Pekka

2014-01-01

Fuels derived from non-petroleum renewable resources have raised interest due to their potential in replacing petroleum-based fuels, but information on their fate and effects in the terrestrial and aquatic environments in accidental spill scenario is limited. In this study, migration of four fuels (conventional diesel, conventional gasoline, renewable diesel NExBTL, and ethanol-blended gasoline RE85 containing maximum 85% ethanol) as non-aqueous phase liquids (NAPL) in soil was demonstrated in a laboratory-scale experiment. Ecotoxicity data was produced for the same fuels. There was no significant difference in migration of conventional and renewable diesel, but gasoline migrated 1.5 times deeper and 7-9 times faster in sand than diesel. RE85 spread horizontally wider but not as deep (p gasoline. Conventional gasoline was the most toxic (lethal concentration [LC50] 20 mg/kg total hydrocarbon content [THC]) among the studied fuels in soil toxicity test with earthworm Eisenia fetida followed by ethanol-blended gasoline (LC50 1,643 mg/kg THC) and conventional diesel (LC50 2,432 mg/kg THC), although gasoline evaporated fast from soil. For comparison, the toxicity of the water-accommodated fractions (WAF) of the fuels was tested with water flea Daphnia magna and Vibrio fischeri, also demonstrating groundwater toxicity. The WAF of conventional gasoline and RE85 showed almost similar toxicity to both the aquatic test species. EC50 values of 1:10 (by volume) WAF were 9.9 %WAF (gasoline) and 9.3 %WAF (RE85) to D. magna and 9.3 %WAF (gasoline) and 12.3 %WAF (RE85) to V. fischeri. Low solubility decreased toxicity potential of conventional diesel in aquatic environment, but direct physical effects of oil phase pose a threat to organisms in nature. Renewable diesel NExBTL did not show clear toxicity to any test species.

Students' Perceptions of the Usefulness of an E-Book with Annotative and Sharing Capabilities as a Tool for Learning: A Case Study

Science.gov (United States)

Lim, Ee-Lon; Hew, Khe Foon

2014-01-01

E-books offer a range of benefits to both educators and students, including ease of accessibility and searching capabilities. However, the majority of current e-books are repository-cum-delivery platforms of textual information. Hitherto, there is a lack of empirical research that examines e-books with annotative and sharing capabilities. This…

Overview of the CANDU fuel handling system for advanced fuel cycles

International Nuclear Information System (INIS)

Koivisto, D.J.; Brown, D.R.

1997-01-01

Because of its neutron economies and on-power re-fuelling capabilities the CANDU system is ideally suited for implementing advanced fuel cycles because it can be adapted to burn these alternative fuels without major changes to the reactor. The fuel handling system is adaptable to implement advanced fuel cycles with some minor changes. Each individual advanced fuel cycle imposes some new set of special requirements on the fuel handling system that is different from the requirements usually encountered in handling the traditional natural uranium fuel. These changes are minor from an overall plant point of view but will require some interesting design and operating changes to the fuel handling system. Some preliminary conceptual design has been done on the fuel handling system in support of these fuel cycles. Some fuel handling details were studies in depth for some of the advanced fuel cycles. This paper provides an overview of the concepts and design challenges. (author)

75 FR 29605 - Clean Alternative Fuel Vehicle and Engine Conversions

Science.gov (United States)

2010-05-26

... Part II Environmental Protection Agency 40 CFR Parts 85 and 86 Clean Alternative Fuel Vehicle and...-0299; FRL-9149-9] RIN 2060-AP64 Clean Alternative Fuel Vehicle and Engine Conversions AGENCY... streamline the process by which manufacturers of clean alternative fuel conversion systems may demonstrate...

NPP fuel cycle and assessment of possible options for long-term fuel supply

International Nuclear Information System (INIS)

Ignatenko, E.I.; Lebedev, V.M.; Davidenko, N.N.

1999-01-01

The purpose of this paper is to present some results of the analysis of the possible options for Russian NPPs fuel supply. In the classical consideration these are four fuel cycles: uranium cycle based on natural uranium, this cycle has several economical advantages with the use of CANDU type reactors with a heavy-water moderator; uranium cycle based on enriched uranium, it is a basis for the current and future nuclear power; uranium-thorium fuel cycle with capabilities which are very promising but unfortunately difficult to implement in practice; plutonium-uranium cycle, in terms of its potential capabilities it is an excellent option, but it is extremely difficult to implement it in practice due to a high activity and toxicity of nuclear materials under recycle. The nuclear power of Russia is currently aimed at using the cheapest fuel resources, that is first of all, uranium reprocessed from industrial reactor fuel and slag-heaps accumulated on the past in isotope-separation plant sites. These resources are enough for the Russian large-scale nuclear power to be developed [ru

Designation of Environmental Impacts and Damages of Turbojet Engine: A Case Study with GE-J85

OpenAIRE

Altuntas, Onder

2014-01-01

Between the troposphere and stratosphere layers of the atmosphere is a critical zone for collecting emissions and negative effects on the Earth (ecological, humanity, and resources). Aircrafts are the main causes of the impacts in this layer. In this study, environmental effects (Damages, Specific Fuel Consumption Impact-SFCI and Thrust Environmental Impact-TEI) of different fueled (Jet-A and Liquid Hydrogen-H2) jet engines (a case study with GE-J85) are investigated. This comparison was made...

Apparatus for locating defective nuclear fuel elements

International Nuclear Information System (INIS)

Lawrie, W.E.

1979-01-01

An ultrasonic search unit for locating defective fuel elements within a fuel assembly used in a water cooled nuclear reactor is presented. The unit is capable of freely traversing the restricted spaces between the fuel elements

Fuel sub-assembly

International Nuclear Information System (INIS)

Jolly, R.

1982-01-01

A fuel sub-assembly for a liquid metal cooled nuclear reactor is described in which the bundle of fuel pins are braced apart by a series of spaced grids. The grids at the lower end are capable of yielding, thus allowing pins swollen by irradiation to be withdrawn with a reduced risk of damage. (U.K.)

Spent-fuel disassembly and canning programs at the Barnwell Nuclear Fuel Plant (BNFP)

International Nuclear Information System (INIS)

Townes, G.A.

1980-02-01

Doubling pool storage and tripling truck cask shipping capability appear feasible based on preliminary development work performed at the BNFP. This would be accomplished by disassembly of the fuel assembly and canning of the fuel pins. The dry, remote disassembly and canning in the headend cells offer adequate rates, easily controlled operator exposure, and visual inspection of the fuel pins and operations through shielded windows

Gamma-Ray Emission Tomography: Modeling and Evaluation of Partial-Defect Testing Capabilities

International Nuclear Information System (INIS)

Jacobsson Svard, S.; Jansson, P.; Davour, A.; Grape, S.; White, T.A.; Smith, L.E.; Deshmukh, N.; Wittman, R.S.; Mozin, V.; Trellue, H.

2015-01-01

Gamma emission tomography (GET) for spent nuclear fuel verification is the subject for IAEA MSP project JNT1955. In line with IAEA Safeguards R&D plan 2012-2023, the aim of this effort is to ''develop more sensitive and less intrusive alternatives to existing NDA instruments to perform partial defect test on spent fuel assembly prior to transfer to difficult to access storage''. The current viability study constitutes the first phase of three, with evaluation and decision points between each phase. Two verification objectives have been identified; (1) counting of fuel pins in tomographic images without any a priori knowledge of the fuel assembly under study, and (2) quantitative measurements of pinby- pin properties, e.g., burnup, for the detection of anomalies and/or verification of operator-declared data. Previous measurements performed in Sweden and Finland have proven GET highly promising for detecting removed or substituted fuel rods in BWR and VVER-440 fuel assemblies even down to the individual fuel rod level. The current project adds to previous experiences by pursuing a quantitative assessment of the capabilities of GET for partial defect detection, across a broad range of potential IAEA applications, fuel types and fuel parameters. A modelling and performance-evaluation framework has been developed to provide quantitative GET performance predictions, incorporating burn-up and cooling-time calculations, Monte Carlo radiation-transport and detector-response modelling, GET instrument definitions (existing and notional) and tomographic reconstruction algorithms, which use recorded gamma-ray intensities to produce images of the fuel's internal source distribution or conclusive rod-by-rod data. The framework also comprises image-processing algorithms and performance metrics that recognize the inherent tradeoff between the probability of detecting missing pins and the false-alarm rate. Here, the modelling and analysis framework is

Capture and immobilization of krypton-85

International Nuclear Information System (INIS)

Whitmell, D.S.; Geens, L.; Penzhorn, R.D.; Smith, M.J.S.

1985-01-01

It may become necessary to contain the krypton-85 released from nuclear fuel during reprocessing in order to reduce the exposure to the local population and the radioactive background throughout the world. A brief description is given of studies being carried out in the Indirect Action Programme. The separation of krypton from other off-gases by cryogenic distillation in the presence of oxygen is being studied at SCK/CEN Mol, together with the behavior of ozone in the distillation column. Two processes for the immobilization of krypton in solid forms have been successfully developed and demonstrated. At KfK Karlsruhe, krypton is encapsulated in vitrified zeolites; at AERE Harwell, krypton is immobilized within a metallic matrix. These processes offer excellent gas retention and either could be adopted for a reprocessing plant

Mass Flow Data Comparison for Comprehensive Fuel Cycle Options

International Nuclear Information System (INIS)

Kim, T.K.; Taiwo, T.A.; Wigeland, R.A.; Dixon, B.W.; Gehin, J.C.; Todosow, M.

