National Library of Energy BETA

Sample records for fossil fuels nuclear

  1. N.R. 20 FOSSIL-FUELED POWER PLANTS; 21 SPECIFIC NUCLEAR REACTORS...

    Office of Scientific and Technical Information (OSTI)

    20 FOSSIL-FUELED POWER PLANTS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 14 SOLAR ENERGY; 15 GEOTHERMAL ENERGY; GEOTHERMAL POWER PLANTS; COMPUTERIZED SIMULATION; HEAT...

  2. Fossil fuels -- future fuels

    SciTech Connect (OSTI)

    1998-03-01

    Fossil fuels -- coal, oil, and natural gas -- built America`s historic economic strength. Today, coal supplies more than 55% of the electricity, oil more than 97% of the transportation needs, and natural gas 24% of the primary energy used in the US. Even taking into account increased use of renewable fuels and vastly improved powerplant efficiencies, 90% of national energy needs will still be met by fossil fuels in 2020. If advanced technologies that boost efficiency and environmental performance can be successfully developed and deployed, the US can continue to depend upon its rich resources of fossil fuels.

  3. Technical considerations in repowering a nuclear plant for fossil fueled operation

    SciTech Connect (OSTI)

    Patti, F.J.

    1996-03-01

    Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today`s world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal.

  4. Environmental review for the conversion of Bellefonte Nuclear Plant to fossil fuel

    SciTech Connect (OSTI)

    Carter, R.; Rucker, H.; Summers, R.

    1998-07-01

    The Tennessee Valley Authority recently issued for public review a Draft Environmental Impact Statement for the conversion of the unfinished Bellefonte Nuclear Plant to fossil fuel. The DEIS was structured to support three tiers of decision making. Tier 1 is to decide between the No-Action Alternative, which is to leave Bellefonte as a partially completed nuclear plant into the indefinite future, and the Proposed Action Alternative, which is to proceed with converting Bellefonte to fossil fuel. Tier 2 is to select one of five conversion options. In the DEIS, TVA indicated no preference among the five competing fossil conversion options. The five conversion pathways would fully repower the plant consistent with fossil fuel availability, would use commercially ready systems and technologies and be designed to fully utilize the capacity of transmission lines serving Bellefonte. Conversion options addressed were pulverized coal (PC), natural gas combined cycle (NGCC), integrated gasification combined cycle (IGCC), IGCC with joint production of electricity and chemicals, and an option, which combines elements of NGCC and IGCC with coproduction. Tier 3 involves decisions about eight sub-option choices, basically types of processes, equipment, and modes of operation, which is part of two or more conversion options. An example of a sub-option choice would be the type of gasifier that would be used in conversion options involving coal or petroleum coke gasification. Other sub-option choices addressed in the DEIS were natural gas pipeline corridors; fuels, feedstocks, and by-products transportation modes; types of combustion turbines; solid fuels; types of boilers for conventional coal-fired options; chemical production mixes; and modes of onsite solid fuel conveyance. The impact of constructing and operating each proposed fossil conversion option at Bellefonte were evaluated for 18 environmental resource and economic categories.

  5. Long-term tradeoffs between nuclear- and fossil-fuel burning

    SciTech Connect (OSTI)

    Krakowski, R.A.

    1996-12-31

    A global energy/economics/environmental (E{sup 3}) model has been adapted with a nuclear energy/materials model to understand better {open_quotes}top-level{close_quotes}, long-term trade offs between civilian nuclear power, nuclear-weapons proliferation, fossil-fuel burning, and global economic welfare. Using a {open_quotes}business-as-usual{close_quotes} (BAU) point-of-departure case, economic, resource, proliferation-risk implications of plutonium recycle in LAIRs, greenhouse-gas-mitigating carbon taxes, and a range of nuclear energy costs (capital and fuel) considerations have been examined. After describing the essential elements of the analysis approach being developed to support the Los Alamos Nuclear Vision Project, preliminary examples of parametric variations about the BAU base-case scenario are presented. The results described herein represent a sampling from more extensive results collected in a separate report. The primary motivation here is: (a) to compare the BAU basecase with results from other studies; (b) to model on a regionally resolved global basis long-term (to year {approximately}2100) evolution of plutonium accumulation in a variety of forms under a limited range of fuel-cycle scenarios; and (c) to illustrate a preliminary connectivity between risks associated with nuclear proliferation and fossil-fuel burning (e.g., greenhouse-gas accumulations).

  6. Development of Nuclear Renewable Oil Shale Systems for Flexible Electricity and Reduced Fossil Fuel Emissions

    SciTech Connect (OSTI)

    Daniel Curtis; Charles Forsberg; Humberto Garcia

    2015-05-01

    We propose the development of Nuclear Renewable Oil Shale Systems (NROSS) in northern Europe, China, and the western United States to provide large supplies of flexible, dispatchable, very-low-carbon electricity and fossil fuel production with reduced CO2 emissions. NROSS are a class of large hybrid energy systems in which base-load nuclear reactors provide the primary energy used to produce shale oil from kerogen deposits and simultaneously provide flexible, dispatchable, very-low-carbon electricity to the grid. Kerogen is solid organic matter trapped in sedimentary shale, and large reserves of this resource, called oil shale, are found in northern Europe, China, and the western United States. NROSS couples electricity generation and transportation fuel production in a single operation, reduces lifecycle carbon emissions from the fuel produced, improves revenue for the nuclear plant, and enables a major shift toward a very-low-carbon electricity grid. NROSS will require a significant development effort in the United States, where kerogen resources have never been developed on a large scale. In Europe, however, nuclear plants have been used for process heat delivery (district heating), and kerogen use is familiar in certain countries. Europe, China, and the United States all have the opportunity to use large scale NROSS development to enable major growth in renewable generation and either substantially reduce or eliminate their dependence on foreign fossil fuel supplies, accelerating their transitions to cleaner, more efficient, and more reliable energy systems.

  7. DOE - Fossil Energy: How Fossil Fuels Were Formed

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fossil Fuel Formation Fossil Energy Study Guides How Fossil Fuels were Formed Contrary to what many people believe, fossil fuels are not the remains of dead dinosaurs. In fact,...

  8. No Fossil Fuel - Kingston | Open Energy Information

    Open Energy Info (EERE)

    Fossil Fuel - Kingston Jump to: navigation, search Name No Fossil Fuel - Kingston Facility No Fossil Fuel - Kingston Sector Wind energy Facility Type Commercial Scale Wind Facility...

  9. Nuclear Energy R&D Imperative 3: Enable a Transition Away from Fossil Fuel in the Transportation and Industrial Sectors

    SciTech Connect (OSTI)

    David Petti; J. Stephen Herring

    2010-03-01

    As described in the Department of Energy Office of Nuclear Energy’s Nuclear Energy R&D Roadmap, nuclear energy can play a significant role in supplying energy for a growing economy while reducing both our dependence on foreign energy supplies and emissions from the burning of fossil fuels. The industrial and transportation sectors are responsible for more than half of the greenhouse gas emissions in the U.S., and imported oil supplies 70% of the energy used in the transportation sector. It is therefore important to examine the various ways nuclear energy can facilitate a transition away from fossil fuels to secure environmentally sustainable production and use of energy in the transportation and manufacturing industry sectors. Imperative 3 of the Nuclear Energy R&D Roadmap, entitled “Enable a Transition Away from Fossil Fuels by Producing Process Heat for use in the Transportation and Industrial Sectors”, addresses this need. This document presents an Implementation Plan for R&D efforts related to this imperative. The expanded use of nuclear energy beyond the electrical grid will contribute significantly to overcoming the three inter-linked energy challenges facing U.S. industry: the rising and volatile prices for premium fossil fuels such as oil and natural gas, dependence on foreign sources for these fuels, and the risks of climate change resulting from carbon emissions. Nuclear energy could be used in the industrial and transportation sectors to: • Generate high temperature process heat and electricity to serve industrial needs including the production of chemical feedstocks for use in manufacturing premium fuels and fertilizer products, • Produce hydrogen for industrial processes and transportation fuels, and • Provide clean water for human consumption by desalination and promote wastewater treatment using low-grade nuclear heat as a useful additional benefit. Opening new avenues for nuclear energy will significantly enhance our nation’s energy security through more effective utilization of our country’s resources while simultaneously providing economic stability and growth (through predictable energy prices and high value jobs), in an environmentally sustainable and secure manner (through lower land and water use, and decreased byproduct emissions). The reduction in imported oil will also increase the retention of wealth within the U.S. economy while still supporting economic growth. Nuclear energy is the only non-fossil fuel that has been demonstrated to reliably supply energy for a growing industrial economy.

  10. Advanced fossil fuel combustor

    SciTech Connect (OSTI)

    Rogers, B.

    1995-05-01

    Charged with enhancing the use of US fossil energy resources, the Morgantown Energy Technology Center (METC) is a federal Department of Energy research center that performs its own research and also manages the work of contractors. One interesting recent METC project is the effort to develop a ``multiannular swirl burner`` (MSB) for use in an advanced fossil fuel combustion system. The design is being developed by an outside contractor with funding and technical assistance from METC. Recently, EG and G Technical Services of West Virginia was asked to provide analytical support to the contractor developing the MSB. Design projects like this usually require building and testing a series of very expensive prototypes. Recent success with computational fluid dynamic (CFD) design techniques, however, have generated a great deal of excitement because of its ability to reduce research and development costs. Using FLUENT, a CFD package from Fluent Inc., EG and G was able to predict, with a high degree of accuracy, the performance of one of the MSB combustor prototypes. Furthermore, the model provided researchers with a more detailed understanding of the proposed design`s performance characteristics.

  11. Fossil fuel furnace reactor

    DOE Patents [OSTI]

    Parkinson, William J.

    1987-01-01

    A fossil fuel furnace reactor is provided for simulating a continuous processing plant with a batch reactor. An internal reaction vessel contains a batch of shale oil, with the vessel having a relatively thin wall thickness for a heat transfer rate effective to simulate a process temperature history in the selected continuous processing plant. A heater jacket is disposed about the reactor vessel and defines a number of independent controllable temperature zones axially spaced along the reaction vessel. Each temperature zone can be energized to simulate a time-temperature history of process material through the continuous plant. A pressure vessel contains both the heater jacket and the reaction vessel at an operating pressure functionally selected to simulate the continuous processing plant. The process yield from the oil shale may be used as feedback information to software simulating operation of the continuous plant to provide operating parameters, i.e., temperature profiles, ambient atmosphere, operating pressure, material feed rates, etc., for simulation in the batch reactor.

  12. Greening up fossil fuels with carbon sequestration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Greening up fossil fuels with carbon sequestration 1663 Los Alamos science and technology magazine Latest Issue:October 2015 past issues All Issues submit Greening up fossil...

  13. No Fossils in This Fuel

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Plan for Environmental Teaching GM Environmental Science Club No Fossils in This Fuel Your PlanET Sixth through Eighth Grades (Can be easily adapted to any elementary/middle school level) Ingredients: Yeast, sugar ... what are you making? Sweet rolls? Not in Science Class! You're blending these ingredients to make an innovative form of fuel! That's right ... when these two simple ingredients are mixed, the yeast  a simple, living organism  breaks the sugar down into ethyl alcohol, or

  14. Greening up fossil fuels with carbon sequestration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Greening up fossil fuels with carbon sequestration 1663 Los Alamos science and technology magazine Latest Issue:March 2016 past issues All Issues » submit Greening up fossil fuels with carbon sequestration Researchers make progress fighting climate change by capturing carbon dioxide from power plants and storing it deep underground in geological reservoirs March 25, 2013 Greening up fossil fuels with carbon sequestration Most of the world's existing energy supply is stored underground in

  15. Deactivation and Storage Issues Shared by Fossil and Nuclear Facilities

    SciTech Connect (OSTI)

    Thomas S. LaGuardia

    1998-12-31

    The deactivation of a power plant, be it nuclear or fossil fueled, requires that the facility be placed in a safe and stable condition to prevent unacceptable exposure of the public or the environment to hazardous materials until the facility can be decommissioned. The conditions at two Texas plants are examined. These plants are fossil fueled, but their conditions might be duplicated at a nuclear plant.

  16. Fossil Fuel-Generated Energy Consumption Reduction for New Federal...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Buildings Fossil Fuel-Generated Energy Consumption Reduction for New Federal Buildings and Major Renovations of Federal Buildings Document details Fossil Fuel-Generated Energy ...

  17. Synthetic fossil fuel technologies: health problems and intersociety...

    Office of Scientific and Technical Information (OSTI)

    Conference: Synthetic fossil fuel technologies: health problems and intersociety cooperation Citation Details In-Document Search Title: Synthetic fossil fuel technologies: health ...

  18. fossil fuels | OpenEI Community

    Open Energy Info (EERE)

    energy becomes more competitive with fossil fuels in OECD countries, reports of this nature can go a long way to supporting more and more development. The four new reports in...