2015-01-01

One of the key objectives stated in the United States Department of Energy, Nuclear Energy R and D road-map is the development of sustainable nuclear fuel cycles that improve natural resource utilisation and provide adequate capability and capacity to manage wastes produced by the fuel cycle. In order to inform this objective, an evaluation and screening of nuclear fuel cycle options has been conducted. As part of that effort, the entire fuel cycle options space was represented by 40 Evaluation Groups (EGs), and mass flow information for each of the EGs was provided by using an Analysis Example (AE). In this paper, the mass flow data of the 40 AEs are compared to inform on trends in the natural resource utilisation and nuclear waste generation. For the AEs that need enriched uranium support, the natural uranium required is high and the natural resource utilisation is generally lower than 2% regardless of the fuel cycle strategy (i.e., once-through, limited recycle, or continuous recycle). However, the utilisation could be improved by avoiding enriched uranium fuel support. The natural resource utilisation increases to more than 80% by recycling the nuclear fuel continuously without enriched uranium support. The combined mass of spent nuclear fuel (SNF) and high-level waste (HLW), i.e., SNF+HLW mass, is lower by using a continuous recycle option compared to a once-through fuel cycle option, because SNF mass is converted to mass of recycled products and only fission products and other process losses need to be disposed. The combined disposed mass of depleted uranium (DU), recovered uranium (RU) and thorium (RTh), i.e. DU+RU+RTh mass, has a similar trend to the uranium utilisation. For the AEs that need enriched uranium fuel, the DU and RU are the major fraction by mass of the DU+RU+RTh, which are two orders of magnitude higher in mass compared to those for the AEs that do not need enriched uranium fuel. (authors)

Environmental consequences of atmosphereic krypton-85. Final report, January 1, 1977-September 30, 1979

International Nuclear Information System (INIS)

Boeck, W.L.

1979-01-01

Krypton-85 is a radioactive inert gas produced during normal operations of the nuclear fuel cycle. The quantities of krypton-85, that will be produced in the next century, are sufficient, if released, to alter the electrical state of the atmosphere. The principal hypothesis is that an anthropogenic alteration of the electric state of the atmosphere could alter other meterological phenomena and lead to significant environmental impacts. The goal of this project was to explore some areas of basic science related to the evaluation of that hypothesis. The approach was primarily theoretical. The following topics were addressed: a first approximation model to estimate the effects of krypton-85 on the electrical state of the atmosphere; an analysis of the pathways between krypton-85 production and the atmosphere; an analytical model for fair weather atmospheric electricity; and a dipole model for atmospheric electricity. The results will provide a framework on which detailed models can be built. The results should provide better understanding of some topics in atmospheric electricity

Advanced Post-Irradiation Examination Capabilities Alternatives Analysis Report

Energy Technology Data Exchange (ETDEWEB)

Jeff Bryan; Bill Landman; Porter Hill

2012-12-01

An alternatives analysis was performed for the Advanced Post-Irradiation Capabilities (APIEC) project in accordance with the U.S. Department of Energy (DOE) Order DOE O 413.3B, “Program and Project Management for the Acquisition of Capital Assets”. The Alternatives Analysis considered six major alternatives: ? No Action ? Modify Existing DOE Facilities – capabilities distributed among multiple locations ? Modify Existing DOE Facilities – capabilities consolidated at a few locations ? Construct New Facility ? Commercial Partnership ? International Partnerships Based on the alternatives analysis documented herein, it is recommended to DOE that the advanced post-irradiation examination capabilities be provided by a new facility constructed at the Materials and Fuels Complex at the Idaho National Laboratory.

Evolution of the Darlington NGS fuel handling computer systems

International Nuclear Information System (INIS)

Leung, V.; Crouse, B.

1996-01-01

The ability to improve the capabilities and reliability of digital control systems in nuclear power stations to meet changing plant and personnel requirements is a formidable challenge. Many of these systems have high quality assurance standards that must be met to ensure adequate nuclear safety. Also many of these systems contain obsolete hardware along with software that is not easily transported to newer technology computer equipment. Combining modern technology upgrades into a system of obsolete hardware components is not an easy task. Lastly, as users become more accustomed to using modern technology computer systems in other areas of the station (e.g. information systems), their expectations of the capabilities of the plant systems increase. This paper will present three areas of the Darlington NGS fuel handling computer system that have been or are in the process of being upgraded to current technology components within the framework of an existing fuel handling control system. (author). 3 figs

Evolution of the Darlington NGS fuel handling computer systems

Energy Technology Data Exchange (ETDEWEB)

Leung, V; Crouse, B [Ontario Hydro, Bowmanville (Canada). Darlington Nuclear Generating Station

1997-12-31

The ability to improve the capabilities and reliability of digital control systems in nuclear power stations to meet changing plant and personnel requirements is a formidable challenge. Many of these systems have high quality assurance standards that must be met to ensure adequate nuclear safety. Also many of these systems contain obsolete hardware along with software that is not easily transported to newer technology computer equipment. Combining modern technology upgrades into a system of obsolete hardware components is not an easy task. Lastly, as users become more accustomed to using modern technology computer systems in other areas of the station (e.g. information systems), their expectations of the capabilities of the plant systems increase. This paper will present three areas of the Darlington NGS fuel handling computer system that have been or are in the process of being upgraded to current technology components within the framework of an existing fuel handling control system. (author). 3 figs.

40 CFR 600.009-85 - Hearing on acceptance of test data.

Science.gov (United States)

2010-07-01

...) ENERGY POLICY FUEL ECONOMY AND CARBON-RELATED EXHAUST EMISSIONS OF MOTOR VEHICLES Fuel Economy... economy data vehicle, in accordance with§ 600.008 (e) or (g), or (ii) The use of fuel economy data, in...) The fuel economy label values determined by the manufacturer under § 600.312(a), then (2)(i) The...

Improving the characteristics of liquid fuel

Energy Technology Data Exchange (ETDEWEB)

Sakan, T

1983-02-04

In order to improve the operational characteristics of a light boiler fuel (LKT) (based on analogous characteristics for a fuel for an internal combustion engine (DVS)) it is proposed to add ether and alcohol to it. The additive of ether improves the viscosity of the fuel, but reduces the heat creating capability. The addition of ether and alcohol (a 3 to 1 ratio by volume) increases the stability of the mixture. With mixing of 75 total percent of the light boiler fuel (a heat creativity of 9,500 kilocalories per liter and a viscosity of 10 centistokes per 30 degrees) with 25 total percent ether produced a fuel with a heat producing capability of 8,690 kilocalories per liter and a viscosity of 2.3 centistokes. With mixing of 70 total percent light boiler oil and 18 total percent ether and 7 total percent alcohol a fuel with a heat creativity of 8,640 kilocalories per liter and a viscosity of 2.7 centistokes was produced.

P and e identification capabilities CAPRICE

Energy Technology Data Exchange (ETDEWEB)

Basini, G. [INFN, Laboratori Nazionali di Frascati, Rome (Italy); Codino, A.; Grimani, C. [Perugia Univ. (Italy)]|[INFN, Perugia (Italy); De Pascale, M.P. [Rome Univ. `Tor Vergata` (Italy)]|[INFN, Rome (Italy); Hof, M. [Siegen Univ. (Germany). Fachbereich Physik; Golden, R.L. [New Mexico State Univ., Las Cruces, NM (United States). Particle Astrophysics Lab.; Brancaccio, F.; Bocciolini, M. [Florence Univ. (Italy)]|[INFN, Florence (Italy); Barbiellini, G.; Boezio, M. [Trieste Univ. (Italy)]|[INFN, Trieste (Italy)

1995-09-01

The cosmic antiparticle ring imaging Cherenkov experiment (CAPRICE) flew on a stratospheric balloon 8-9 August 1994 over northern Canada and collected data for more than 21 hours with less than 5 g/cm{sup 2} of residual atmosphere. The instrument includes a solid radiator RICH detector and an electromagnetic calorimeter for particle identification in the magnetic spectrometer. Preliminary antiproton and positron identification capabilities are presented.

Preliminary safety evaluation of a commercial-scale krypton-85 encapsulation facility

International Nuclear Information System (INIS)

Christensen, A.B.; Tanner, J.E.; Knecht, D.A.

1980-09-01

This report demonstrates that a commercial-scale facility for encapsulating krypton-85 in zeolite-5A or glass at a 2000 MTHM per year nuclear fuel reprocessing plant can be designed to contain fragments and the 340 to 850 kCi krypton-85 inventory from an assumed catastrophic failure of the high pressure vessel. The vessel failure was assumed as a worst case and was not based on a detailed design evaluation or operating experience. The process design is based on existing commercial hot isostatic pressing technology operated at up to 40 times the scale required for krypton encapsulation. From the calculated process gas inventory in the pressure vessel and vessel design, the explosive energy of 8.4 kg TNT and vessel plug and fragment velocities were calculated. The facility Containment Cell housing the high pressure vessel was designed to contain the gases, fragments, and the shock wave energy calculated for vessel failure. The Access Cell located directly above the Containment Cell was designed to be a tertiary confinement of krypton-85, should the access hatch be breached

Emission characteristics when using bioethanol as a fuel for passenger cars

International Nuclear Information System (INIS)

Egebaeck, K.E.; Laurikko, J.; Ryden, C.