  19. High efficiency, quasi-instantaneous steam expansion device utilizing fossil or nuclear fuel as the heat source

    SciTech Connect (OSTI)

    Claudio Filippone, Ph.D.

    1999-06-01

    Thermal-hydraulic analysis of a specially designed steam expansion device (heat cavity) was performed to prove the feasibility of steam expansions at elevated rates for power generation with higher efficiency. The steam expansion process inside the heat cavity greatly depends on the gap within which the steam expands and accelerates. This system can be seen as a miniaturized boiler integrated inside the expander where steam (or the proper fluid) is generated almost instantaneously prior to its expansion in the work-producing unit. Relatively cold water is pulsed inside the heat cavity, where the heat transferred causes the water to flash to steam, thereby increasing its specific volume by a large factor. The gap inside the heat cavity forms a special nozzle-shaped system in which the fluid expands rapidly, accelerating toward the system outlet. The expansion phenomenon is the cause of ever-increasing fluid speed inside the cavity system, eliminating the need for moving parts (pumps, valves, etc.). In fact, the subsequent velocity induced by the sudden fluid expansion causes turbulent conditions, forcing accelerating Reynolds and Nusselt numbers which, in turn, increase the convective heat transfer coefficient. When the combustion of fossil fuels constitutes the heat source, the heat cavity concept can be applied directly inside the stator of conventional turbines, thereby greatly increasing the overall system efficiency.

  20. Replace Fossil Fuels, Final Technical Report Roberts, William...

    Office of Scientific and Technical Information (OSTI)

    Crude Glycerol as Cost-Effective Fuel for Combined Heat and Power to Replace Fossil Fuels, Final Technical Report Roberts, William L 09 BIOMASS FUELS biofuels, glycerin, glycerol,...

  1. Thermal dissolution of solid fossil fuels

    SciTech Connect (OSTI)

    E.G. Gorlov

    2007-10-15

    The use of oil shales and coals in the processes of thermal dissolution is considered. It is shown that thermal dissolution is a mode of liquefaction of solid fossil fuels and can be used both independently and in combination with liquefaction of coals and processing of heavy petroleum residues.

  2. Carbon Dioxide Information Analysis Center (CDIAC)-Fossil Fuel...

    Open Energy Info (EERE)

    Fuel CO2 Emissions Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Carbon Dioxide Information Analysis Center (CDIAC)-Fossil Fuel CO2 Emissions AgencyCompany...

  3. Fossil fuel is king with energy producers

    SciTech Connect (OSTI)

    Hansen, T.

    1996-11-01

    Worldwide energy consumption is expected to double today`s levels by 2020, according to the World Energy Council. As diverse energy needs develop, fossil fuels are expected to continue to be the major source for power generation throughout the world. In the United States, utility deregulation is making low-cost fuel and power plant efficiency more important than ever. Electricity generators see both natural gas and coal as the fuels that will allow them to best meet the nation`s future energy needs. Coal will see less increase in its share of electricity generation than natural gas due to the costs associated with meeting the Clean Air Act Amendments` (CAAA) requirements. According to Organizations for Economic Cooperation Development, coal in both the United States and Europe will experience a 12 percent growth by 2010. Even with this somewhat slow growth, coal will remain the nation`s number one fuel for electricity generation well into the next century.

  4. Fossil fuel conversion--measurement and modeling

    SciTech Connect (OSTI)

    Solomon, P.R.; Smoot, L.D.; Serio, M.A.; Hamblen, D.G.; Brewster, B.S.; Radulovic, P.T.

    1994-10-01

    The main objective of this program is to understand the chemical and physical mechanisms in coal conversion processes and incorporate this knowledge in computer-aided reactor engineering technology for the purposes of development, evaluation, design, scale-up, simulation, control and feedstock evaluation in advanced coal conversion devices. To accomplish this objective, this program will: (1) provide critical data on the physical and chemical processes in fossil fuel gasifiers and combustors; (2) further develop a set of comprehensive codes; and (3) apply these codes to model various types of combustors and gasifiers (fixed-bed, transport reactor, and fluidized-bed for coal and gas turbines for natural gas).

  5. Minimising greenhouse gas emissions from fossil fuels

    SciTech Connect (OSTI)

    Freund, P.

    1997-07-01

    Combustion of fossil fuels is the main anthropogenic source of carbon dioxide, the principal greenhouse gas. Generation of electricity is the single largest user of fossil fuels, world-wide. If there is international agreement about the need to make substantial reductions in greenhouse gas emissions, then having access to suitable, effective technology would be important. This would help avoid the need for precipitate action, such as radical changes in the energy supply systems. Capture and disposal of greenhouse gases from flue gases can achieve substantial reductions in greenhouse gas emissions. This can be realized with known technology. In this paper, the range of options will be summarized and steps needed to achieve further progress will be identified. Emissions of other gases, such as methane, are also expected to influence the climate. Methane is emitted from many anthropogenic sources; the IEA Greenhouse Gas programme is investigating ways of reducing these emissions. Opportunities for abatement of methane emissions associated with coal mining will be described. Reduction in emissions from drainage gas is relatively straightforward and can, in appropriate circumstances, generate useful income for the none operator. More substantial amounts of methane are discharged in mine ventilation air but these are more difficult to deal with. In this paper, a summary will be given of recent progress in reducing methane emissions. Opportunities will be examined for further research to progress these technologies.

  6. Fossil Fuels Study Guide - High School | Department of Energy

    Energy Savers [EERE]

    Fuels Study Guide - High School Fossil Fuels Study Guide - High School PDF icon Fossil Fuels Study Guide - High School More Documents & Publications Coal Study Guide for Elementary School Coal Study Guide - Middle School Secondary Energy Infobook and Secondary Infobook Activities (19 Activities)

  7. Fossil Fuel-Generated Energy Consumption Reduction for New Federal

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Buildings and Major Renovations of Federal Buildings | Department of Energy Buildings Fossil Fuel-Generated Energy Consumption Reduction for New Federal Buildings and Major Renovations of Federal Buildings Document details Fossil Fuel-Generated Energy Consumption Reduction for New Federal Buildings and Major Renovations of Federal Buildings in a Supplemental Notice of Proposed Rulemaking. File fossilfuel.docx More Documents & Publications Fossil Fuel-Generated Energy Consumption

  8. Fossil Fuel-Generated Energy Consumption Reduction for New Federal...

    Broader source: Energy.gov (indexed) [DOE]

    the Fossil Fuel-Generated Energy Consumption Reduction for New Federal Buildings and Major Renovations of Federal Buildings in an OIRA Comparison Document. File ...

  9. Brazil-NETL Advanced Fossil Fuels Partnerships | Open Energy...

    Open Energy Info (EERE)

    Brazil-NETL Advanced Fossil Fuels Partnerships (Redirected from Brazil-NETL Cooperation) Jump to: navigation, search Logo: Brazil-NETL Cooperation Name Brazil-NETL Cooperation...

  10. Brazil-NETL Advanced Fossil Fuels Partnerships | Open Energy...

    Open Energy Info (EERE)

    Brazil-NETL Advanced Fossil Fuels Partnerships Jump to: navigation, search Logo: Brazil-NETL Cooperation Name Brazil-NETL Cooperation AgencyCompany Organization National Energy...

  11. Fossil fuel combined cycle power system

    DOE Patents [OSTI]

    Labinov, Solomon Davidovich; Armstrong, Timothy Robert; Judkins, Roddie Reagan

    2006-10-10

    A system for converting fuel energy to electricity includes a reformer for converting a higher molecular weight gas into at least one lower molecular weight gas, at least one turbine to produce electricity from expansion of at least one of the lower molecular weight gases, and at least one fuel cell. The system can further include at least one separation device for substantially dividing the lower molecular weight gases into at least two gas streams prior to the electrochemical oxidization step. A nuclear reactor can be used to supply at least a portion of the heat the required for the chemical conversion process.

  12. Fossil fuel combined cycle power generation method

    DOE Patents [OSTI]

    Labinov, Solomon D [Knoxville, TN; Armstrong, Timothy R [Clinton, TN; Judkins, Roddie R [Knoxville, TN

    2008-10-21

    A method for converting fuel energy to electricity includes the steps of converting a higher molecular weight gas into at least one mixed gas stream of lower average molecular weight including at least a first lower molecular weight gas and a second gas, the first and second gases being different gases, wherein the first lower molecular weight gas comprises H.sub.2 and the second gas comprises CO. The mixed gas is supplied to at least one turbine to produce electricity. The mixed gas stream is divided after the turbine into a first gas stream mainly comprising H.sub.2 and a second gas stream mainly comprising CO. The first and second gas streams are then electrochemically oxidized in separate fuel cells to produce electricity. A nuclear reactor can be used to supply at least a portion of the heat the required for the chemical conversion process.

  13. Spent Nuclear Fuel

    U.S. Energy Information Administration (EIA) Indexed Site

    Nuclear & Uranium Glossary › FAQS › Overview Data Status of U.S. Nuclear Outages (interactive) Summary Uranium & nuclear fuel Nuclear power plants Spent nuclear fuel International All nuclear data reports Analysis & Projections Major Topics Most popular Nuclear plants and reactors Projections Recurring Uranium All reports Browse by Tag Alphabetical Frequency Tag Cloud Spent Nuclear Fuel Release date: December 7, 2015 Next release date: Late 2018 Spent nuclear fuel data are

  14. Optimization of fossil fuel sources: An exergy approach

    SciTech Connect (OSTI)

    Camdali, U.

    2007-02-15

    We performed linear programming for optimization of fossil fuel supply in 2000 in Turkey. For this, an exergy analysis is made because the second law of thermodynamics takes into account the quality of energy as well as quantity of energy. Our analyses showed that the interfuel substitution between different fossil fuels will lead to a best energy mix of the country. The total retail price of fossil fuels can be lowered to 11.349 billion US$ from 13.012 billion US$ by increasing the domestic production of oil, lignite, and hard coal and by decreasing imports. The remaining demand can be met by natural gas imports. In conclusion, our analysis showed that a reduction of 1.663 billion US$ in fossil fuel cost can be made possible by giving more emphasis on domestic production, particularly of oil, lignite and hard coal.

  15. Sales of Fossil Fuels Produced from Federal and Indian Lands...

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    of Energy Washington, DC 20585 U.S. Energy Information Administration | Sales of Fossil Fuels Produced on Federal and Indian Lands, FY 2003 through FY 2012 ii This report...

  16. Nuclear Fuels | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Fuels Nuclear Fuels A reactor's ability to produce power efficiently is significantly affected by the composition and configuration of its fuel system. A nuclear fuel ...

  17. Fossil Fuel-Generated Energy Consumption Reduction for New Federal

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Buildings and Major Renovations of Federal Buildings OIRA Comparison Document | Department of Energy Buildings OIRA Comparison Document Fossil Fuel-Generated Energy Consumption Reduction for New Federal Buildings and Major Renovations of Federal Buildings OIRA Comparison Document Document details the Fossil Fuel-Generated Energy Consumption Reduction for New Federal Buildings and Major Renovations of Federal Buildings in an OIRA Comparison Document. File fossilfuel_compare2014.docx More

  18. Disclosure of Permitted Communication Concerning Fossil Fuel Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Consumption Reduction for New Construction and Major Renovations of Federal Buildings -- Docket No. EERE-2010-BT-STD-0031; RIN 1904-AB96 | Department of Energy Fossil Fuel Energy Consumption Reduction for New Construction and Major Renovations of Federal Buildings -- Docket No. EERE-2010-BT-STD-0031; RIN 1904-AB96 Disclosure of Permitted Communication Concerning Fossil Fuel Energy Consumption Reduction for New Construction and Major Renovations of Federal Buildings -- Docket No.

  19. Advanced nuclear fuel

    SciTech Connect (OSTI)

    Terrani, Kurt

    2014-07-14

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  20. Advanced nuclear fuel

    ScienceCinema (OSTI)

    Terrani, Kurt

    2014-07-15

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  1. Proliferation Resistant Nuclear Reactor Fuel

    SciTech Connect (OSTI)

    Gray, L W; Moody, K J; Bradley, K S; Lorenzana, H E

    2011-02-18

    Global appetite for fission power is projected to grow dramatically this century, and for good reason. Despite considerable research to identify new sources of energy, fission remains the most plentiful and practical alternative to fossil fuels. The environmental challenges of fossil fuel have made the fission power option increasingly attractive, particularly as we are forced to rely on reserves in ecologically fragile or politically unstable corners of the globe. Caught between a globally eroding fossil fuel reserve as well as the uncertainty and considerable costs in the development of fusion power, most of the world will most likely come to rely on fission power for at least the remainder of the 21st century. Despite inevitable growth, fission power faces enduring challenges in sustainability and security. One of fission power's greatest hurdles to universal acceptance is the risk of potential misuse for nefarious purposes of fissionable byproducts in spent fuel, such as plutonium. With this issue in mind, we have discussed intrinsic concepts in this report that are motivated by the premise that the utility, desirability, and applicability of nuclear materials can be reduced. In a general sense, the intrinsic solutions aim to reduce or eliminate the quantity of existing weapons usable material; avoid production of new weapons-usable material through enrichment, breeding, extraction; or employ engineering solutions to make the fuel cycle less useful or more difficult for producing weapons-usable material. By their nature, these schemes require modifications to existing fuel cycles. As such, the concomitants of these modifications require engagement from the nuclear reactor and fuel-design community to fully assess their effects. Unfortunately, active pursuit of any scheme that could further complicate the spread of domestic nuclear power will probably be understandably unpopular. Nevertheless, the nonproliferation and counterterrorism issues are paramount, and we posit that the exploration, development, and implementation of intrinsic mechanisms such as discussed here are part of a balanced approach aimed at preventing the misuse of nuclear material for nuclear-energy applications.