1998-11-01

In 1991 the Swedish Transport and Communication Research Board (KFB), was asked by the Swedish Government to carry out investigations and field tests in order to demonstrate the possibility of using bioethanol and biogas as automotive fuels. A five-year programme was set up for the investigations and demonstrations and the programme was later extended to a seven-year programme. Despite the fact that most of the work has been directed towards heavy-duty vehicles and especially buses in city traffic some important investigations have been carried out in order to demonstrate the use of bioethanol and biogas in passenger cars. The programme for passenger cars has consisted of running and testing 53 Flexible Fuel Vehicles (FFV), fuelled with bioethanol (E85), a project run by the Swedish Ethanol Development Foundation, and 20 other cars fuelled with biogas, a project carried out by the City of Stockholm's Material Supply Organisation, and sponsored by KFB. For both fleets of vehicles the exhaust emissions have been extensively characterised at a laboratory in Finland owned by the Technical Research Centre of Finland. The aim of this paper is to present some interesting results from the demonstrations of the use of E85 in FFV's and thereby especially focus on the results of the characterisation of both regulated and non-regulated emissions 23 refs, 16 figs, 9 tabs

Emission characteristics when using bioethanol as a fuel for passenger cars

Energy Technology Data Exchange (ETDEWEB)

Egebaeck, K.E. [Luleaa Univ. of Technology, (Sweden); Laurikko, J. [Technical Research Centre of Finland, Helsinki (Finland); Ryden, C. [Tima, (Sweden)

1998-11-01

In 1991 the Swedish Transport and Communication Research Board (KFB), was asked by the Swedish Government to carry out investigations and field tests in order to demonstrate the possibility of using bioethanol and biogas as automotive fuels. A five-year programme was set up for the investigations and demonstrations and the programme was later extended to a seven-year programme. Despite the fact that most of the work has been directed towards heavy-duty vehicles and especially buses in city traffic some important investigations have been carried out in order to demonstrate the use of bioethanol and biogas in passenger cars. The programme for passenger cars has consisted of running and testing 53 Flexible Fuel Vehicles (FFV), fuelled with bioethanol (E85), a project run by the Swedish Ethanol Development Foundation, and 20 other cars fuelled with biogas, a project carried out by the City of Stockholm`s Material Supply Organisation, and sponsored by KFB. For both fleets of vehicles the exhaust emissions have been extensively characterised at a laboratory in Finland owned by the Technical Research Centre of Finland. The aim of this paper is to present some interesting results from the demonstrations of the use of E85 in FFV`s and thereby especially focus on the results of the characterisation of both regulated and non-regulated emissions 23 refs, 16 figs, 9 tabs

Externalities of fuel cycles 'ExternE' project. Hydro fuel cycle. Estimation of physical impacts and monetary valuation for priority impact pathways

International Nuclear Information System (INIS)

Navrud, S.; Riise, J.; Strand, J.

1994-01-01

The aim of the External Costs of Fuel Cycles (ExternE) study is to develop methods to measure and monetize all the externalities associated with incremental investments in electric power production, taking account of the different stages of the fuel cycles. Since fuel cycle externalities are characterised by being very site-specific, the impact pathway damage function approach, developed in ExternE, has been implemented in different European countries for each of the selected fuel cycles. This is done to demonstrate that this methodological framework can be used at different locations, to motivate further development of the methods, and to look at the sensitivity of the estimates to different locations. Electricite de France (EdF) in France and ENCO Environmental Consultants a.s. in Norway have taken on a joint responsibility for adapting the methodological framework for hydroelectric fuel cycle analyses in Europe. We report the first implementation of the hydroelectric fuel cycle within ExternE. Choice of reference site and technology Two stages of the hydroelectric fuel cycle have been identified: 1. Electricity generation 2. Transmission There are three phases of each of these stages: construction, operation and dismantling. We have assumed a construction period of 5 years (starting in 1990) and an operation period of 40 years. Dismantling after 40 years is not a realistic option. Therefore, we have focused on the construction and operation phases, of both electricity generation and transmission. The Sauda Hydroelectric Development Project (SHDP) was selected, because it illustrates upgrading and extention of an existing hydro power project. Such projects are likely to be the dominating strategy for future hydroelectric development in Norway, many other European countries and in the U.S., due to the lack of new sites available for development. SHDP consists of an extention of a previously developed area (Basis project) and six new diversion projects. The

Biodiesel from Mustard oil: a Sustainable Engine Fuel Substitute for Bangladesh

Directory of Open Access Journals (Sweden)

M.M. Alam

2013-10-01

Full Text Available Various attractive features of mustard oil based biodiesel as a potential substitute for engine fuel are investigated in this paper for use in Bangladesh. Although the use of mustard oil as edible oil has been reduced, Bangladesh still produces 0.22 million metric tons of mustard oil per year. This surplus mustard oil would satisfactorily be used as an alternative to diesel fuel, and thus could contribute in reducing the expenses for importing fuel from foreign countries. Moreover, the rural people of Bangladesh are capable of producing mustard oil themselves using indigenous machines. Fuel properties of biodiesel obtained from mustard oil were determined in the laboratory using standard procedure and an experimental setup was constructed to study the performance of a small diesel engine. It is observed that with biodiesel, the engine is capable of running without difficulty. Initially different lower blends of biodiesel (e.g., B20, B30 etc. have been used to avoid complicated modification of the engine and the fuel supply system. It is also found in some condition that mustard oil based biodiesel have better properties than those made from other vegetable oils. These properties of mustard oil based biodiesel were evaluated to validate its sustainability in Bangladesh. Keywords: biodiesel, indigenous machines, mustard oil, renewable energy policy, sustainability

Safety assessment of OPG's used fuel for dry storage

International Nuclear Information System (INIS)

Roman, H.; Khan, A.

2005-01-01

'Full text:' Ontario Power Generation (OPG) operates the Pickering Waste Management Facility (PWMF) and Western Waste Management Facility (WWMF) where OPG has been storing 10-year or older used fuel in the Dry Storage Containers (DSCs) since 1996 and 2003 respectively. The construction licence for the Darlington Used Fuel Dry Storage Facility (DUFDSF) was obtained in August 2004. Safety assessment of the used fuel for dry storage is required to support each request for regulatory approval to construct and operate a dry storage facility. The objective of the safety assessment is to assess the used fuel performance under normal operation and postulated credible accident scenarios. A reference used fuel bundle is defined based on the operating history and data on fuel discharged from the reactors of the specific nuclear generating station. The characteristics of the reference used fuel bundle are used to calculate the nuclide inventory, source term and decay heat used for the assessment. When assessing malfunctions and accidents, postulated external and internal events are considered. Consideration is also given to the design basis accidents of the specific nuclear generating station that could affect the used fuel under dry storage. For those events deemed credible (i.e. probability > 10 -7 ), a bounding fuel failure consequence is predicted. Given the chemical characteristics of the radionuclides in used fuel, the design of the CANDU fuel and the conditions inside the DSC, in the event that a used fuel bundle should become damaged during used fuel dry storage operations, the only significant radionuclides species that are volatile are krypton-85 and tritium. Release of these radionuclides is considered in calculating public and worker doses. (author)

IFR fuel cycle--pyroprocess development

International Nuclear Information System (INIS)

Laidler, J.J.; Miller, W.E.; Johnson, T.R.; Ackerman, J.P.; Battles, J.E.

1992-01-01

The Integral Fast Reactor (IFR) fuel cycle is based on the use of a metallic fuel alloy, with nominal composition U-2OPu-lOZr. In its present state of development, this fuel system offers excellent high-burnup capabilities. Test fuel has been carried to burnups in excess of 20 atom % in EBR-II irradiations, and to peak burnups over 15 atom % in FFTF. The metallic fuel possesses physical characteristics, in particular very high thermal conductivity, that facilitate a high degree of passive inherent safety in the IFR design. The fuel has been shown to provide very large margins to failure in overpower transient events. Rapid overpower transient tests carried out in the TREAT reactor have shown the capability to withstand up to 400% overpower conditions before failing. An operational transient test conducted in EBR-II at a power ramp rate of 0.1% per second reached its termination point of 130% of normal power without any fuel failures. The IFR metallic fuel also exhibits superior compatibility with the liquid sodium coolant. Equally as important as the performance advantages offered by the use of metallic fuel is the fact that this fuel system permits the use of an innovative reprocessing method, known as ''pyroprocessing,'' featuring fused-salt electrorefining of the spent fuel. Development of the IFR pyroprocess has been underway at the Argonne National Laboratory for over five years, and great progress has been made toward establishing a commercially-viable process. Pyroprocessing offers a simple, compact means for closure of the fuel cycle, with anticipated significant savings in fuel cycle costs

Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code

Science.gov (United States)

Williamson, R. L.; Capps, N. A.; Liu, W.; Rashid, Y. R.; Wirth, B. D.

2016-11-01

Nuclear fuel operates in an extreme environment that induces complex multiphysics phenomena occurring over distances ranging from inter-atomic spacing to meters, and times scales ranging from microseconds to years. To simulate this behavior requires a wide variety of material models that are often complex and nonlinear. The recently developed BISON code represents a powerful fuel performance simulation tool based on its material and physical behavior capabilities, finite-element versatility of spatial representation, and use of parallel computing. The code can operate in full three dimensional (3D) mode, as well as in reduced two dimensional (2D) modes, e.g., axisymmetric radial-axial ( R- Z) or plane radial-circumferential ( R- θ), to suit the application and to allow treatment of global and local effects. A BISON case study was used to illustrate analysis of Pellet Clad Mechanical Interaction failures from manufacturing defects using combined 2D and 3D analyses. The analysis involved commercial fuel rods and demonstrated successful computation of metrics of interest to fuel failures, including cladding peak hoop stress and strain energy density. In comparison with a failure threshold derived from power ramp tests, results corroborate industry analyses of the root cause of the pellet-clad interaction failures and illustrate the importance of modeling 3D local effects around fuel pellet defects, which can produce complex effects including cold spots in the cladding, stress concentrations, and hot spots in the fuel that can lead to enhanced cladding degradation such as hydriding, oxidation, CRUD formation, and stress corrosion cracking.