  2. Solubilities of heavy fossil fuels in compressed gases

    SciTech Connect (OSTI)

    Monge, A. Jr.

    1982-01-01

    Design of processes for upgrading heavy fossil fuels such as coal-derived liquids, heavy petroleum fractions, tar sands, and shale oil, requires quantitative information for equilibrium properties of the fossil fuel in the presence of compressed light gases at elevated temperatures. Presented here are methods to predict and measure solubilities of heavy fossil fuels in compressed gases in the region ambient to 100 bar and 600 K. A molecular-thermodynamic model is used to predict heavy fossil-fuel solubilities. The heavy fuel is fractionated ina spinning-band column at low pressure and high reflux; each fraction is considered to be a pseudo-component. Each fraction is characterized by one vapor-pressure datum (obtained during fractionation), elemental analysis, and proton-NMR spectra (to determine aromaticity). Liquid-phase properties are obtained from the SWAP equation for vapor pressure and from a density correlation. Vapor-phase properties are obtained using the virial equation of state with virial coefficients from Kaul's correlation. The molecular-thermodynamic model has been used to establish a design-oriented computer program for calculating heavy, fossil-fuel solubility for general application in process design and, in particular, for isobaric condensation as a function of temperature as required for design of a continuous-flow heat exchanger. A total-vaporization technique is used to measure the solubilities of narrow-boiling, heavy fossil-fuel fractions in compressed gases. The solubility of a heavy fraction is determined from the volume of gas required to vaporize completely a small, measured mass of fossil-fuel sample. To test the molecular-thermodynamic model, the total-vaporization technique has been used to measure the solubilities of two Lurgi coal-tar fractions in compressed methane. Predicted and experimental solubilities agree well.

  3. New Optical Sensor Suite for Ultrahigh Temperature Fossil Fuel Application

    SciTech Connect (OSTI)

    John Coggin; Tom Flynn; Jonas Ivasauskas; Daniel Kominsky; Carrie Kozikowski; Russell May; Michael Miller; Tony Peng; Gary Pickrell; Raymond Rumpf; Kelly Stinson-Bagby; Dan Thorsen; Rena Wilson

    2007-12-31

    Accomplishments of a program to develop and demonstrate photonic sensor technology for the instrumentation of advanced powerplants and solid oxide fuel cells are described. The goal of this project is the research and development of advanced, robust photonic sensors based on improved sapphire optical waveguides, and the identification and demonstration of applications of the new sensors in advanced fossil fuel power plants, where the new technology will contribute to improvements in process control and monitoring.

  4. Norwegian carbon taxes and their implication for fossil fuels

    SciTech Connect (OSTI)

    Kaarstad, O.

    1995-12-31

    The Scandinavian countries, and in particular Norway and Sweden, have since 1990/91 taxed CO{sub 2}-emissions with carbon tax of about US $150 per ton of CO{sub 2}. One may therefore say that these countries have placed themselves in a role as {open_quotes}carbon tax laboratories{close_quotes}. These very high CO{sub 2}-taxes have been in place for about four years and the first lessons from this experience are reported. In general it would seem as if the taxation mechanism is less efficient than economists have expected. The CO{sub 2}-emissions are increasing in both Norway and Sweden and the stabilization goal to the year 2000 will not be achieved in spite of the high taxation. The fossil fuel industry will have to learn to live with the climate change question which is inherently hostile to fossil fuels. It is argued that a more informed and active participation by the fossil fuel industry is needed in the climate change discussion. In addition the image of fossil fuels will benefit from showing real and potential improvement in the area of greenhouse gas emissions in the whole energy chain from production to combustion. The R&D effort being done into CO{sub 2}-capture and -disposal is creating such an option for the future. It is argued that the image of the entire fossil fuel industry will benefit from the creation of a {open_quotes}CO{sub 2}-free{close_quote} option or vision for oil, gas and coal. A number of examples are shown where today (or in the near future) actual CO{sub 2}-disposal in underground formations are taking place.

  5. Vented nuclear fuel element

    DOE Patents [OSTI]

    Grossman, Leonard N.; Kaznoff, Alexis I.

    1979-01-01

    A nuclear fuel cell for use in a thermionic nuclear reactor in which a small conduit extends from the outside surface of the emitter to the center of the fuel mass of the emitter body to permit escape of volatile and gaseous fission products collected in the center thereof by virtue of molecular migration of the gases to the hotter region of the fuel.

  6. US fossil fuel technologies for Thailand

    SciTech Connect (OSTI)

    Buehring, W.A.; Dials, G.E.; Gillette, J.L.; Szpunar, C.B.; Traczyk, P.A.

    1990-10-01

    The US Department of Energy has been encouraging other countries to consider US coal and coal technologies in meeting their future energy needs. Thailand is one of three developing countries determined to be a potentially favorable market for such exports. This report briefly profiles Thailand with respect to population, employment, energy infrastructure and policies, as well as financial, economic, and trade issues. Thailand is shifting from a traditionally agrarian economy to one based more strongly on light manufacturing and will therefore require increased energy resources that are reliable and flexible in responding to anticipated growth. Thailand has extensive lignite deposits that could fuel a variety of coal-based technologies. Atmospheric fluidized-bed combustors could utilize this resource and still permit Thailand to meet emission standards for sulfur dioxide. This option also lends itself to small-scale applications suitable for private-sector power generation. Slagging combustors and coal-water mixtures also appear to have potential. Both new construction and refurbishment of existing plants are planned. 18 refs., 3 figs., 7 tabs.

  7. Fossil fuels in a sustainable energy future

    SciTech Connect (OSTI)

    Bechtel, T.F.

    1995-12-01

    The coal industry in the United States has become a world leader in safety, productivity, and environmental protection in the mining of coal. The {open_quotes}pick-and-shovel{close_quotes} miner with mangled limbs and black lung disease has been replaced by the highly skilled technicians that lead the world in tons per man-hour. The gob piles, polluted streams, and scared land are a thing of the past. The complementary efforts of the DOE and EPRI-funded programs in coal utilization R&D and the Clean Coal Technology Program commercial demonstrations, have positioned the power generation industry to utilize coal in a way that doesn`t pollute the air or water, keeps electrical power costs low, and avoids the mountains of waste material. This paper reviews the potential for advanced coal utilization technologies in new power generation applications as well as the repowering of existing plants to increase their output, raise their efficiency, and reduce pollution. It demonstrates the potential for these advanced coal-fueled plants to play a complementary role in future planning with the natural gas and oil fired units currently favored in the market place. The status of the US program to demonstrate these technologies at commercial scale is reviewed in some detail.

  8. Nuclear fuel composition

    DOE Patents [OSTI]

    Feild, Jr., Alexander L.

    1980-02-19

    1. A high temperature graphite-uranium base nuclear fuel composition containing from about 1 to about 5 five weight percent rhenium metal.

  9. Fossil fuel decarbonization technology for mitigating global warming

    SciTech Connect (OSTI)

    Steinberg, M.

    1998-09-01

    It has been understood that production of hydrogen from fossil and carbonaceous fuels with reduced CO{sub 2} emission to the atmosphere is key to the production of hydrogen-rich fuels for mitigating the CO{sub 2} greenhouse gas climate change problem. The conventional methods of hydrogen production from fossil fuels (coal, oil, gas and biomass) include steam reforming and water gas shift mainly of natural gas (SRM). In order to suppress CO{sub 2} emission from the steam reforming process, CO{sub 2} must be concentrated and sequestered either in or under the ocean or underground (in aquifers, or depleted oil or gas wells). Up to about 40% of the energy is lost in this process. An alternative process is the pyrolysis or the thermal decomposition of methane, natural gas (TDM) to hydrogen and carbon. The carbon can either be sequestered or sold on the market as a materials commodity or used as a fuel at a later date under less severe CO{sub 2} restraints. The energy sequestered in the carbon amounts to about 42% of the energy in the natural gas resource which is stored and not destroyed. A comparison is made between the well developed conventional SRM and the less developed TDM process including technological status, efficiency, carbon management and cost. The TDM process appears to have advantages over the well developed SRM process. It is much easier to sequester carbon as a stable solid than CO{sub 2} as a reactive gas or low temperature liquid. It is also possible to reduce cost by marketing the carbon as a filler or construction material. The potential benefits of the TDM process justifies its further efficient development. The hydrogen can be used as a transportation fuel or converted to methanol by reaction with CO{sub 2} from fossil fuel fired power plant stack gases, thus allowing reuse of the carbon in conventional IC automobile engines or in advanced fuel cell vehicles.

  10. Fossil fuel decarbonization technology for mitigating global warming

    SciTech Connect (OSTI)

    Steinberg, M.

    1998-07-01

    It has been understood that production of hydrogen from fossil and carbonaceous fuels with reduced CO{sub 2} emission to the atmosphere is key to the production of hydrogen-rich fuels for mitigating the CO{sub 2} greenhouse gas climate change problem. The conventional methods of hydrogen production from fossil fuels (coal, oil, gas and biomass) include steam reforming and water gas shift mainly of natural gas (SRM). In order to suppress CO{sub 2} emission from the steam reforming process, CO{sub 2} must be concentrated and sequestered either in or under the ocean or in or underground (in aquifers, or depleted oil or gas wells). Up to about 40% of the energy is lost in this process. An alternative process is the pyrolysis or the thermal decomposition of methane, natural gas (TDM) to hydrogen and carbon. The carbon can either be sequestered or sold on the market as a materials commodity or used as a fuel at a later date under less severe CO{sub 2} restraints. The energy sequestered in the carbon amounts to about 42% of the energy in the natural gas resource which is stored and not destroyed. A comparison is made between the well developed conventional SRB and the less developed TDM process including technological status, efficiency, carbon management and cost. The TDM process appears to have advantages over the well developed SRM process. It is much easier to sequester carbon as a stable solid than CO{sub 2} as a reactive gas or low temperature liquid. It is also possible to reduce cost by marketing the carbon as a filler or construction material. The potential benefits of the TDM process justifies its further efficient development. The hydrogen can be used as a transportation fuel or converted to methanol by reaction with CO{sub 2} from fossil fuel fired power plant stack gases, thus allowing reuse of the carbon in conventional IC automobile engines or in advanced fuel cell vehicles.

  11. Fossil fuel decarbonization technology for mitigating global warming

    SciTech Connect (OSTI)

    Steinberg, M.

    1998-04-01

    It has been understood that production of hydrogen from fossil and carbonaceous fuels with reduced CO{sub 2} emission to the atmosphere is key to the production of hydrogen-rich fuels for mitigating the CO{sub 2} greenhouse gas climate change problem. The conventional methods of hydrogen production from fossil fuels (coal, oil, gas and biomass) include steam reforming process, mainly of natural gas (SRM). In order to suppress CO{sub 2} emission from the steam reforming process, CO{sub 2} must be concentrated and sequestered either in or under the ocean or in or underground (in aquifers, or depleted oil or gas wells). Up to about 40% of the energy is lost in this process. An alternative process is the pyrolysis or the thermal decomposition of methane, natural gas (TDM) to hydrogen and carbon. The carbon can either be sequestered or sold on the market as a materials commodity or used as a fuel at a later date under less severe CO{sub 2} restraints. The energy sequestered in the carbon amounts to about 42% of the energy in the natural gas resource which is stored and not destroyed. A comparison is made between the well developed conventional SRM and the less developed TDM process including technological status, efficiency, carbon management and cost. The TDM process appears to have advantages over the well developed SRM process. It is much easier to sequester carbon as a stable solid than CO{sub 2} as a reactive gas or low temperature liquid. It is also possible to reduce cost by marketing the carbon as a filler or construction material. The potential benefits of the TDM process justifies its further efficient development. The hydrogen can be used as a transportation fuel or converted to methanol by reaction with CO{sub 2} from fossil fuel fired power plant stack gases, thus allowing reuse of the carbon in conventional IC automobile engines or in advanced fuel cell vehicles.