Nuclear Fuels & Materials Spotlight Volume 4

Energy Technology Data Exchange (ETDEWEB)

I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

2014-04-01

As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • The first identification of silver and palladium migrating through the SiC layer in TRISO fuel • A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension • Results of high-temperature safety testing on coated particle fuels irradiated in the ATR • New methods for testing the integrity of irradiated plate-type reactor fuel • Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions • Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and • An example of a capsule irradiation test. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

Study Of The Fuel Cycle Effect To The Electricity Generating Cost

International Nuclear Information System (INIS)

Salimy, D. H.

1998-01-01

The nuclear fuel cycle cost contributes relatively small fraction to the total nuclear power generation cost, I.e. about 15 to 30%, compared to the fuel cost in the coal-generated electricity (40-60%). Or in the oil-generated electricity (70-80%). This situation will give effect that the future generation cost is much less sensitive to the changes in the fuel prince than in the case of fossil fuel power plants. The study has shown that by assuming a 100% increase in the natural uranium price, the total nuclear fuel cycle cost would increase only by about 27% and in turn it contributes about 29% increase to the total nuclear fuel cycle cost. As a result, it contributes only 4 to 8% increase in the nuclear energy generation cost. As a comparison, if the same situation should occur to fossil fuel plants, the assumed fuel price increase would have increased the electricity generating cost by about 40-65% for coal-fired plants, and about 70-85% for oil-fired plants. This study also has assesses the economic aspects of the electricity generating cots for nuclear power plant (NPP) and the coal power plant. For an NPP the most affecting factor is the investment cost, while for the coal power plant, the major factor influencing the total cost is the price/cost of the fuel

Air quality effects of alternative fuels. Final report

Energy Technology Data Exchange (ETDEWEB)

Guthrie, P.; Ligocki, M.; Looker, R.; Cohen, J.

1997-11-01

To support the Alternative Fuels Utilization Program, a comparison of potential air quality effects of alternative transportation fuels is being performed. This report presents the results of Phase 1 of this program, focusing on reformulated gasoline (RFG), methanol blended with 15 percent gasoline (M85), and compressed natural gas (CNG). The fuels are compared in terms of effects on simulated future concentrations of ozone and mobile source air toxics in a photochemical grid model. The fuel comparisons were carried out for the future year 2020 and assumed complete replacement of gasoline in the projected light-duty gasoline fleet by each of the candidate fuels. The model simulations were carried out for the areas surrounding Los Angeles and Baltimore/DC, and other (non-mobile) sources of atmospheric emissions were projected according to published estimates of economic and population growth, and planned emission control measures specific to each modeling domain. The future-year results are compared to a future-year run with all gasoline vehicle emissions removed. The results of the comparison indicate that the use of M85 is likely to produce similar ozone and air toxics levels as those projected from the use of RFG. Substitution of CNG is projected to produce significantly lower levels of ozone and the mobile source air toxics than those projected for RFG or M85. The relative benefits of CNG substitution are consistent in both modeling domains. The projection methodologies used for the comparison are subject to a large uncertainty, and modeled concentration distributions depend on meteorological conditions. The quantitative comparison of fuel effects is thus likely to be sensitive to alternative assumptions. The consistency of the results for two very different modeling domains, using very different base assumptions, lends credibility to the qualitative differentiation among these fuels. 32 refs., 42 figs., 47 tabs.

Containing method for spent fuel and spent fuel containing vessel

International Nuclear Information System (INIS)

Maekawa, Hiromichi; Hanada, Yoshine.

1996-01-01

Upon containing spent fuels, a metal vessel main body and a support spacer having fuel containing holes are provided. The support spacer is disposed in the inside of the metal vessel main body, and spent fuel assemblies are loaded in the fuel containing holes. Then, a lid is welded at the opening of the metal vessel main body to provide a sealing state. In this state, heat released from the spent fuel assemblies is transferred to the wall of the metal vessel main body via the support spacer. Since the support spacer has a greater heat conductivity than gases, heat of the spent fuel assemblies tends to be released to the outside, thereby capable of removing heat of the spent fuel assemblies effectively. In addition, since the surfaces of the spent fuel assemblies are in contact with the inner surface of the fuel containing holes of the support spacer, impact-resistance and earthquake-resistance are ensured, and radiation from the spent fuel assemblies is decayed by passing through the layer of the support spacer. (T.M.)

Mathematical optimization of incore nuclear fuel management decisions: Status and trends

International Nuclear Information System (INIS)

Turinsky, P.J.

1999-01-01

Nuclear fuel management involves making decisions about the number of fresh assemblies to purchase and their Attributes (e.g. enrichment and burnable poison loading), burnt fuel to reinsert, location of the assemblies in the core (i.e. loading pattern (LP)), and insertion of control rods as a function of cycle exposure (i.e. control rod pattern (CRP)). The out-of-core and incore nuclear fuel management problems denote an artificial separation of decisions to simplify the decisionmaking. The out-of-core problem involves multicycle analysis so that levelized fuel cycle cost can be evaluated; whereas, the incore problem normally involves single cycle analysis. Decision variables for the incore problem normally include all of the above noted decisions with the exception of the number of fresh assemblies, which is restricted by discharge burnup limits and therefore involves multicycle considerations. This paper reports on the progress that is being made in addressing the incore nuclear fuel management problem utilizing formal mathematical optimization methods. Advances in utilizing the Simulating Annealing, Genetic Algorithm and Tabu Search methods, with applications to pressurized and boiling water reactor incore optimization problem, will be reviewed. Recent work on the addition of multiobjective optimization capability to aide the decision maker, and utilization of heuristic rules and incorporation of parallel algorithms to increase computational efficiency, will be discussed. (orig.) [de

COMPARATIVE ANALYSIS OF STRUCTURAL CHANGES IN U-MO DISPERSED FUEL OF FULL-SIZE FUEL ELEMENTS AND MINI-RODS IRRADIATED IN THE MIR REACTOR

Directory of Open Access Journals (Sweden)

ALEKSEY. L. IZHUTOV

2013-12-01

The full-size fuel rods were irradiated up to an average burnup of ∼ 60%235U; the mini-rods were irradiated to an average burnup of ∼ 85%235U. The presented data show a significant increase of the void fraction in the U-Mo alloy as the U-235 burnup rises from ∼ 40% up to ∼ 85%. The effect of irradiation test conditions and U-235 burnup were analyzed with regard to the formation of an interaction layer between the matrix and fuel particles as well as generation of porosity in the U-Mo alloy. Shown here are changes in distribution of U fission products as the U-235 burnup increases from ∼ 40% up to ∼ 85%.

Fission product release from TRIGA-LEU reactor fuels

International Nuclear Information System (INIS)

Baldwin, N.L.; Foushee, F.C.; Greenwood, J.S.

1980-01-01

Due to present international concerns over nuclear proliferation, TRIGA reactor fuels will utilize only low-enriched uranium (LEU) (enrichment <20%). This requires increased total uranium loading per unit volume of fuel in order to maintain the appropriate fissile loading. Tests were conducted to determine the fractional release of gaseous and metallic fission products from typical uranium-zirconium hydride TRIGA fuels containing up to 45 wt-% uranium. These tests, performed in late 1977 and early 1978, were similar to those conducted earlier on TRIGA fuels with 8.5 wt-% U. Fission gas release measurements were made on prototypic specimens from room temperature to 1100 deg. C in the TRIGA King Furnace Facility. The fuel specimens were irradiated in the TRIGA reactor at a low power level. The fractional releases of the gaseous nuclides of krypton and xenon were measured under steady-state operating conditions. Clean helium was used to sweep the fission gases released during irradiation from the furnace into a standard gas collection trap for gamma counting. The results of these tests on TRIGA-LEU fuel agree well with data from the similar, earlier tests on TRIGA fuel. The correlation used to calculate the release of fission products from 8.5 wt-% U TRIGA fuel applies equally well for U contents up to 45 wt-%. (author)

The Back End of the Fuel Cycle Moves Front and Center

International Nuclear Information System (INIS)

Isaacs, T; Choi, J

2006-01-01

For many years, the commercial nuclear business has remained relatively stable in many ways. The introduction of new plants, the spread to new countries, and the development of key elements of the fuel cycle such as enrichment, reprocessing and waste disposal have been quite modest. That is unlikely to be the case in the coming years. A number of events and trends are becoming increasingly apparent and are cause for both opportunity and caution: (1) New nuclear power plant orders are likely to grow and spread, particularly in the developing world, e.g. China and India. (2) The growing recognition that the developing world will be a major competitor for limited energy resources is raising awareness in the developed world regarding concerns for future energy security. (3) Clearer evidence of the effects of greenhouse gas emissions on global warming, largely from the burning of fossil fuels, is creating more attention on the environmental benefits of nuclear power. (4) The last decade has shown unequivocal evidence of countries lying, cheating on their NPT obligation, and covertly carrying out nuclear weapons-related activities. Some have suggested their presumed need for a domestic nuclear fuel cycle as a rationale to pursue enrichment and/or reprocessing capabilities, which would move them to the doorstep of being nuclear weapons capable. The DPRK even took the action to abrogate the NPT to hold on to its nuclear weapons program. (5) 9/11 and other evidence have made it undeniable that terrorist groups would like to obtain weapons of mass destruction, particularly nuclear weapons, and would use them if they could. A number of initiatives have been proposed recently to allow for the growth and spread of nuclear power while limiting the justifications for additional countries to pursue the acquisition of enrichment or reprocessing capabilities. Most of these initiatives have fresh fuel assurance as a central component. The rationale is simple; if a country can have

Fuel Thermal Expansion (FTHEXP)

International Nuclear Information System (INIS)

Reymann, G.A.

1978-07-01

A model is presented which deals with dimensional changes in LWR fuel pellets caused by changes in temperature. It is capable of dealing with any combination of UO 2 and PuO 2 in solid, liquid or mixed phase states, and includes expansion due to the solid-liquid phase change. The function FTHEXP models fuel thermal expansion as a function of temperature, fraction of PuO 2 , and the fraction of fuel which is molten

Session 1984-85. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

International Nuclear Information System (INIS)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

Interim spent-fuel storage options at commercial nuclear power plants

International Nuclear Information System (INIS)

Thakkar, A.R.; Hylko, J.M.