  12. U.S. DOE fossil energy fuel cell program

    SciTech Connect (OSTI)

    Wayne Surdoval

    2007-07-01

    The U.S. Department of Energy's Office of Fossil Energy's National Energy Technology Laboratory, in partnership with private industry, educational institutions, and national laboratories, is leading the research, development, and demonstration of high efficiency, fuel flexible solid oxide fuel cells (SOFCs) and coal based SOFC power generation systems for stationary markets. This Fuel Cell Program has three parts: Solid State Energy Conversion Alliance (SECA) cost reduction, SECA fuel cell coal based systems, and advanced SECA systems. The SECA cost reduction goal is to have SOFCs capable of being mass manufactured at $400 per kilowatt by 2010. Concurrently, the scale-up, aggregation, and integration of the technology will progress in parallel leading to prototype validation of megawatt class products by 2012 with potential testing at FutureGen. The SECA coal-based and advanced systems goals are the development of megawatt-class fuel cell power systems that will enable affordable, reliable, efficient, and environmentally-friendly electrical power from coal.

  13. An oxy-hydrocarbon model of fossil fuels

    SciTech Connect (OSTI)

    Fred D. Lang; Tom Canning

    2007-09-15

    This paper asserts a new method of analyzing fossil fuels, useful for sorting coals into well-defined categories and for the identification of outlying ultimate analysis data. It describes a series of techniques starting with a new multivariant approach for describing the lower ranks of coal, progressing to a classical, but modified, single-variant approach for the volatile and high-energy ranks. In addition, for a few special cases, multiple low and high ranks are also well described by the multivariant approach. As useful as these techniques are for analyzing fuel chemistry in the laboratory arena, this work was initiated in support of Exergetic Systems' Input/Loss Method. At commercial coal-fired power plants, Input/Loss allows the determination of fuel chemistry based on combustion effluents. The methods presented allow equations to be developed independent of combustion stoichiometrics, which improve Input/Loss accuracy in determining fuel chemistry on-line and in real time.

  14. Formulating Energy Policies Related to Fossil Fuel Use:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    CONF-9 O O 255 --I DE90 008741 Formulating Energy Policies Related to Fossil Fuel Use: i Critical Uncertainties in the Global Carbon Cycle. W. M. Post, V. H. Dale, D. L. DeAngelis, L. K. Mann, P. J. Mulholland, R. V. O'Neill, T. -H. Peng, M. P. Farrell Environmental Sciences Division Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831 The global carbon cycle is the dynamic interaction among the earth's carbon sources and sinks. Understanding the global carbon cycle

  15. Nuclear fuel element

    DOE Patents [OSTI]

    Zocher, Roy W.

    1991-01-01

    A nuclear fuel element and a method of manufacturing the element. The fuel element is comprised of a metal primary container and a fuel pellet which is located inside it and which is often fragmented. The primary container is subjected to elevated pressure and temperature to deform the container such that the container conforms to the fuel pellet, that is, such that the container is in substantial contact with the surface of the pellet. This conformance eliminates clearances which permit rubbing together of fuel pellet fragments and rubbing of fuel pellet fragments against the container, thus reducing the amount of dust inside the fuel container and the amount of dust which may escape in the event of container breach. Also, as a result of the inventive method, fuel pellet fragments tend to adhere to one another to form a coherent non-fragmented mass; this reduces the tendency of a fragment to pierce the container in the event of impact.

  16. TEPP- Spent Nuclear Fuel

    Broader source: Energy.gov [DOE]

    This scenario provides the planning instructions, guidance, and evaluation forms necessary to conduct an exercise involving a highway shipment of spent nuclear fuel.  This exercise manual is one in...

  17. Nuclear Fuel Reprocessing

    SciTech Connect (OSTI)

    Michael F. Simpson; Jack D. Law

    2010-02-01

    This is an a submission for the Encyclopedia of Sustainable Technology on the subject of Reprocessing Spent Nuclear Fuel. No formal abstract was required for the article. The full article will be attached.

  18. Nuclear fuel element

    DOE Patents [OSTI]

    Meadowcroft, Ronald Ross; Bain, Alastair Stewart

    1977-01-01

    A nuclear fuel element wherein a tubular cladding of zirconium or a zirconium alloy has a fission gas plenum chamber which is held against collapse by the loops of a spacer in the form of a tube which has been deformed inwardly at three equally spaced, circumferential positions to provide three loops. A heat resistant disc of, say, graphite separates nuclear fuel pellets within the cladding from the plenum chamber. The spacer is of zirconium or a zirconium alloy.

  19. Tsiklauri-Durst combined cycle (T-D Cycle{trademark}) application for nuclear and fossil-fueled power generating plants

    SciTech Connect (OSTI)

    Tsiklauri, B.; Korolev, V.N.; Durst, B.M.; Shen, P.K.

    1998-07-01

    The Tsiklauri-Durst combined cycle is a combination of the best attributes of both nuclear power and combined cycle gas power plants. A technology patented in 1994 by Battelle Memorial Institute offers a synergistic approach to power generation. A typical combined cycle is defined as the combination of gas turbine Brayton Cycle, topping steam turbine Rankine Cycle. Exhaust from the gas turbine is used in heat recovery steam generators to produce steam for a steam turbine. In a standard combined cycle gas turbine-steam turbine application, the gas turbine generates about 65 to 70 percent of system power. The thermal efficiency for such an installation is typically about 45 to 50 percent. A T-D combined cycle takes a new, creative approach to combined cycle design by directly mixing high enthalpy steam from the heat recovery steam generator, involving the steam generator at more than one pressure. Direct mixing of superheated and saturated steam eliminates the requirement for a large heat exchanger, making plant modification simple and economical.

  20. Mitigating environmental pollution and impacts from fossil fuels: The role of alternative fuels

    SciTech Connect (OSTI)

    Liu, L.; Cheng, S.Y.; Li, J.B.; Huang, Y.F.

    2007-07-01

    In order to meet the rising global demand for energy, rapid development of conventional fossil fuels (i.e., coal, oil, and natural gas) have been experienced by many nations, bringing dramatic economic benefit and prosperity to fossil-fuel industries as well as well being of human society. However, various fossil-fuel related activities emit huge quantities of gaseous, liquid, and solid waste materials, posing a variety of impacts, risks, and liabilities to the environment. Therefore, on the one hand, control measures are desired for effectively managing pollution issues; on the other hand, it becomes extremely critical to invest efforts in finding promising alternative energy sources as solutions to the possible energy shortage crisis in future. This article focuses on both aspects through: (1) a discussion of waste materials generated from fossil-fuel industries and waste management measures; and (2) an exploration of some well-recognized alternative fuels in terms of their nature, availability, production, handling, environmental performances, and current and future applications. The conclusion restates the urgency of finding replaceable long-term alternatives to the conventional fuels.

  1. Spatial Relationships of Sector-Specific Fossil-fuel CO2 Emissions in the

    Office of Scientific and Technical Information (OSTI)

    United States (Journal Article) | SciTech Connect Spatial Relationships of Sector-Specific Fossil-fuel CO2 Emissions in the United States Citation Details In-Document Search Title: Spatial Relationships of Sector-Specific Fossil-fuel CO2 Emissions in the United States Quantification of the spatial distribution of sector-specific fossil fuel CO2 emissions provides strategic information to public and private decision-makers on climate change mitigation options and can provide critical

  2. Carter, L.D. 20 FOSSIL-FUELED POWER PLANTS; COAL GASIFICATION...

    Office of Scientific and Technical Information (OSTI)

    carbon capture, utilisation, and storage Carter, L.D. 20 FOSSIL-FUELED POWER PLANTS; COAL GASIFICATION; POWER GENERATION; CARBON DIOXIDE; CAPTURE; STORAGE; USA; ENHANCED...

  3. EPRI-DOE Joint Report on Fossil Fleet Transition with Fuel Changes...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    and Large Scale Variable Renewable Integration Now Available EPRI-DOE Joint Report on Fossil Fleet Transition with Fuel Changes and Large Scale Variable Renewable Integration ...

  4. Rajendran, N. 36 MATERIALS SCIENCE; 20 FOSSIL-FUELED POWER PLANTS...

    Office of Scientific and Technical Information (OSTI)

    ACI Committee 229 Rajendran, N. 36 MATERIALS SCIENCE; 20 FOSSIL-FUELED POWER PLANTS; 01 COAL, LIGNITE, AND PEAT; FLY ASH; WASTE PRODUCT UTILIZATION; BACKFILLING; THERMAL...

  5. Fossil fuel derivatives with reduced carbon. Phase I final report

    SciTech Connect (OSTI)

    Kennel, E.B.; Zondlo, J.W.; Cessna, T.J.

    1999-06-30

    This project involves the simultaneous production of clean fossil fuel derivatives with reduced carbon and sulfur, along with value-added carbon nanofibers. This can be accomplished because the nanofiber production process removes carbon via a catalyzed pyrolysis reaction, which also has the effect of removing 99.9% of the sulfur, which is trapped in the nanofibers. The reaction is mildly endothermic, meaning that net energy production with real reductions in greenhouse emissions are possible. In Phase I research, the feasibility of generating clean fossil fuel derivatives with reduced carbon was demonstrated by the successful design, construction and operation of a facility capable of utilizing coal as well as natural gas as an inlet feedstock. In the case of coal, for example, reductions in CO{sub 2} emissions can be as much as 70% (normalized according to kilowatts produced), with the majority of carbon safely sequestered in the form of carbon nanofibers or coke. Both of these products are value-added commodities, indicating that low-emission coal fuel can be done at a profit rather than a loss as is the case with most clean-up schemes. The main results of this project were as follows: (1) It was shown that the nanofiber production process produces hydrogen as a byproduct. (2) The hydrogen, or hydrogen-rich hydrocarbon mixture can be consumed with net release of enthalpy. (3) The greenhouse gas emissions from both coal and natural gas are significantly reduced. Because coal consumption also creates coke, the carbon emission can be reduced by 75% per kilowatt-hour of power produced.

  6. Nuclear fuel pin scanner

    DOE Patents [OSTI]

    Bramblett, Richard L.; Preskitt, Charles A.

    1987-03-03

    Systems and methods for inspection of nuclear fuel pins to determine fiss loading and uniformity. The system includes infeed mechanisms which stockpile, identify and install nuclear fuel pins into an irradiator. The irradiator provides extended activation times using an approximately cylindrical arrangement of numerous fuel pins. The fuel pins can be arranged in a magazine which is rotated about a longitudinal axis of rotation. A source of activating radiation is positioned equidistant from the fuel pins along the longitudinal axis of rotation. The source of activating radiation is preferably oscillated along the axis to uniformly activate the fuel pins. A detector is provided downstream of the irradiator. The detector uses a plurality of detector elements arranged in an axial array. Each detector element inspects a segment of the fuel pin. The activated fuel pin being inspected in the detector is oscillated repeatedly over a distance equal to the spacing between adjacent detector elements, thereby multiplying the effective time available for detecting radiation emissions from the activated fuel pin.

  7. Service experience and reliability improvement: Nuclear, fossil, and petrochemical plants

    SciTech Connect (OSTI)

    Bamford, W.H.; Cipolla, R.C.; Warke, W.R.; Onyewuenyi, O.A.; Bagnoli, D.; Phillips, J.H.; Prager, M.; Becht, C. IV

    1994-01-01

    This publication contains papers presented at the following four symposia conducted at the 1994 Pressure Vessels and Piping Conference in Minneapolis, Minnesota, June 19--23: Service Experience in Nuclear Plants; Risk-Based Inspection and Evaluation; Service Experience in Operating Fossil Power Plants; and Service Experience in Petrochemical Plants. These symposia were sponsored by the Materials and Fabrication and the Design and Analysis Committees of the ASME Pressure Vessels and Piping Division. The objective of these symposia was to disseminate information on issues and degradation that have resulted from the operation of nuclear, fossil, and petrochemical power plants, as well as related reliability issues. Thirty-nine papers have been processed separately for inclusion on the data base.

  8. New Optimal Sensor Suite for Ultrahigh Temperature Fossil Fuel Applications

    SciTech Connect (OSTI)

    John Coggin; Jonas Ivasauskas; Russell G. May; Michael B. Miller; Rena Wilson

    2006-09-30

    Accomplishments during Phase II of a program to develop and demonstrate photonic sensor technology for the instrumentation of advanced powerplants are described. The goal of this project is the research and development of advanced, robust photonic sensors based on improved sapphire optical waveguides, and the identification and demonstration of applications of the new sensors in advanced fossil fuel power plants, where the new technology will contribute to improvements in process control and monitoring. During this program work period, major progress has been experienced in the development of the sensor hardware, and the planning of the system installation and operation. The major focus of the next work period will be the installation of sensors in the Hamilton, Ohio power plant, and demonstration of high-temperature strain gages during mechanical testing of SOFC components.

  9. Progress performance report of clean uses of fossil fuels

    SciTech Connect (OSTI)

    Todd, Jr., Lee T.; Boggess, Ronald J.; Carson, Ronald J.; Falkenberg, Virginia P.; Flanagan, Patrick; Hettinger, Jr., William P.; Kimel, Kris; Kupchella, Charles E.; Magid, Lee J.; McLaughlin, Barbara; Royster, Wimberly C.; Streepey, Judi L.; Wells, James H.; Stencel, John; Derbyshire, Frank J.; Hanley, Thomas R.; Magid, Lee J.; McEllistrem, Marc T.; Riley, John T.; Steffen, Joseph M.