1991-01-01

Although spent fuel can be stored safely in waterfilled pools at reactor sites, some utilities may not possess sufficient space for life-of-plant storage capability. In-pool storage capability may be increased by reracking assemblies, rod consolidation, double tiering spent-fuel racks, and by shipping spent fuel to other utility-owned facilities. Long-term on-site storage capability for spent fuel may be provided by installing (dry-type) metal casks, storage and transportation casks, concrete casks, horizontal concrete modules, modular concrete vaults, or by constructing additional (pool-type) storage installations. Experience to date has provided valuable information regarding dry-type or pool-type installations, cask handling and staffing requirements, security features, decommissioning activities, and radiological issues

Marketing Capability in Strategy Research

DEFF Research Database (Denmark)

Ritter, Thomas; Distel, Andreas Philipp

Following the call for a demand-side perspective of strategic management (e.g., Priem et al., 2012), a firm’s marketing capability, i.e. its ability to interact with down-stream stakeholders, becomes a pivotal element in explaining a firm’s competitiveness. While marketing capability is recognized...... in the strategic management literature as an important driver of firm performance, our review of 86 articles reveals a lack of a generally accepted definition of marketing capability, a lack of a common conceptualization as well as differences in the measurement of marketing capability. In order to build a common...... ground for advancing marketing capability research and thus supporting the demand-side perspective in strategic management, we develop an integrative framework to explain the differences and propose a research agenda for developing the field....

Control rod studies for alternative fuel cycles in the GA 1160 MW(e) high temperature reactor

Energy Technology Data Exchange (ETDEWEB)

Neef, H. J.

1975-06-15

The control system, which is investigated in this paper for both the low enriched uranium high enriched uranium/thorium fuel cycles, has been developed to control the General Atomics (GA) thorium fuel cycle 1160 MW(e) reactor. It has been shown in this investigation that its effectiveness in the low enriched and subsequent thorium cycle switch-over reactor is equivalent to the effectiveness in the thorium cycle. The shutdown margin in the low enriched core is even higher compared to the thorium core, mainly due to the presence of Pa-233 in the thorium cycle. As long as the fuel cycle for the thorium cycle is not closed with the recycling of U-233, the low enriched cycle will offer an attractive alternative. It was found that the GA 1160 MW(e) control system has enough built-in control rod capacity to accommodate the low enriched uranium cycle and to perform a later switch-over to a thorium-based fuel cycle.

Microbial Fuel Cells under Extreme Salinity

Science.gov (United States)

Monzon del Olmo, Oihane

I developed a Microbial Fuel Cell (MFC) that unprecedentedly works (i.e., produces electricity) under extreme salinity (≈ 100 g/L NaCl). Many industries, such as oil and gas extraction, generate hypersaline wastewaters with high organic strength, accounting for about 5% of worldwide generated effluents, which represent a major challenge for pollution control and resource recovery. This study assesses the potential for microbial fuel cells (MFCs) to treat such wastewaters and generate electricity under extreme saline conditions. Specifically, the focus is on the feasibility to treat hypersaline wastewater generated by the emerging unconventional oil and gas industry (hydraulic fracturing) and so, with mean salinity of 100 g/L NaCl (3-fold higher than sea water). The success of this novel technology strongly depends on finding a competent and resilient microbial community that can degrade the waste under extreme saline conditions and be able to use the anode as their terminal electron acceptor (exoelectrogenic capability). I demonstrated that MFCs can produce electricity at extremely high salinity (up to 250 g/l NaCl) with a power production of 71mW/m2. Pyrosequencing analysis of the anode population showed the predominance of Halanaerobium spp. (85%), which has been found in shale formations and oil reservoirs. Promoting Quorum sensing (QS, cell to cell communication between bacteria to control gene expression) was used as strategy to increase the attachment of bacteria to the anode and thus improve the MFC performance. Results show that the power output can be bolstered by adding 100nM of quinolone signal with an increase in power density of 30%, for the first time showing QS in Halanaerobium extremophiles. To make this technology closer to market applications, experiments with real wastewaters were also carried out. A sample of produced wastewater from Barnet Shale, Texas (86 g/L NaCl) produced electricity when fed in an MFC, leading to my discovery of another

Characterization of Hanford K basin spent nuclear fuel and sludge

International Nuclear Information System (INIS)

Lawrence, L.A.

1996-01-01

A characterization plan was prepared to support the Integrated Process Strategy (IPS) for resolution of the safety and environmental concerns associated with the deteriorating Spent Nuclear Fuel (SNF) stored in the Hanford Site K Basins. This plan provides the structure and logic and identifies the information needs to be supported by the characterization activities. The IPS involves removal of the fuel elements from the storage canister and placing them in a container, i.e., Multiple Canister Overpack (MCO) capable of holding multiple tiers of baskets full of fuel. The MCOs will be vacuum dried to remove free water and shipped to the Container Storage Building (CSB) where they will be staged waiting for hot vacuum conditioning. The MCO will be placed in interim storage in the CSB following conditioning and disposition

Nuclear fuel pellet loading apparatus

International Nuclear Information System (INIS)

Gerkey, K.S.

1979-01-01

An automatic apparatus for loading a predetermined amount of nuclear fuel pellets into a nuclear fuel element to be used in a nuclear reactor is described. The apparatus consists of a vibratory bed capable of supporting corrugated trays containing rows of nuclear fuel pellets and arranged in alignment with the open ends of several nuclear fuel elements. A sweep mechanism is arranged above the trays and serves to sweep the rows of fuel pellets onto the vibratory bed and into the fuel element. A length detecting system, in conjunction with a pellet stopping mechanism, is also provided to assure that a predetermined amount of nuclear fuel pellets are loaded into each fuel element

Fuel assemblies

International Nuclear Information System (INIS)

Nakatsuka, Masafumi.

1979-01-01

Purpose: To prevent scattering of gaseous fission products released from fuel assemblies stored in an fbr type reactor. Constitution; A cap provided with means capable of storing gas is adapted to amount to the assembly handling head, for example, by way of threading in a storage rack of spent fuel assemblies consisting of a bottom plate, a top plate and an assembly support mechanism. By previously eliminating the gas inside of the assembly and the cap in the storage rack, gaseous fission products upon loading, if released from fuel rods during storage, are stored in the cap and do not scatter in the storage rack. (Horiuchi, T.)

Separation, storage, and disposal of krypton-85: status and projects

Energy Technology Data Exchange (ETDEWEB)

Laser, M.

1976-09-15

Despite the relatively small impact of ⁸⁵Kr to man the separation of fission krypton from the off-gas of fuel reprocessing plants must be taken into account. Combined with other advantages also in power reactor stations the retention of ⁸⁵Kr seems to be attractive. Cryogenic processes are favored worldwide, because the technology has been well proven during several decades in air liquefaction and separation plants. Relatively small modifications must be made to adjust these processes to fission gas separation plants. Some fundamental data however are necessary for the design of a plant. Besides cryogenic processes a liquid adsorption for reprocessing off-gases and charcoal adsorption processes for reactor off-gas are under discussion. The retained krypton can be stored under air or water cooling in usual pressurized steel cylinders. However, legal problems may arise. The steel cylinders can be stored in engineered storage facilities for an intermediate period or finally. In Europe, however, the final storage will be questionable. Therefore, the dumping of ⁸⁵Kr into the deep sea has been proposed. For this reason a revision of the London Convention is necessary, because the dumping of ⁸⁵/Kr has not been specified. The IAEA as competent authority is asked to define the conditions for dumping. Injection of krypton containing gases into porous geologic strata may also be possible, if a very small release can be guaranteed.

Flash Foods' Job Creation and Petroleum Independence with E85

Energy Technology Data Exchange (ETDEWEB)

Walk, Steve [Protec Fuel Management LLC, Boca Raton, FL (United States)

2016-11-21

Protec Fuel Management project objectives are to help design, build, provide, promote and supply biofuels for the greater energy independence, national security and domestic economic growth through job creations, infrastructure projects and supply chain business stimulants.

77 FR 17568 - Notice of Receipt of Petition for Decision That Nonconforming 2005 Ifor Williams LM85G Trailers...

Science.gov (United States)

2012-03-26

...-0030, Notice 1] Notice of Receipt of Petition for Decision That Nonconforming 2005 Ifor Williams LM85G... Safety Administration (NHTSA) of a petition for a decision that 2005 Ifor Williams LM85G trailers that... capable of being altered to comply with, all applicable FMVSS based on destructive test data or such other...

Retention of 60Co, 85Sr and 137Cs on inorganic ion exchangers

International Nuclear Information System (INIS)

Dozol, J.F.; Eymard, S.

1983-11-01

The aim of the study is the treatment of radioactive wastes produced in plutonium fuel fabrication or in spent fuel reprocessing by inorganic ion exchangers for ultimate storage. This rapport, gives the distribution coefficients of 60 Co, 85 Sr, 137 Cs (in sodium nitrate medium at different concentration of sodium: .23g/l, 1 g/l, 10 g/l) obtained with different inorganic exchangers: titanium oxyde, sodium titanate, sodium zirconate, sodium niobate, sodium tantalate, titanium phosphate, zirconium phosphate, ammonium phosphotungstate in zirconium phosphate, polyantimonic acid amorphous aluminosilicate and several zeolites (ZBS 15 from OXYMIN, ZEOLON 400, ZEOLON 500, ZEOLON 900 from Norton, IE 96, A 51, 13 X from Union Carbide) [fr

Factors affecting diesel fuel degradation using a bespoke high-pressure fuel system rig

OpenAIRE

Gopalan, Kesavan; Smith, Christopher; Pickering, Simon; Chuck, Christopher; Bannister, Christopher

2018-01-01

Recently, there has been automotive industry-wide impetus to reduce overall diesel vehicle emissions and fuel consumption by increasing fuel injection pressures within common rail systems. Many production fuel injection systems are now capable of delivering rail pressures of 1800-2000 bar with those able to achieve 3000 bar under development. In addition, there has been a gradual increase in the permitted FAME content in EN590 diesel from 5% to 7% with further increases to 10% proposed. With ...