    1992-01-01

    A one-year USDOE/EPSCOR Traineeship Grant, entitled Clean Uses of Fossil Fuels.'' was awarded to the Kentucky EPSCoR Committee in September 1991 and administered through the the DOE/EPSCoR Subcommittee. Ten Traineeships were awarded to doctoral students who are enrolled or accepted into Graduate Programs at either the University of Kentucky or the University of Louisville. The disciplines of these students include Biology, Chemical Engineering, Chemistry, Geological Sciences, and Physics. The methods used for a statewide proposal solicitation and to award the Traineeships are presented. The review panel and Kentucky DOE/EPSCoR Subcommittee involved in awarding the Traineeships are described. A summary of the proposed research to be performed within these awards is presented, along with a description of the qualifications of the faculty and students who proposed projects. Future efforts to increase participation in Traineeship proposals for the succeeding funding period are outlined.

  10. Progress performance report of clean uses of fossil fuels

    SciTech Connect (OSTI)

    Not Available

    1992-09-01

    A one-year USDOE/EPSCOR Traineeship Grant, entitled ``Clean Uses of Fossil Fuels.`` was awarded to the Kentucky EPSCoR Committee in September 1991 and administered through the the DOE/EPSCoR Subcommittee. Ten Traineeships were awarded to doctoral students who are enrolled or accepted into Graduate Programs at either the University of Kentucky or the University of Louisville. The disciplines of these students include Biology, Chemical Engineering, Chemistry, Geological Sciences, and Physics. The methods used for a statewide proposal solicitation and to award the Traineeships are presented. The review panel and Kentucky DOE/EPSCoR Subcommittee involved in awarding the Traineeships are described. A summary of the proposed research to be performed within these awards is presented, along with a description of the qualifications of the faculty and students who proposed projects. Future efforts to increase participation in Traineeship proposals for the succeeding funding period are outlined.

  11. 30 DIRECT ENERGY CONVERSION; 20 FOSSIL-FUELED POWER PLANTS; 32...

    Office of Scientific and Technical Information (OSTI)

    Lee, G.T.; Sudhoff, F.A. 30 DIRECT ENERGY CONVERSION; 20 FOSSIL-FUELED POWER PLANTS; 32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATION; FUEL CELL POWER PLANTS; GAS TURBINE...

  12. Better batteries to break dependence on fossil fuels > EMC2 News...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Better batteries to break dependence on fossil fuels April 28th, 2015 By Linda B. ... said Abrua, which means better and more affordable designs for fuel cells and batteries. ...

  13. Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Dale, Deborah J.

    2014-10-28

    These slides will be presented at the training course “International Training Course on Implementing State Systems of Accounting for and Control (SSAC) of Nuclear Material for States with Small Quantity Protocols (SQP),” on November 3-7, 2014 in Santa Fe, New Mexico. The slides provide a basic overview of the Nuclear Fuel Cycle. This is a joint training course provided by NNSA and IAEA.

  14. Nuclear Fuel Reprocessing

    SciTech Connect (OSTI)

    Harold F. McFarlane; Terry Todd

    2013-11-01

    Reprocessing is essential to closing nuclear fuel cycle. Natural uranium contains only 0.7 percent 235U, the fissile (see glossary for technical terms) isotope that produces most of the fission energy in a nuclear power plant. Prior to being used in commercial nuclear fuel, uranium is typically enriched to 3–5% in 235U. If the enrichment process discards depleted uranium at 0.2 percent 235U, it takes more than seven tonnes of uranium feed to produce one tonne of 4%-enriched uranium. Nuclear fuel discharged at the end of its economic lifetime contains less one percent 235U, but still more than the natural ore. Less than one percent of the uranium that enters the fuel cycle is actually used in a single pass through the reactor. The other naturally occurring isotope, 238U, directly contributes in a minor way to power generation. However, its main role is to transmute into plutoniumby neutron capture and subsequent radioactive decay of unstable uraniumand neptuniumisotopes. 239Pu and 241Pu are fissile isotopes that produce more than 40% of the fission energy in commercially deployed reactors. It is recovery of the plutonium (and to a lesser extent the uranium) for use in recycled nuclear fuel that has been the primary focus of commercial reprocessing. Uraniumtargets irradiated in special purpose reactors are also reprocessed to obtain the fission product 99Mo, the parent isotope of technetium, which is widely used inmedical procedures. Among the fission products, recovery of such expensive metals as platinum and rhodium is technically achievable, but not economically viable in current market and regulatory conditions. During the past 60 years, many different techniques for reprocessing used nuclear fuel have been proposed and tested in the laboratory. However, commercial reprocessing has been implemented along a single line of aqueous solvent extraction technology called plutonium uranium reduction extraction process (PUREX). Similarly, hundreds of types of reactor fuels have been irradiated for different purposes, but the vast majority of commercial fuel is uranium oxide clad in zirconium alloy tubing. As a result, commercial reprocessing plants have relatively narrow technical requirements for used nuclear that is accepted for processing.

  15. The Council of Industrial Boiler Owners special project on non-utility fossil fuel ash classification

    SciTech Connect (OSTI)

    Svendsen, R.L.

    1996-12-31

    Information is outlined on the Council of Industrial Boiler Owners (CIBO) special project on non-utility fossil fuel ash classification. Data are presented on; current (1996) regulatory status of fossil-fuel combustion wastes; FBC technology identified for further study; CIBO special project methods; Bevill amendment study factors; data collection; and CIBO special project status.

  16. Nuclear Fuel Cycle Options Catalog

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management ...

  17. Low-emission vortex combustion of biomass and fossil fuel

    SciTech Connect (OSTI)

    Finker, F.Z.; Kubischkin, I.B.; Akhmedov, D.B.

    1995-11-01

    The article introduces the results of development and industrial experience of low-emission vortex combustion technology (LEVC) of biomass and fossil fuel in industrial and utility boilers in Russian timber and paper industries and Polish power plants. The LEVC technology is based on aerodynamics method of multiple circulation of gases and fuel in the furnaces. LEVC technology accumulates the advantages of conventional and fluidized bed combustion technology. Existing boilers could be easily retrofitted for the application of LEVC technology without requiring major investment. The repowering of boiler with LEVC was the result the reduction NOx emission to the level 170g/GJ without installation additional flue gas cleaning equipment and it gave the opportunity for an injection of sulfur sorbent in the furnace. The authors discussed Russian-Polish experiment on utility boiler retrofitted with the application of LEVC. As the result the efficiency of the boiler increased in 2%. The reduction of the emission is: NOx-40%, SO2-17%.

  18. Refractory failure in IGCC fossil fuel power systems

    SciTech Connect (OSTI)

    Dogan, Cynthia P.; Kwong, Kyei-Sing; Bennett, James P.; Chinn, Richard E.

    2001-01-01

    Current generation refractory materials used in slagging gasifiers employed in Integrated Gasification Combined Cycle (IGCC) fossil fuel power systems have unacceptably short service lives, limiting the reliability and cost effectiveness of gasification as a means to generate power. The short service life of the refractory lining results from exposure to the extreme environment inside the operating gasifier, where the materials challenges include temperatures to 1650 C, thermal cycling, alternating reducing and oxidizing conditions, and the presence of corrosive slags and gases. Compounding these challenges is the current push within the industry for fuel flexibility, which results in slag chemistries and operating conditions that can vary widely as the feedstock for the gasifier is supplemented with alternative sources of carbon, such as petroleum coke and biomass. As a step toward our goal of developing improved refractory materials for this application, we have characterized refractory-slag interactions, under a variety of simulated gasifier conditions, utilizing laboratory exposure tests such as the static cup test and a gravimetric test. Combining this information with that gained from the post-mortem analyses of spent refractories removed from working gasifiers, we have developed a better understanding of refractory failure in gasifier environments. In this paper, we discuss refractory failures in slagging gasifiers and possible strategies to reduce them. Emphasis focuses on the refractories employed in gasifier systems which utilize coal as the primary feedstock.

  19. Nuclear fuel element

    DOE Patents [OSTI]

    Armijo, Joseph S.; Coffin, Jr., Louis F.

    1983-01-01

    A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has a composite cladding having a substrate and a metal barrier metallurgically bonded on the inside surface of the substrate so that the metal barrier forms a shield between the substrate and the nuclear fuel material held within the cladding. The metal barrier forms about 1 to about 30 percent of the thickness of the cladding and is comprised of a low neutron absorption metal of substantially pure zirconium. The metal barrier serves as a preferential reaction site for gaseous impurities and fission products and protects the substrate from contact and reaction with such impurities and fission products. The substrate of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy. Methods of manufacturing the composite cladding are also disclosed.

  20. Nuclear fuel element

    DOE Patents [OSTI]

    Armijo, Joseph S.; Coffin, Jr., Louis F.

    1980-04-29

    A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has an improved composite cladding comprised of a moderate purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube. The metal barrier forms a shield between the alloy tube and a core of nuclear fuel material enclosed in the composite cladding. There is a gap between the cladding and the core. The metal barrier forms about 1 to about 30 percent of the thickness of the composite cladding and has low neutron absorption characteristics. The metal barrier serves as a preferential reaction site for gaseous impurities and fission products and protects the alloy tube from contact and reaction with such impurities and fission products. Methods of manufacturing the composite cladding are also disclosed.

  1. Nuclear reactor fuel element

    DOE Patents [OSTI]

    Johnson, Carl E. (Elk Grove, IL); Crouthamel, Carl E. (Richland, WA)

    1980-01-01

    A nuclear reactor fuel element is described which has an outer cladding, a central core of fissionable or mixed fissionable and fertile fuel material and a layer of oxygen gettering material on the inner surface of the cladding. The gettering material reacts with oxygen released by the fissionable material during irradiation of the core thereby preventing the oxygen from reacting with and corroding the cladding. Also described is an improved method for coating the inner surface of the cladding with a layer of gettering material.

  2. NUCLEAR REACTOR FUEL-BREEDER FUEL ELEMENT

    DOE Patents [OSTI]

    Currier, E.L. Jr.; Nicklas, J.H.

    1962-08-14

    A fuel-breeder fuel element was developed for a nuclear reactor wherein discrete particles of fissionable material are dispersed in a matrix of fertile breeder material. The fuel element combines the advantages of a dispersion type and a breeder-type. (AEC)

  3. INNOVATIVE FOSSIL FUEL FIRED VITRIFICATION TECHNOLOGY FOR SOIL REMEDIATION

    SciTech Connect (OSTI)

    J. Hnat; L.M. Bartone; M. Pineda

    2001-07-13

    This Summary Report summarizes the progress of Phases 3, 3A and 4 of a waste technology Demonstration Project sponsored under a DOE Environmental Management Research and Development Program and administered by the U.S. Department of Energy National Energy Technology Laboratory-Morgantown (DOE-NETL) for an ''Innovative Fossil Fuel Fired Vitrification Technology for Soil Remediation''. The Summary Reports for Phases 1 and 2 of the Program were previously submitted to DOE. The total scope of Phase 3 was to have included the design, construction and demonstration of Vortec's integrated waste pretreatment and vitrification process for the treatment of low level waste (LLW), TSCA/LLW and mixed low-level waste (MLLW). Due to funding limitations and delays in the project resulting from a law suit filed by an environmental activist and the extended time for DOE to complete an Environmental Assessment for the project, the scope of the project was reduced to completing the design, construction and testing of the front end of the process which consists of the Material Handling and Waste Conditioning (MH/C) Subsystem of the vitrification plant. Activities completed under Phases 3A and 4 addressed completion of the engineering, design and documentation of the Material Handling and Conditioning System such that final procurement of the remaining process assemblies can be completed and construction of a Limited Demonstration Project be initiated in the event DOE elects to proceed with the construction and demonstration testing of the MH/C Subsystem.

  4. Nuclear fuel electrorefiner

    DOE Patents [OSTI]

    Ahluwalia, Rajesh K.; Hua, Thanh Q.

    2004-02-10

    The present invention relates to a nuclear fuel electrorefiner having a vessel containing a molten electrolyte pool floating on top of a cadmium pool. An anodic fuel dissolution basket and a high-efficiency cathode are suspended in the molten electrolyte pool. A shroud surrounds the fuel dissolution basket and the shroud is positioned so as to separate the electrolyte pool into an isolated electrolyte pool within the shroud and a bulk electrolyte pool outside the shroud. In operation, unwanted noble-metal fission products migrate downward into the cadmium pool and form precipitates where they are removed by a filter and separator assembly. Uranium values are transported by the cadmium pool from the isolated electrolyte pool to the bulk electrolyte pool, and then pass to the high-efficiency cathode where they are electrolytically deposited thereto.