Fuel Chemistry Division: progress report for 1987

International Nuclear Information System (INIS)

1990-01-01

The progress of research and development activities of the Fuel Chemistry Division of the Bhabha Atomic Research Centre, Bombay, during 1987 is reported in the form of summaries which are arranged under the headings: Fuel Development Chemistry, Chemistry of Actinides, Chemical Quality Control of Fuel, and Studies related to Nuclear Material Accounting. A list of publications by the members of the Division during the report period is given at the end of the report. (M.G.B.). refs., 15 figs., 85 tabs

CFD thermal-hydraulic analysis of a CANDU fuel channel

International Nuclear Information System (INIS)

Catana, A.; Prisecaru, I.; Dupleac, D.; Danila, N.

2009-01-01

This paper presents the numerical investigation of a CANDU fuel channel using CFD (Computational fluid dynamics) methodology approach. Limited computer power available at Bucharest University POLITEHNICA forced the authors to analyse only segments of fuel channel namely the significant ones: fuel bundle junctions with adjacent segments, fuel bundle spacer planes with adjacent segments, regular segments of fuel bundles. The computer code used is FLUENT. Fuel bundles contained in pressure tubes forms a complex flow domain. The flow is characterized by high turbulence and in some parts of fuel channel also by multi-phase flow. The flow in the fuel channel has been simulated by solving the equations for conservation of mass and momentum. For turbulence modelling the standard k-e model is employed although other turbulence models can be used as well. In this paper we do not consider heat generation and heat transfer capabilities of CFD methods. Since we consider only some relatively short segments of a CANDU fuel channel we can assume, for this starting stage, that heat transfer is not very important for these short segments of fuel channel. The boundary conditions for CFD analysis are provided by system and sub-channel analysis. In this paper the discussion is focused on some flow parameters behaviour at the bundle junction, spacer's plane configuration, etc. In this paper we present results for Standard CANDU 6 Fuel Bundles as a basis for CFD thermal-hydraulic analysis of INR proposed SEU43 and other new nuclear fuels. (authors)

Suppression of the stellar enhancement factor and the reaction 85Rb(p,n)85Sr

International Nuclear Information System (INIS)

Rauscher, T.; Kiss, G. G.; Gyuerky, Gy.; Simon, A.; Fueloep, Zs.; Somorjai, E.

2009-01-01

It is shown that a Coulomb suppression of the stellar enhancement factor occurs in many endothermic reactions at and far from stability. Contrary to common assumptions, reaction measurements for astrophysics with minimal impact of stellar enhancement should be preferably performed for those reactions instead of their reverses, despite of their negative Q value. As a demonstration, the cross section of the astrophysically relevant 85 Rb(p,n) 85 Sr reaction has been measured by activation between 2.16≤E c.m. ≤3.96 MeV and the astrophysical reaction rates at p process temperatures for (p,n) as well as (n,p) are directly inferred from the data. Additionally, our results confirm a previously derived modification of a global optical proton potential. The presented arguments are also relevant for other α- and proton-induced reactions in the p, rp, and νp processes.

The Mycobacterium leprae antigen 85 complex gene family: identification of the genes for the 85A, 85C, and related MPT51 proteins

NARCIS (Netherlands)

Rinke de Wit, T. F.; Bekelie, S.; Osland, A.; Wieles, B.; Janson, A. A.; Thole, J. E.

1993-01-01

The genes for two novel members (designated 85A and 85C) of the Mycobacterium leprae antigen 85 complex family of proteins and the gene for the closely related M. leprae MPT51 protein were isolated. The complete DNA sequence of the M. leprae 85C gene and partial sequences of the 85A and MPT51 genes

Fuel failure detection in operating reactors

International Nuclear Information System (INIS)

Seigel, B.; Hagen, H.H.

1977-12-01

Activity detectors in commercial BWRs and PWRs are examined to determine their capability to detect a small number of fuel rod failures during reactor operation. The off-gas system radiation monitor in a BWR and the letdown line radiation monitor in a PWR are calculated to have this capability, and events are cited that support this analysis. Other common detectors are found to be insensitive to small numbers of fuel failures. While adequate detectors exist for normal and transient operation, those detectors would not perform rapidly enough to be useful during accidents; in most accidents, however, primary system sensors (pressure, temperature, level) would provide adequate warning. Advanced methods of fuel failure detection are mentioned

Detection Capability Evaluation on Chang'e-5 Lunar Mineralogical Spectrometer (LMS)

Science.gov (United States)

Liu, Bin; Ren, Xin; Yan, Wei; Xu, Xuesen; Cai, Tingni; Liu, Dawei; Liu, Jianjun; Li, Chunlai

2016-04-01

The Chang'e-5 (CE-5) lunar sample return mission is scheduled to launch in 2017 to bring back lunar regolith and drill samples. The Chang'e-5 Lunar Mineralogical Spectrometer (LMS), as one of the three sets of scientific payload installed on the lander, is used to collect in-situ spectrum and analyze the mineralogical composition of the sampling site. It can also help to select the sampling site , and to compare the measured laboratory spectrum of returned sample with in-situ data. LMS employs acousto-optic tunable filters (AOTFs) and is composed of a VIS/NIR module (0.48μm-1.45μm) and an IR module (1.4μm -3.2μm). It has spectral resolution ranging from 3 to 25 nm, with a field of view (FOV) of 4.24°×4.24°. Unlike Chang'e-3 VIS/NIR Imaging Spectrometer (VNIS), the spectral coverage of LMS is extended from 2.4μm to 3.2μm, which has capability to identify H2O/OH absorption features around 2.7μm. An aluminum plate and an Infragold plate are fixed in the dust cover, being used as calibration targets in the VIS/NIR and IR spectral range respectively when the dust cover is open. Before launch, a ground verification test of LMS needs to be conducted in order to: 1) test and verify the detection capability of LMS through evaluation on the quality of image and spectral data collected for the simulated lunar samples; and 2) evaluate the accuracy of data processing methods by the simulation of instrument working on the moon. The ground verification test will be conducted both in the lab and field. The spectra of simulated lunar regolith/mineral samples will be collected simultaneously by the LMS and two calibrated spectrometers: a FTIR spectrometer (Model 102F) and an ASD FieldSpec 4 Hi-Res spectrometer. In this study, the results of the LMS ground verification test will be reported including the evaluation on the LMS spectral and image data quality, mineral identification and inversion ability, accuracy of calibration and geometric positioning .

Program on MOX fuel utilization in light water reactors

International Nuclear Information System (INIS)

Kenda, Hirofumi

2000-01-01

MOX fuel utilization program by the Japanese electric power companies was released in February, 1997. Principal philosophy for MOX fuel design is that MOX fuel shall be compatible with Uranium fuel and behavior of core loaded with MOX fuel shall be similar to that of conventional core. MOX fuel is designed so that geometry and nuclear capability of MOX fuel are equivalent to Uranium fuel. (author)

Size and transportation capabilities of the existing US cask fleet

International Nuclear Information System (INIS)

Danese, F.L.; Johnson, P.E.; Joy, D.S.

1990-01-01

This study investigates the current spent nuclear fuel cask fleet capability in the United States. In addition, it assesses the degree to which the current fleet would be available, as a contingency, until proposed Office of Civilian Radioactive Waste Management casks become operational. A limited fleet of ten spent fuel transportation casks is found to be readily available for use in Federal waste management efforts over the next decade

Fuel characteristics pertinent to the design of aircraft fuel systems, Supplement I : additional information on MIL-F-7914(AER) grade JP-5 fuel and several fuel oils

Science.gov (United States)

Barnett, Henry C; Hibbard, Robert R

1953-01-01

Since the release of the first NACA publication on fuel characteristics pertinent to the design of aircraft fuel systems (NACA-RM-E53A21), additional information has become available on MIL-F7914(AER) grade JP-5 fuel and several of the current grades of fuel oils. In order to make this information available to fuel-system designers as quickly as possible, the present report has been prepared as a supplement to NACA-RM-E53A21. Although JP-5 fuel is of greater interest in current fuel-system problems than the fuel oils, the available data are not as extensive. It is believed, however, that the limited data on JP-5 are sufficient to indicate the variations in stocks that the designer must consider under a given fuel specification. The methods used in the preparation and extrapolation of data presented in the tables and figures of this supplement are the same as those used in NACA-RM-E53A21.

Wastes from selected activities in two light-water reactor fuel cycles

International Nuclear Information System (INIS)

Palmer, C.R.; Hill, O.F.