  5. High Efficiency Direct Carbon and Hydrogen Fuel Cells for Fossil Fuel Power Generation

    SciTech Connect (OSTI)

    Steinberg, M; Cooper, J F; Cherepy, N

    2002-01-02

    Hydrogen he1 cells have been under development for a number of years and are now nearing commercial applications. Direct carbon fuel cells, heretofore, have not reached practical stages of development because of problems in fuel reactivity and cell configuration. The carbon/air fuel cell reaction (C + O{sub 2} = CO{sub 2}) has the advantage of having a nearly zero entropy change. This allows a theoretical efficiency of 100 % at 700-800 C. The activities of the C fuel and CO{sub 2} product do not change during consumption of the fuel. Consequently, the EMF is invariant; this raises the possibility of 100% fuel utilization in a single pass. (In contrast, the high-temperature hydrogen fuel cell has a theoretical efficiency of and changes in fuel activity limit practical utilizations to 75-85%.) A direct carbon fuel cell is currently being developed that utilizes reactive carbon particulates wetted by a molten carbonate electrolyte. Pure COZ is evolved at the anode and oxygen from air is consumed at the cathode. Electrochemical data is reported here for the carbon/air cell utilizing carbons derived from he1 oil pyrolysis, purified coal, purified bio-char and petroleum coke. At 800 O C, a voltage efficiency of 80% was measured at power densities of 0.5-1 kW/m2. Carbon and hydrogen fuels may be produced simultaneously at lugh efficiency from: (1) natural gas, by thermal decomposition, (2) petroleum, by coking or pyrolysis of distillates, (3) coal, by sequential hydrogasification to methane and thermal pyrolysis of the methane, with recycle of the hydrogen, and (4) biomass, similarly by sequential hydrogenation and thermal pyrolysis. Fuel production data may be combined with direct C and H2 fuel cell operating data for power cycle estimates. Thermal to electric efficiencies indicate 80% HHV [85% LHV] for petroleum, 75.5% HHV [83.4% LHV] for natural gas and 68.3% HHV [70.8% LHV] for lignite coal. Possible benefits of integrated carbon and hydrogen fuel cell power generation cycles are: (1) increased efficiency by a factor of up to 2 over many conventional fossil fuel steam plants, (2) reduced power generation cost, especially for increasing fossil fuel cost, (3) reduced CO2 emission per kWh, and (4) direct sequestration or reuse (e.g., in enhanced oil or NG recovery) of the CO{sub 2} product.

  6. Emissions from ethanol-blended fossil fuel flames

    SciTech Connect (OSTI)

    Akcayoglu, Azize

    2011-01-15

    A fundamental study to investigate the emission characteristics of ethanol-blended fossil fuels is presented. Employing a heterogeneous experimental setup, emissions are measured from diffusion flames around spherical porous particles. Using an infusion pump, ethanol-fossil fuel blend is transpired into a porous sphere kept in an upward flowing air stream. A typical probe of portable digital exhaust gas analyzer is placed in and around the flame with the help of a multi-direction traversing mechanism to measure emissions such as un-burnt hydrocarbons, carbon monoxide and carbon dioxide. Since ethanol readily mixes with water, emission characteristics of ethanol-water blends are also studied. For comparison purpose, emissions from pure ethanol diffusion flames are also presented. A simplified theoretical analysis has been carried out to determine equilibrium surface temperature, composition of the fuel components in vapor-phase and heat of reaction of each blend. These theoretical predictions are used in explaining the emission characteristics of flames from ethanol blends. (author) This paper presents the results of an experimental study of flow structure in horizontal equilateral triangular ducts having double rows of half delta-wing type vortex generators mounted on the duct's slant surfaces. The test ducts have the same axial length and hydraulic diameter of 4 m and 58.3 mm, respectively. Each duct consists of double rows of half delta wing pairs arranged either in common flow-up or common flow-down configurations. Flow field measurements were performed using a Particle Image Velocimetry Technique for hydraulic diameter based Reynolds numbers in the range of 1000-8000. The secondary flow field differences generated by two different vortex generator configurations were examined in detail. The secondary flow is found stronger behind the second vortex generator pair than behind the first pair but becomes weaker far from the second pair in the case of Duct1. However, the strength of the secondary flow is found nearly the same behind the first and the second vortex generator pair as well as far from the second vortex generator pair in the case of Duct2. Both ducts are able to create a counter-rotating and a second set of twin foci. Duct2 is able to create the second set of twin foci in an earlier streamwise location than Duct1, as these foci are well-known to their heat transfer augmentation. A larger vortex formation area and a greater induced vorticity field between vortex pairs are observed for Duct2 compared with Duct1. As the induced flow field between the vortex pairs increases the heat transfer, and as the flow field between the vortex cores is found larger in the case of Duct2, therefore, it is expected to obtain better heat transfer characteristics for Duct2 compared with Duct1. (author)

  7. Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2014

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Map Appendix State/area maps Figure A1. Fossil fuel production on federal and Indian lands, FY 2014 Source: U.S. Energy Information Administration based on U.S. Department of the Interior, Office of Natural Resources Revenue. "ONNR Statistical Information Site" (http://statistics.onrr.gov). July 2015 U.S. Energy Information Administration | Sales of Fossil Fuels Produced on Federal and Indian Lands, FY 2003 through FY 2014 24 Figure A2. Changes in fossil fuels production (trillion

  8. Nuclear Fuels Storage & Transportation Planning Project | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown ...

  9. INNOVATIVE FOSSIL FUEL FIRED VITRIFICATION TECHNOLOGY FOR SOIL REMEDIATION

    SciTech Connect (OSTI)

    J. Hnat; L.M. Bartone; M. Pineda

    2001-10-31

    This Final Report summarizes the progress of Phases 3,3A and 4 of a waste technology Demonstration Project sponsored under a DOE Environmental Management Research and Development Program and administered by the U.S. Department of Energy National Energy Technology Laboratory-Morgantown (DOE-NETL) for an ''Innovative Fossil Fuel Fired Vitrification Technology for Soil Remediation''. The Summary Reports for Phases 1 and 2 of the Program were previously submitted to DOE. The total scope of Phase 3 was to have included the design, construction and demonstration of Vortec's integrated waste pretreatment and vitrification process for the treatment of low level waste (LLW), TSCA/LLW and mixed low-level waste (MLLW). Due to funding limitations and delays in the project resulting from a law suit filed by an environmental activist and the extended time for DOE to complete an Environmental Assessment for the project, the scope of the project was reduced to completing the design, construction and testing of the front end of the process which consists of the Material Handling and Waste Conditioning (MH/C) Subsystem of the vitrification plant. Activities completed under Phases 3A and 4 addressed completion of the engineering, design and documentation of the MH/C System such that final procurement of the remaining process assemblies can be completed and construction of a Limited Demonstration Project be initiated in the event DOE elects to proceed with the construction and demonstration testing of the MH/C Subsystem. Because of USEPA policies and regulations that do not require treatment of low level or low-level/PCB contaminated wastes, DOE terminated the project because there is no purported need for this technology.

  10. EMGeo: Risk Minimizing Software for Finding Offshore Fossil Fuels by Fluid Identification

    Energy Innovation Portal (Marketing Summaries) [EERE]

    2011-01-21

    Berkeley Lab researchers Greg Newman and Michael Commer have developed advanced software for discovering and mapping offshore fossil fuel deposits. When combined with established seismic methods, this software makes possible direct imaging of reservoir fluids....

  11. Allen, C.A. 15 GEOTHERMAL ENERGY; 20 FOSSIL-FUELED POWER PLANTS...

    Office of Scientific and Technical Information (OSTI)

    Liquid-fluidized-bed heat exchanger flow distribution models Cole, L.T.; Allen, C.A. 15 GEOTHERMAL ENERGY; 20 FOSSIL-FUELED POWER PLANTS; FLUIDIZED BED HEAT EXCHANGERS; DESIGN;...

  12. Impacts of Renewable Generation on Fossil Fuel Unit Cycling: Costs and Emissions (Presentation)

    SciTech Connect (OSTI)

    Brinkman, G.; Lew, D.; Denholm, P.

    2012-09-01

    Prepared for the Clean Energy Regulatory Forum III, this presentation looks at the Western Wind and Solar Integration Study and reexamines the cost and emissions impacts of fossil fuel unit cycling.

  13. Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2011

    Office of Energy Efficiency and Renewable Energy (EERE)

    This paper was prepared in response to recent requests that the U.S. Energy Information Administration (EIA) provide updated summary information regarding fossil fuel production on federal and...

  14. fan blades Karr, O.F.; Brooks, J.B.; Seay, E. 20 FOSSIL-FUELED...

    Office of Scientific and Technical Information (OSTI)

    draft fan blades Karr, O.F.; Brooks, J.B.; Seay, E. 20 FOSSIL-FUELED POWER PLANTS; 32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATION; 42 ENGINEERING NOT INCLUDED IN OTHER...

  15. Fossil fuel potential of Turkey: A statistical evaluation of reserves, production, and consumption

    SciTech Connect (OSTI)

    Korkmaz, S.; Kara-Gulbay, R.; Turan, M.

    2008-07-01

    Since Turkey is a developing country with tremendous economic growth, its energy demand is also getting increased. Of this energy, about 70% is supplied from fossil fuels and the remaining 30% is from renewable sources. Among the fossil fuels, 90% of oil, natural gas, and coal are imported, and only 10% is from domestic sources. All the lignite is supplied from domestic sources. The total share of renewable sources and lignite in the total energy production is 45%. In order for Turkey to have sufficient and reliable energy sources, first the renewable energy sources must be developed, and energy production from fossil fuels, except for lignite, must be minimized. Particularly, scarcity of fossil fuels and increasing oil prices have a strong effect on economic growth of the country.

  16. Swelling-resistant nuclear fuel

    DOE Patents [OSTI]

    Arsenlis, Athanasios; Satcher, Jr., Joe; Kucheyev, Sergei O.

    2011-12-27

    A nuclear fuel according to one embodiment includes an assembly of nuclear fuel particles; and continuous open channels defined between at least some of the nuclear fuel particles, wherein the channels are characterized as allowing fission gasses produced in an interior of the assembly to escape from the interior of the assembly to an exterior thereof without causing significant swelling of the assembly. Additional embodiments, including methods, are also presented.

  17. A synthesis of carbon dioxide emissions from fossil-fuel combustion

    SciTech Connect (OSTI)

    Andres, Robert Joseph; Boden, Thomas A; Breon, F.-M.; Erickson, D; Gregg, J. S.; Jacobson, Andrew; Marland, Gregg; Miller, J.; Oda, T; Raupach, Michael; Rayner, P; Treanton, K.

    2012-01-01

    This synthesis discusses the emissions of carbon dioxide from fossil-fuel combustion and cement production. While much is known about these emissions, there is still much that is unknown about the details surrounding these emissions. This synthesis explores 5 our knowledge of these emissions in terms of why there is concern about them; how they are calculated; the major global efforts on inventorying them; their global, regional, and national totals at different spatial and temporal scales; how they are distributed on global grids (i.e. maps); how they are transported in models; and the uncertainties associated with these different aspects of the emissions. The magnitude of emissions 10 from the combustion of fossil fuels has been almost continuously increasing with time since fossil fuels were first used by humans. Despite events in some nations specifically designed to reduce emissions, or which have had emissions reduction as a byproduct of other events, global total emissions continue their general increase with time. Global total fossil-fuel carbon dioxide emissions are known to within 10% uncertainty (95% 15 confidence interval). Uncertainty on individual national total fossil-fuel carbon dioxide emissions range from a few percent to more than 50 %. The information discussed in this manuscript synthesizes global, regional and national fossil-fuel carbon dioxide emissions, their distributions, their transport, and the associated uncertainties.

  18. 2004 Office of Fossil Energy Fuel Cell Program Annual Report

    SciTech Connect (OSTI)

    NETL

    2004-11-01

    Annual report of fuel cell projects sponsored by Department of Energy, National Energy Technology Laboratory.

  19. Base-Load and Peak Electricity from a Combined Nuclear Heat and Fossil Combined-Cycle Plant

    SciTech Connect (OSTI)

    Conklin, James C.; Forsberg, Charles W.

    2007-07-01

    A combined-cycle power plant is proposed that uses heat from a high-temperature reactor and fossil fuel to meet base-load and peak electrical demands. The high temperature gas turbine produces shaft power to turn an electric generator. The hot exhaust is then fed to a heat recovery steam generator (HRSG) that provides steam to a steam turbine for added electrical power production. A simplified computational model of the thermal power conversion system was developed in order to parametrically investigate two different steady-state operation conditions: base load nuclear heat only from an Advanced High Temperature Reactor (AHTR), and combined nuclear heat with fossil heat to increase the turbine inlet temperature. These two cases bracket the expected range of power levels, where any intermediate power level can result during electrical load following. The computed results indicate that combined nuclear-fossil systems have the potential to offer both low-cost base-load electricity and lower-cost peak power relative to the existing combination of base-load nuclear plants and separate fossil-fired peak-electricity production units. In addition, electric grid stability, reduced greenhouse gases, and operational flexibility can also result with using the conventional technology presented here for the thermal power conversion system coupled with the AHTR. (authors)

  20. Base-Load and Peak Electricity from a Combined Nuclear Heat and Fossil Combined-Cycle Plant

    SciTech Connect (OSTI)

    Conklin, Jim; Forsberg, Charles W

    2007-01-01

    A combined-cycle power plant is proposed that uses heat from a high-temperature reactor and fossil fuel to meet base-load and peak electrical demands. The high-temperature gas turbine produces shaft power to turn an electric generator. The hot exhaust is then fed to a heat recovery steam generator (HRSG) that provides steam to a steam turbine for added electrical power production. A simplified computational model of the thermal power conversion system was developed in order to parametrically investigate two different steady-state operation conditions: base load nuclear heat only from an Advanced High Temperature Reactor (AHTR), and combined nuclear heat with fossil heat to increase the turbine inlet temperature. These two cases bracket the expected range of power levels, where any intermediate power level can result during electrical load following. The computed results indicate that combined nuclear-fossil systems have the potential to offer both low-cost base-load electricity and lower-cost peak power relative to the existing combination of base-load nuclear plants and separate fossil-fired peak-electricity production units. In addition, electric grid stability, reduced greenhouse gases, and operational flexibility can also result with using the conventional technology presented here for the thermal power conversion system coupled with the AHTR.

  1. Advanced Nuclear Fuel Cycle Options

    SciTech Connect (OSTI)

    Roald Wigeland; Temitope Taiwo; Michael Todosow; William Halsey; Jess Gehin

    2010-06-01

    A systematic evaluation has been conducted of the potential for advanced nuclear fuel cycle strategies and options to address the issues ascribed to the use of nuclear power. Issues included nuclear waste management, proliferation risk, safety, security, economics and affordability, and sustainability. The two basic strategies, once-through and recycle, and the range of possibilities within each strategy, are considered for all aspects of the fuel cycle including options for nuclear material irradiation, separations if needed, and disposal. Options range from incremental changes to todays implementation to revolutionary concepts that would require the development of advanced nuclear technologies.

  2. Standard for the qualification of high capacity fossil fuel fired plant operators

    SciTech Connect (OSTI)

    Axtman, W.

    1996-12-31

    The American Society of Mechanical Engineers, at the request of the U.S. Environmental Protection Agency (EPA) and, in recognition of the needs and benefits associated with standard qualifications of operators of high capacity fossil fuel fired plants, established the Qualifications of High Capacity Fossil Fuel Fired Operator (QFO) Committee in 1994. The purpose of the QFO Committee is to develop and maintain such a standard for operators. This standard includes qualifications, duties, responsibilities and the certification requirements for operators as appropriate to The Clean Air Act as amended in 1990 for fossil fuel fired plants with inputs equal to or greater than 10,000 Btu/hr. This Standard does not cover the certification or validation of fossil plant operating procedures, operating practices, facility performance, nor compliance with any particular permit requirement. This standard recognizes the titles or positions to which any particular fossil plant operator may apply, will vary within a facility. Therefore, this standard does not attempt to identify the individual who is required to obtain certification in any class designation. The fossil plant owner is urged to contact the local jurisdiction in which the fossil plant is located in this regard. This standard does not in itself require certification but rather it serves as a means for complying with federal, state, and local regulations which require operators of fossil fuel fired boilers with inputs equal to or greater than 10,000,000 But/hr to be certified. Safety codes and standards are intended to enhance public health and safety. Revisions to this Standard result from committee considerations of factors such as technological advances, new data, and changing environmental and industry needs. Revisions do not imply that previous editions of this standard were inadequate.

  3. Municipal waste combustion assessment: Fossil fuel co-firing. Final report, October 1988-July 1989

    SciTech Connect (OSTI)

    Landrum, V.J.; Barton, R.G.

    1989-07-01

    The report identifies refuse derived fuel (RDF) processing operations and various RDF types; describes such fossil fuel co-firing techniques as coal fired spreader stokers, pulverized coal wall fired boilers, pulverized coal tangentially fired boilers, and cyclone fired boilers; and describes the population of coal fired boilers that currently co-fire RDF, have previously co-fired RDF but have ceased to do so, and have been used in RDF co-firing demonstrations. (Fossil fuel co-firing, defined as the combustion of RDF with another fuel (usually coal) in a device designed primarily to burn the other fuel, is generally confined to commercial and utility boilers.) Model plants are developed and good combustion practices are recommended.

  4. Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2014

    U.S. Energy Information Administration (EIA) Indexed Site

    Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2014 July 2015 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Sales of Fossil Fuels Produced on Federal and Indian Lands, FY 2003 through FY 2014 i This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data,

  5. Combustion system for hybrid solar fossil fuel receiver

    DOE Patents [OSTI]

    Mehos, Mark S.; Anselmo, Kenneth M.; Moreno, James B.; Andraka, Charles E.; Rawlinson, K. Scott; Corey, John; Bohn, Mark S.

    2004-05-25

    A combustion system for a hybrid solar receiver comprises a pre-mixer which combines air and fuel to form an air-fuel mixture. The mixture is introduced tangentially into a cooling jacket. A burner plenum is fluidically connected to the cooling jacket such that the burner plenum and the cooling jacket are arranged in thermal contact with one another. The air-fuel mixture flows through the cooling jacket cooling the burner plenum to reduce pre-ignition of the air-fuel mixture in the burner plenum. A combustion chamber is operatively associated with and open to the burner plenum to receive the air-fuel mixture from the burner plenum. An igniter is operatively positioned in the combustion chamber to combust the air-fuel mixture, releasing heat. A recuperator is operatively associated with the burner plenum and the combustion chamber and pre-heats the air-fuel mixture in the burner plenum with heat from the combustion chamber. A heat-exchanger is operatively associated and in thermal contact with the combustion chamber. The heat-exchanger provides heat for the hybrid solar receiver.

  6. Modeling the Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Jacob J. Jacobson; A. M. Yacout; G. E. Matthern; S. J. Piet; A. Moisseytsev

    2005-07-01

    The Advanced Fuel Cycle Initiative is developing a system dynamics model as part of their broad systems analysis of future nuclear energy in the United States. The model will be used to analyze and compare various proposed technology deployment scenarios. The model will also give a better understanding of the linkages between the various components of the nuclear fuel cycle that includes uranium resources, reactor number and mix, nuclear fuel type and waste management. Each of these components is tightly connected to the nuclear fuel cycle but usually analyzed in isolation of the other parts. This model will attempt to bridge these components into a single model for analysis. This work is part of a multi-national laboratory effort between Argonne National Laboratory, Idaho National Laboratory and United States Department of Energy. This paper summarizes the basics of the system dynamics model and looks at some results from the model.

  7. Boiler and steam generator corrosion: Fossil fuel power plants. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    The bibliography contains citations concerning corrosion effects, mechanisms, detection, and inhibition in fossil fuel fired boilers. Fluidized bed combustors and coal gasification are included in the applications. The citations examine hot corrosion, thermal mechanical degradation, and intergranular oxidation corrosion studies performed on the water side and hot gas side of heat exchanger tubes and support structures. Coatings and treatment of material to inhibit corrosion are discussed. Corrosion affecting nuclear powered steam generators is examined in a separate bibliography. (Contains a minimum of 85 citations and includes a subject term index and title list.)

  8. Boiler and steam generator corrosion: Fossil fuel power plants. (Latest citations from the NTIS database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1993-01-01

    The bibliography contains citations concerning corrosion effects, mechanisms, detection, and inhibition in fossil fuel fired boilers. Fluidized bed combustors and coal gasification are included in the applications. The citations examine hot corrosion, thermal mechanical degradation, and intergranular oxidation corrosion studies performed on the water side and hot gas side of heat exchanger tubes and support structures. Coatings and treatment of material to inhibit corrosion are discussed. Corrosion affecting nuclear powered steam generators is examined in a separate bibliography. (Contains a minimum of 84 citations and includes a subject term index and title list.)

  9. Boiler and steam generator corrosion: Fossil fuel power plants. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    1996-03-01

    The bibliography contains citations concerning corrosion effects, mechanisms, detection, and inhibition in fossil fuel fired boilers. Fluidized bed combustors and coal gasification are included in the applications. The citations examine hot corrosion, thermal mechanical degradation, and intergranular oxidation corrosion studies performed on the water side and hot gas side of heat exchanger tubes and support structures. Coatings and treatment of material to inhibit corrosion are discussed. Corrosion affecting nuclear powered steam generators is examined in a separate bibliography. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  10. Boiler and steam generator corrosion: Fossil fuel power plants. (Latest citations from the NTIS Bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1994-11-01

    The bibliography contains citations concerning corrosion effects, mechanisms, detection, and inhibition in fossil fuel fired boilers. Fluidized bed combustors and coal gasification are included in the applications. The citations examine hot corrosion, thermal mechanical degradation, and intergranular oxidation corrosion studies performed on the water side and hot gas side of heat exchanger tubes and support structures. Coatings and treatment of material to inhibit corrosion are discussed. Corrosion affecting nuclear powered steam generators is examined in a separate bibliography. (Contains a minimum of 119 citations and includes a subject term index and title list.)

  11. Boiler and steam generator corrosion: Fossil fuel power plants. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    1996-11-01

    The bibliography contains citations concerning corrosion effects, mechanisms, detection, and inhibition in fossil fuel fired boilers. Fluidized bed combustors and coal gasification are included in the applications. The citations examine hot corrosion, thermal mechanical degradation, and intergranular oxidation corrosion studies performed on the water side and hot gas side of heat exchanger tubes and support structures. Coatings and treatment of material to inhibit corrosion are discussed. Corrosion affecting nuclear powered steam generators is examined in a separate bibliography. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  12. CO2 emissions mitigation and fossil fuel markets: Dynamic and international aspects of climate policies

    SciTech Connect (OSTI)

    Bauer, Nico; Bosetti, Valentina; Hamdi-Cherif, Meriem; Kitous, Alban; McCollum, David; Mejean, Aurelie; Rao, Shilpa; Turton, Hal; Paroussos, Leonidas; Ashina, Shuichi; Calvin, Katherine V.; Wada, Kenichi; Van Vuuren, Detlef

    2015-01-01

    This paper explores a multi-model scenario ensemble to assess the impacts of idealized and non-idealized climate change stabilization policies on fossil fuel markets. Under idealized conditions climate policies significantly reduce coal use in the short- and long-term. Reductions in oil and gas use are much smaller, particularly until 2030, but revenues decrease much more because oil and gas prices are higher and decrease with mitigation. A first deviation from the optimal transition pathway relaxes global emission targets until 2030, in accordance with the Copenhagen pledges and regionally-specific low-carbon technology targets. Fossil fuel markets revert back to the no-policy case: though coal use increases strongest, revenue gains are higher for oil and gas. To balance the carbon budget over the 21st century, the long-term reallocation of fossil fuels is significantly larger - twice and more - than the short-term distortion. This amplifying effect results from coal lock-in and inter-fuel substitution effects. The second deviation from the optimal transition pathway relaxes the global participation assumption. The result here is less clear cut across models, as we find carbon leakage effects ranging from positive to negative because leakage and substitution patterns of coal, oil, and gas differ. In summary, distortions of fossil fuel markets resulting from relaxed short-term global emission targets are more important and less uncertain than the issue of carbon leakage from early mover action.

  13. CO₂ emission mitigation and fossil fuel markets: Dynamic and international aspects of climate policies

    SciTech Connect (OSTI)

    Bauer, Nico; Bosetti, Valentina; Hamdi-Cherif, Meriem; Kitous, Alban; McCollum, David; Mejean, Aurelie; Rao, Shilpa; Turton, Hal; Paroussos, Leonidas; Ashina, Shuichi; Calvin, Katherine; Wada, Kenichi; van Vuuren, Detlef

    2015-01-01

    This paper explores a multi-model scenario ensemble to assess the impacts of idealized and non-idealized climate change stabilization policies on fossil fuel markets. Under idealized conditions climate policies significantly reduce coal use in the short- and long-term. Reductions in oil and gas use are much smaller, particularly until 2030, but revenues decrease much more because oil and gas prices are higher than coal prices. A first deviation from optimal transition pathways is delayed action that relaxes global emission targets until 2030 in accordance with the Copenhagen pledges. Fossil fuel markets revert back to the no-policy case: though coal use increases strongest, revenue gains are higher for oil and gas. To balance the carbon budget over the 21st century, the long-term reallocation of fossil fuels is significantly larger—twice and more—than the short-term distortion. This amplifying effect results from coal lock-in and inter-fuel substitution effects to balance the full-century carbon budget. The second deviation from the optimal transition pathway relaxes the global participation assumption. The result here is less clear-cut across models, as we find carbon leakage effects ranging from positive to negative because trade and substitution patterns of coal, oil, and gas differ across models. In summary, distortions of fossil fuel markets resulting from relaxed short-term global emission targets are more important and less uncertain than the issue of carbon leakage from early mover action.