1980-07-01

This report presents projected volumes and radioactivities of wastes from the production of electrical energy using light-water reactors (LWR). The projections are based upon data developed for a recent environmental impact statement in which the transuranic wastes (i.e., those wastes containing certain long-lived alpha emitters at concentrations of at least 370 becquerels, or 10 nCi, per gram of waste) from fuel cycle activities were characterized. In addition, since the WG.7 assumed that all fuel cycle wastes except mill tailings are placed in a mined geologic repository, the nontransuranic wastes from several activities are included in the projections reported. The LWR fuel cycles considered are the LWR, once-through fuel cycle (Strategy 1), in which spent fuel is packaged in metal canisters and then isolated in geologic formations; and the LWR U/Pu recycle fuel cycle (Strategy 2), wherein spent fuel is reprocessed for recovery and recycle of uranium and plutonium in LWRs. The wastes projected for the two LWR fuel cycles are summarized. The reactor operations and decommissioning were found to dominate the rate of waste generation in each cycle. These activities account for at least 85% of the fuel cycle waste volume (not including head-end wastes) when normalized to per unit electrical energy generated. At 10 years out of reactor, however, spent fuel elements in Strategy 1 represent 98% of the fuel cycle activity but only 4% of the volume. Similarly, the packaged high-level waste, fuel hulls and hardware in Strategy 2 concentrate greater than 95% of the activity in 2% of the waste volume

Nuclear and thermal power plant power ramping capability

International Nuclear Information System (INIS)

Golovach, E.A.

1983-01-01

The possibilities of step power increase by NPP and TPP units under emergency conditions of power grids operation are considered. The data analysis has shown that power units ramping capability with WWER-440, WWER-1000 and RBMK-1000 reactors is higher than that of 300 MW power units on fossil fuel, at the initial time interval (0-30 s). These NPP power units satisfy as to ramping capability the energy system requirements. Higher NPP power units ramping capability is explained by the fact that relative pressure before turbine valves is decreased less than in straight-through boilers while the steam volumes time constant of steam separator-superheaters is less than that of intermediate superheatings. Higher power unit ramping capability with WWER-440 and RBMK-1000 reactors as compared with the WWER-1000 reactor is pointed out as well as the increase of WWER-1000 power unit capability using high-speed turbines

Physical model of the nuclear fuel cycle simulation code SITON

International Nuclear Information System (INIS)

Brolly, Á.; Halász, M.; Szieberth, M.; Nagy, L.; Fehér, S.

2017-01-01

Finding answers to main challenges of nuclear energy, like resource utilisation or waste minimisation, calls for transient fuel cycle modelling. This motivation led to the development of SITON v2.0 a dynamic, discrete facilities/discrete materials and also discrete events fuel cycle simulation code. The physical model of the code includes the most important fuel cycle facilities. Facilities can be connected flexibly; their number is not limited. Material transfer between facilities is tracked by taking into account 52 nuclides. Composition of discharged fuel is determined using burnup tables except for the 2400 MW thermal power design of the Gas-Cooled Fast Reactor (GFR2400). For the GFR2400 the FITXS method is used, which fits one-group microscopic cross-sections as polynomial functions of the fuel composition. This method is accurate and fast enough to be used in fuel cycle simulations. Operation of the fuel cycle, i.e. material requests and transfers, is described by discrete events. In advance of the simulation reactors and plants formulate their requests as events; triggered requests are tracked. After that, the events are simulated, i.e. the requests are fulfilled and composition of the material flow between facilities is calculated. To demonstrate capabilities of SITON v2.0, a hypothetical transient fuel cycle is presented in which a 4-unit VVER-440 reactor park was replaced by one GFR2400 that recycled its own spent fuel. It is found that the GFR2400 can be started if the cooling time of its spent fuel is 2 years. However, if the cooling time is 5 years it needs an additional plutonium feed, which can be covered from the spent fuel of a Generation III light water reactor.

Preliminary safety evaluation of a commercial-scale krypton-85 encapsulation facility

International Nuclear Information System (INIS)

Christensen, A.B.; Tanner, J.E.; Knecht, D.A.

1980-01-01

This paper demonstrates that a commercial-scale facility for encapsulating krypton-85 in zeolite-5A or glass at a 2000 MTHM per year nuclear fuel reprocessing plant can be designed to contain fragments and the 340 to 850 kCi krypton-85 inventory from an assumed catastrophic failure of the high pressure vessel. The vessel failure was assumed as a worst case and was not based on a detailed design evaluation or operating experience. The process design is based on existing commercial hot isostatic pressing technology operated at up to 40 times the scale required for krypton encapsulation. From the calculated process gas inventory in the pressure vessel and vessel design, the maximum explosive energy of 8.4 kg TNT and resulting vessel plug and fragment velocities were calculated. The facility Containment Cell housing the high pressure vessel was designed to contain the gases, fragments, and the shock wave energy calculated for a hypothetical vessel failure. The Access Cell located directly above the Containment Cell was designed to be a tertiary confinement of krypton-85, should the access hatch be breached. 3 figures, 2 tables

Geography of Existing and Potential Alternative Fuel Markets in the United States

Energy Technology Data Exchange (ETDEWEB)

Johnson, C.; Hettinger, D.

2014-11-01

When deploying alternative fuels, it is paramount to match the right fuel with the right location, in accordance with local market conditions. We used six market indicators to evaluate the existing and potential regional market health for each of the five most commonly deployed alternative fuels: electricity (used by plug-in electric vehicles), biodiesel (blends of B20 and higher), E85 ethanol, compressed natural gas (CNG), and propane. Each market indicator was mapped, combined, and evaluated by industry experts. This process revealed the weight the market indicators should be given, with the proximity of fueling stations being the most important indicator, followed by alternative fuel vehicle density, gasoline prices, state incentives, nearby resources, and finally, environmental benefit. Though markets vary among states, no state received 'weak' potential for all five fuels, indicating that all states have an opportunity to use at least one alternative fuel. California, Illinois, Indiana, Pennsylvania, and Washington appear to have the best potential markets for alternative fuels in general, with each sporting strong markets for four of the fuels. Wyoming showed the least potential, with weak markets for all alternative fuels except for CNG, for which it has a patchy market. Of all the fuels, CNG is promising in the greatest number of states--largely because freight traffic provides potential demand for many far-reaching corridor markets and because the sources of CNG are so widespread geographically.

A conceptual redesign of an Inter-Building Fuel Transfer Cask

International Nuclear Information System (INIS)

Klann, R.T.; Picker, B.A. Jr.

1993-01-01

The Inter-Building Fuel Transfer Cask, referred to as the IBC, is a lead shielded cask for transporting subassemblies between buildings on the Argonne National Laboratory-West site near Idaho Falls, Idaho. The cask transports both newly fabricated and spent reactor subassemblies between the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF) and the Hot Fuel Examination Facility (HFEF). The IBC will play a key role in the Integral Fast Reactor (IFR) fuel recycling demonstration project. This report discusses a conceptual redesign of the IBC which has been performed. The objective of the conceptual design was to increase the passive heat removal capabilities, reduce the personnel radiation exposure and incorporate enhanced safety features into the design. The heat transfer, radiation and thermal-hydraulic properties of the IBC were analytically modelled to determine the principal factors controlling the desip. The scoping studies that were performed determined the vital physical characteristics (i.e., size, shielding, pumps, etc.) of the MC conceptual design

Recent TMX-U central cell heating and fueling experiments

International Nuclear Information System (INIS)

Hooper, E.B. Jr.; Barter, J.; Dimonte, G.; Falabella, S.; Molvik, A.W.; Pincosy, P.; Turner, W.C.

1986-01-01

Recent experiments have begun to test new methods of heating and fueling of the TMX-U central cell plasma. Heating is with ICRH and 2kV neutral beams. Fueling is by the 2kV beams and by gas puffing. The ICRH system used for fundamental-frequency slow-wave heating consists of two double half-turn antennas, with one on each side of the central cell midplane at mirror ratios of 1:3 and 1:5. Gas fueling is between these two antennas to ensure that recently ionized particles pass through an ICRH resonance before entering the thermal barrier and cells. In recent gas-fed experiments with 100 to 200kW power on each antenna, the end loss temperature was measured to increase from 30eV to above 150eV with perpendicular (cc) temperatures of >500eV. The TMX-U central cell has been equipped with 10 low energy neutral-beam injectors (LENI). These beams are designed to operate at 2kV (net) accel-voltage and deliver 17 atom amperes each to the TMX-U plasma. This low energy was selected to improve trapping (relative to higher energy) on the initial ICRH heated plasma (2X10/sup 12/ cm/sup -3/). At 2keV the beams are predicted to be capable of building up and fueling to 10/sup 13/ cm/sup -3/ density, with ion-ion scattering providing a warm, isotropic ion component in the central cell

East African Medical Journal - Vol 85, No 3 (2008)

African Journals Online (AJOL)

Congenital Lymphoedema, Bronchiectasis And Seizure: Case Report · EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT · DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT. S Semiz, E Dagdeviren, H Ergin, I Kilic, M Cimbis, E Semiz, 145-149. http://dx.doi.org/10.4314/eamj.v85i3.9635 ...

Energy management strategy based on fuzzy logic for a fuel cell hybrid bus

Science.gov (United States)

Gao, Dawei; Jin, Zhenhua; Lu, Qingchun

Fuel cell vehicles, as a substitute for internal-combustion-engine vehicles, have become a research hotspot for most automobile manufacturers all over the world. Fuel cell systems have disadvantages, such as high cost, slow response and no regenerative energy recovery during braking; hybridization can be a solution to these drawbacks. This paper presents a fuel cell hybrid bus which is equipped with a fuel cell system and two energy storage devices, i.e., a battery and an ultracapacitor. An energy management strategy based on fuzzy logic, which is employed to control the power flow of the vehicular power train, is described. This strategy is capable of determining the desired output power of the fuel cell system, battery and ultracapacitor according to the propulsion power and recuperated braking power. Some tests to verify the strategy were developed, and the results of the tests show the effectiveness of the proposed energy management strategy and the good performance of the fuel cell hybrid bus.

Energy management strategy based on fuzzy logic for a fuel cell hybrid bus

Energy Technology Data Exchange (ETDEWEB)

Gao, Dawei; Jin, Zhenhua; Lu, Qingchun [State Key Laboratory of Automotive Safety and Energy, Tsinghua University, Beijing 100084 (China)

2008-10-15

Fuel cell vehicles, as a substitute for internal-combustion-engine vehicles, have become a research hotspot for most automobile manufacturers all over the world. Fuel cell systems have disadvantages, such as high cost, slow response and no regenerative energy recovery during braking; hybridization can be a solution to these drawbacks. This paper presents a fuel cell hybrid bus which is equipped with a fuel cell system and two energy storage devices, i.e., a battery and an ultracapacitor. An energy management strategy based on fuzzy logic, which is employed to control the power flow of the vehicular power train, is described. This strategy is capable of determining the desired output power of the fuel cell system, battery and ultracapacitor according to the propulsion power and recuperated braking power. Some tests to verify the strategy were developed, and the results of the tests show the effectiveness of the proposed energy management strategy and the good performance of the fuel cell hybrid bus. (author)

Fire spread probabilities for experimental beds composed of mixedwood boreal forest fuels

Science.gov (United States)

M.B. Dickinson; E.A. Johnson; R. Artiaga

2013-01-01

Although fuel characteristics are assumed to have an important impact on fire regimes through their effects on extinction dynamics, limited capabilities exist for predicting whether a fire will spread in mixedwood boreal forest surface fuels. To improve predictive capabilities, we conducted 347 no-wind, laboratory test burns in surface fuels collected from the mixed-...

NASA fuel cell applications for space: Endurance test results on alkaline fuel cell electrolyzer components

International Nuclear Information System (INIS)

Sheibley, D.W.

1984-01-01

Fuel cells continue to play a major role in manned spacecraft power generation. The Gemini and Apollo programs used fuel cell power plants as the primary source of mission electrical power, with batteries as the backup. The current NASA use for fuel cells is in the Orbiter program. Here, low temperature alkaline fuel cells provide all of the on-board power with no backup power source. Three power plants per shipset are utilized; the original power plant contained 32-cell substacks connected in parallel. For extended life and better power performance, each power plant now contains three 32-cell substacks connected in parallel. One of the possible future applications for fuel cells will be for the proposed manned Space Station in low earth orbit (LEO)(1, 2, 3). By integrating a water electrolysis capability with a fuel cell (a regenerative fuel cell system), a multikilowatt energy storage capability ranging from 35 kW to 250 kW can be achieved. Previous development work on fuel cell and electrolysis systems would tend to minimize the development cost of this energy storage system. Trade studies supporting initial Space Station concept development clearly show regenerative fuel cell (RFC) storage to be superior to nickel-cadmium and nickel-hydrogen batteries with regard to subsystem weight, flexibility in design, and integration with other spacecraft systems when compared for an initial station power level ranging from 60 kW to 75 kW. The possibility of scavenging residual O 2 and H 2 from the Shuttle external tank for use in fuel cells for producing power also exists

Test system design for Hardware-in-Loop evaluation of PEM fuel cells and auxiliaries

Energy Technology Data Exchange (ETDEWEB)

Randolf, Guenter; Moore, Robert M. [Hawaii Natural Energy Institute, University of Hawaii, Honolulu, HI (United States)

2006-07-14

In order to evaluate the dynamic behavior of proton exchange membrane (PEM) fuel cells and their auxiliaries, the dynamic capability of the test system must exceed the dynamics of the fastest component within the fuel cell or auxiliary component under test. This criterion is even more critical when a simulated component of the fuel cell system (e.g., the fuel cell stack) is replaced by hardware and Hardware-in-Loop (HiL) methodology is employed. This paper describes the design of a very fast dynamic test system for fuel cell transient research and HiL evaluation. The integration of the real time target (which runs the simulation), the test stand PC (that controls the operation of the test stand), and the programmable logic controller (PLC), for safety and low-level control tasks, into one single integrated unit is successfully completed. (author)

Fuel consumption and emission on fuel mixer low-grade bioethanol fuelled motorcycle

Directory of Open Access Journals (Sweden)

Abikusna Setia

2017-01-01

Full Text Available Bioethanol is currently used as an alternative fuel for gasoline substitute (fossil fuel because it can reduce the dependence on fossil fuel and also emissions produced by fossil fuel which are CO2, HO, NOx. Bioethanol is usually used as a fuel mixed with gasoline with certain comparison. In Indonesia, the usage is still rare. Bioethanol that is commonly used is bioethanol anhydrous 99.5%. In the previous studies, bioethanol was distilled from low to high grade to produce ethanol anhydrous. But the result is only able to reach 95% or ethanol hydrous. This study is objected to design a simple mechanism in the mixing of bioethanol hydrous with the gasoline using a fuel mixer mechanism. By this mechanism, the fuel consumption and the resulting emissions from combustion engine can be analyzed. The fuel blend composition is prepared as E5, E10, and E15/E20, the result of fuel consumption and emission will be compared with pure gasoline. The using of bioethanol hydrous as a fuel mixture was tended to produce more stable bioethanol fuel consumption. However, the utilization of the mixture was found able to reduce the exhaust emissions (CO, HC, and NOx.

Banyan latex: a facile fuel for the multifunctional properties of MgO nanoparticles prepared via auto ignited combustion route

International Nuclear Information System (INIS)

Anil Kumar, M R; Nagaswarupa, H P; Gurushantha, K; Pratapkumar, C; Prashantha, S C; Shashishekar, T R; Anantharaju, K S; Nagabhushana, H; Sharma, S C; Vidya, Y S; Daruka Prasad, B; Vivek Babu, C S; Vishnu Mahesh, K R

2015-01-01

MgO nanoparticles (MNPs) were prepared by a solution combustion route using banyan tree (BT) latex and glycine as fuels. The powder x-ray diffraction results indicate the formation of a single cubic phase and the crystallite size obtained from transmission electron microscopy was found to be ∼10–15 nm. Scanning electron microscopy result reveals spherical-shaped particles obtained with BT latex. However, in a chemical route, porous and agglomerated particles were obtained. The energy band gap of MNPs obtained using BT latex and a chemical route were found to be in the range 4.85–5.0 eV. Photoluminescence peaks observed at 473, 514, and 588 nm when excited at 433 nm, which were attributed to surface defects. The enhanced photocatalytic activities of spherical MgO were due to smaller crystallite size, higher surface defects, dye sensitization, and capability to reduce the electron–hole pair recombination. Further, green-synthesized MNPs exhibit superior antifungal activity against various plant pathogens. The present studies demonstrated a green engineering route for the synthesis of multifunctional MNPs using BT latex. (paper)

Race for a Better Fuel Begins with NREL Researchers | News | NREL

Science.gov (United States)

produced at NREL registers an estimated octane rating of 107. NREL's fuel is better suited for race cars by Dennis Schroeder Look! Up in the Sky! In addition to race cars, the 85% triptane could find a use Race for a Better Fuel Begins with NREL Researchers Race for a Better Fuel Begins with NREL

Development of Army Fire-Resistant Diesel Fuel.

Science.gov (United States)

1979-12-01

45 C C Service Station Fuel Semple 85 A 75B AB C C 95 95 Service Station Fuel Sample 8 00 A -7B\\ A -7s C Refiney Fu UNMODIFIED* MODIFIED* SURFACTANT...Change in Brake Power, % -11.2 Change in Brake Specific Volumetric Fuel Consumption, % +17.7 Change in Thermal Efficiency of Work Cycle, abs % - 1.6...and unmodified surfactant) 2. Cladosporium resinae . 3. ASTM mixed fungal spore inoculum (only with item A5 and with item A4 made with deionized water

Frações de zinco em solo arenoso e suas relações com disponibilidade para Cynodon spp cv. Tifton-85 Zinc fractions in a sandy soil and its relations with availability to Cynodon spp cv. Tifton-85

Directory of Open Access Journals (Sweden)

E. M. André

2003-06-01

Full Text Available Para avaliar um esquema de fracionamento de zinco em Argissolo arenoso e suas relações com a disponibilidade de Zn para Cynodon spp cv. Tifton-85, realizou-se um experimento em casa de vegetação, em esquema fatorial 5 x 2 x 2 (5 doses de Zn, 2 doses de calcário e 2 épocas de amostragem, em delineamento inteiramente casualizado, com três repetições. As doses de Zn foram de 0; 2,5; 5,0; 7,5 e 10 mg dm-3; metade dos vasos não recebeu calagem (V = 42 % e metade recebeu a calagem com vistas em elevar o índice de saturação por bases a 70 %. As épocas de amostragem foram 30 e 150 dias após aplicação de Zn, respectivamente, antes do plantio e depois do 3º corte de Tifton-85. A aplicação de Zn resultou em aumento significativo do elemento nas frações: trocável, óxidos de Mn, matéria orgânica e óxidos de Fe. O Zn ligado aos óxidos de Mn aumentou significativamente com a calagem. Após 150 dias de experimentação, houve diminuição do Zn trocável, ligado aos óxidos de Mn, à matéria orgânica e aos óxidos de Fe, e aumento na fração residual. A distribuição de Zn nas frações do solo foi: residual > óxidos de Fe > óxidos de Mn > trocável > matéria orgânica. As relações entre as características estudadas mostraram que tanto o Zn-DTPA quanto o Zn trocável, ligado à M.O. e aos óxidos de Mn, foram eficientes para representar o Zn absorvido pela planta.To evaluate a fractionation scheme for Zn in a sandy soil (Ultisol and its relation with Zn availability for Cynodon spp cv. Tifton-85, an experiment was carried out in greenhouse, with a factorial scheme (5 doses of zinc, 2 doses of lime and 2 times of sampling, in a completely randomized block design, with three replications. The doses of Zn were: 0; 2.5; 5.0; 7.5 and 10 mg dm-3; half of the pots did not received liming (V = 42% and, in the other half, liming was done to increase the base saturation index to 70%. The sampling times were 30 and 150 days after Zn