  14. FUEL ELEMENT FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Bassett, C.H.

    1961-05-16

    A fuel element particularly adapted for use in nuclear reactors of high power density is offered. It has fissionable fuel pellet segments mounted in a tubular housing and defining a central passage in the fuel element. A burnable poison element extends through the central passage, which is designed to contain more poison material at the median portion than at the end portions thereby providing a more uniform hurnup and longer reactivity life.

  15. Categorization of Used Nuclear Fuel Inventory in Support of a...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    National Nuclear Fuel Cycle Strategy Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy The Office of Nuclear Energy ...

  16. Direct Carbon Conversion: Application to the Efficient Conversion of Fossil Fuels to Electricity

    SciTech Connect (OSTI)

    Cooper, J F; Cherepy, N; Berry, G; Pasternak, A; Surles, T; Steinberg, M

    2001-03-07

    We introduce a concept for efficient conversion of fossil fuels to electricity that entails the decomposition of fossil-derived hydrocarbons into carbon and hydrogen, and electrochemical conversion of these fuels in separate fuel cells. Carbon/air fuel cells have the advantages of near zero entropy change and associated heat production (allowing 100% theoretical conversion efficiency). The activities of the C fuel and CO{sub 2} product are invariant, allowing constant EMF and full utilization of fuel in single pass mode of operation. System efficiency estimates were conducted for several routes involving sequential extraction of a hydrocarbon from the fossil resource by (hydro) pyrolysis followed by thermal decomposition. The total energy conversion efficiencies of the processes were estimated to be (1) 80% for direct conversion of petroleum coke; (2) 67% HHV for CH{sub 4}; (3) 72% HHV for heavy oil (modeled using properties of decane); (4) 75.5% HHV (83% LHV) for natural gas conversion with a Rankine bottoming cycle for the H{sub 2} portion; and (5) 69% HHV for conversion of low rank coals and lignite through hydrogenation and pyrolysis of the CH{sub 4} intermediate. The cost of carbon fuel is roughly $7/GJ, based on the cost of the pyrolysis step in the industrial furnace black process. Cell hardware costs are estimated to be less than $500/kW.

  17. NUCLEAR REACTOR FUEL SYSTEMS

    DOE Patents [OSTI]

    Thamer, B.J.; Bidwell, R.M.; Hammond, R.P.

    1959-09-15

    Homogeneous reactor fuel solutions are reported which provide automatic recombination of radiolytic gases and exhibit large thermal expansion characteristics, thereby providing stability at high temperatures and enabling reactor operation without the necessity of apparatus to recombine gases formed by the radiolytic dissociation of water in the fuel and without the necessity of liquid fuel handling outside the reactor vessel except for recovery processes. The fuels consist of phosphoric acid and water solutions of enriched uranium, wherein the uranium is in either the hexavalent or tetravalent state.

  18. NUCLEAR REACTOR FUEL ELEMENT

    DOE Patents [OSTI]

    Anderson, W.F.; Tellefson, D.R.; Shimazaki, T.T.

    1962-04-10

    A plate type fuel element which is particularly useful for organic cooled reactors is described. Generally, the fuel element comprises a plurality of fissionable fuel bearing plates held in spaced relationship by a frame in which the plates are slidably mounted in grooves. Clearance is provided in the grooves to allow the plates to expand laterally. The plates may be rigidly interconnected but are floatingly supported at their ends within the frame to allow for longi-tudinal expansion. Thus, this fuel element is able to withstand large temperature differentials without great structural stresses. (AEC)

  19. Steam-reforming of fossil fuels and wastes to produce energy and chemicals without greenhouse gases

    SciTech Connect (OSTI)

    Galloway, T.R.

    1998-07-01

    Worldwide concern has demanded a re-examination of the energy- and chemical-producing plants that use fossil fuel sources and release large quantities of greenhouse gases. Plant retrofits with steam-reformer/gasifiers will increase plant efficiencies, improve economics and avoid releasing troublesome amounts of greenhouse gases, such as carbon dioxide. In this paper, the authors describe and illustrate the several new steam-reforming/gasification plants that are processing waste streams and fossil fuels. These plants range in size from 1 ton/day to 2,000 tons/day. They are commercial and economically successful. These new concepts can be used to both upgrade fossil plants for improved economics while eliminating the release of greenhouse gases. By aggressively retrofitting old coal plants and sequestering CO{sub 2}, a 15% reduction in 1990 CO{sub 2} emissions can be met by the US by 2010.

  20. NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 05 NUCLEAR FUELS...

    Office of Scientific and Technical Information (OSTI)

    Title list of documents made publicly available, January 1-31, 1998 NONE 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 05 NUCLEAR FUELS; BIBLIOGRAPHIES; NUCLEAR POWER PLANTS;...

  1. An overview of alternative fossil fuel price and carbon regulation scenarios

    SciTech Connect (OSTI)

    Wiser, Ryan; Bolinger, Mark

    2004-10-01

    The benefits of the Department of Energy's research and development (R&D) efforts have historically been estimated under business-as-usual market and policy conditions. In recognition of the insurance value of R&D, however, the Office of Energy Efficiency and Renewable Energy (EERE) and the Office of Fossil Energy (FE) have been exploring options for evaluating the benefits of their R&D programs under an array of alternative futures. More specifically, an FE-EERE Scenarios Working Group (the Working Group) has proposed to EERE and FE staff the application of an initial set of three scenarios for use in the Working Group's upcoming analyses: (1) a Reference Case Scenario, (2) a High Fuel Price Scenario, which includes heightened natural gas and oil prices, and (3) a Carbon Cap-and-Trade Scenario. The immediate goal is to use these scenarios to conduct a pilot analysis of the benefits of EERE and FE R&D efforts. In this report, the two alternative scenarios being considered by EERE and FE staff--carbon cap-and-trade and high fuel prices--are compared to other scenarios used by energy analysts and utility planners. The report also briefly evaluates the past accuracy of fossil fuel price forecasts. We find that the natural gas prices through 2025 proposed in the FE-EERE Scenarios Working Group's High Fuel Price Scenario appear to be reasonable based on current natural gas prices and other externally generated gas price forecasts and scenarios. If anything, an even more extreme gas price scenario might be considered. The price escalation from 2025 to 2050 within the proposed High Fuel Price Scenario is harder to evaluate, primarily because few existing forecasts or scenarios extend beyond 2025, but, at first blush, it also appears reasonable. Similarly, we find that the oil prices originally proposed by the Working Group in the High Fuel Price Scenario appear to be reasonable, if not conservative, based on: (1) the current forward market for oil, (2) current oil prices, (3) externally generated oil price forecasts, and (4) the historical difficulty in accurately forecasting oil prices. Overall, a spread between the FE-EERE High Oil Price and Reference scenarios of well over $8/bbl is supported by the literature. We conclude that a wide range of carbon regulation scenarios are possible, especially within the time frame considered by EERE and FE (through 2050). The Working Group's Carbon Cap-and-Trade Scenario is found to be less aggressive than many Kyoto-style targets that have been analyzed, and similar in magnitude to the proposed Climate Stewardship Act. The proposed scenario is more aggressive than some other scenarios found in the literature, however, and ignores carbon banking and offsets and does not allow nuclear power to expand. We are therefore somewhat concerned that the stringency of the proposed carbon regulation scenario in the 2010 to 2025 period will lead to a particularly high estimated cost of carbon reduction. As described in more detail later, we encourage some flexibility in the Working Group's ultimate implementation of the Carbon Cap-and-Trade Scenario. We conclude by identifying additional scenarios that might be considered in future analyses, describing a concern with the proposed specification of the High Fuel Price Scenario, and highlighting the possible difficulty of implementing extreme scenarios with current energy modeling tools.

  2. NUCLEAR REACTOR FUEL ELEMENT

    DOE Patents [OSTI]

    Currier, E.L. Jr.; Nicklas, J.H.

    1963-06-11

    A fuel plate is designed for incorporation into control rods of the type utilized in high-flux test reactors. The fuel plate is designed so that the portion nearest the poison section of the control rod contains about one-half as much fissionable material as in the rest of the plate, thereby eliminating dangerous flux peaking in that portion. (AEC)

  3. Spent Nuclear Fuel Project Safety Management Plan

    SciTech Connect (OSTI)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities.

  4. Nuclear Fuel Cycle Options Catalog

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Options Catalog - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  5. Liquid fossil-fuel technology. Quarterly technical progress report, April-June 1982

    SciTech Connect (OSTI)

    Linville, B.

    1982-10-01

    This report primarily covers in-house oil, gas, and synfuel research and lists the contracted research. The report is broken into the following areas: liquid fossil fuel cycle, extraction, processing, utilization, and project integration and technology transfer. BETC publications are listed. (DLC)

  6. Impacts of Wind and Solar on Fossil-Fueled Generators: Preprint

    SciTech Connect (OSTI)

    Lew, D.; Brinkman, G.; Kumar, N.; Besuner, P.; Agan, D.; Lefton, S.

    2012-08-01

    High penetrations of wind and solar power will impact the operations of the remaining generators on the power system. Regional integration studies have shown that wind and solar may cause fossil-fueled generators to cycle on and off and ramp down to part load more frequently and potentially more rapidly. Increased cycling, deeper load following, and rapid ramping may result in wear-and-tear impacts on fossil-fueled generators that lead to increased capital and maintenance costs, increased equivalent forced outage rates, and degraded performance over time. Heat rates and emissions from fossil-fueled generators may be higher during cycling and ramping than during steady-state operation. Many wind and solar integration studies have not taken these increased cost and emissions impacts into account because data have not been available. This analysis considers the cost and emissions impacts of cycling and ramping of fossil-fueled generation to refine assessments of wind and solar impacts on the power system.

  7. FUEL ELEMENT FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Bassett, C.H.

    1961-05-01

    A nuclear reactor fuel element comprising high density ceramic fissionable material enclosed in a tubular cladding of corrosion-resistant material is described. The fissionable material is in the form of segments of a tube which have cooperating tapered interfaces which produce outward radial displacement when the segments are urged axially together. A resilient means is provided within the tubular housing to constantly urge the fuel segments axially. This design maintains the fuel material in tight contacting engagement against the inner surface of the outer cladding tube to eliminate any gap therebetween which may be caused by differential thermal expansion between the fuel material and the material of the tube.

  8. Nuclear Fuels: Promise and Limitations

    SciTech Connect (OSTI)

    Harold F. McFarlane

    2012-03-01

    From 1950 through 1980, scientists, engineers and national leaders confidently predicted an early twenty-first century where fast breeder reactors and commercial nuclear fuel reprocessing were commonplace. Such a scenario seemed necessary for a world with the more than 1000 GWe of nuclear energy needed to meet such an ever-increasing thirst for energy. Thirty years later uranium reserves are increasing on pace with consumption, the growth of nuclear power has been slowed, commercial breeder reactors have yet to enter the marketplace, and less than a handful of commercial reprocessing plants operate. As Nobel Laureate Niels Bohr famously said, Prediction is very difficult, especially if its about the future. The programme for IChemEs 2012 conference on the nuclear fuel cycle features a graphic of an idealized nuclear fuel cycle that symbolizes the quest for a closed nuclear fuel cycle featuring careful husbanding of precious resources while minimizing the waste footprint. Progress toward achieving this ideal has been disrupted by technology innovations in the mining and petrochemical industries, as well as within the nuclear industry.

  9. Environmental impact of fossil fuel combustion in power generation

    SciTech Connect (OSTI)

    Allen, J.W.; Beal, P.R.

    1996-12-31

    All the recent developments in the combustion systems employed for power generation have been based on environmental considerations. Combustion modifications have been developed and utilised in order to control NO{sub x} emissions and improvements continue to be made as the legislative requirements tighten. Chemical processes and fuel switching are used to control SO{sub x} emissions. After nitrogen, carbon dioxide is the major gas emitted from the combustion process and its potential potency as a greenhouse gas is well documented. Increased efficiency cycles, mainly based on natural gas as the prime fuel, can minimise the amount of CO{sub x} produced per unit of power generated. As the economics of natural gas utilisation become less favourable a return to clean coal technology based power generation processes may be required.

  10. Orimulsion conversion boosts prospects of `fourth` fossil fuel

    SciTech Connect (OSTI)

    1995-04-01

    This article describes how, by retrofitting a 100-MW oil-fired and a 215-MW coal-fired unit, one utility turned a plant destined for peaking service into a base-load asset with a predictable fuel bill and manageable emissions-even in environmentally sensitive Atlantic Canada. Six years ago, New Brunswick Power Corp (NB Power) found itself on the horns of a dilemma. For years, the utility had been searching for a powerplant fuel with a more stable price than oil, which at the time was fueling one-third of its generating capacity. Buying and burning more domestic coal-even at twice the price of offshore supplies-was the preferred option, because that would also help keep New Brunswick`s coal mines open. But by 1989, federal and provincial legislation had begun to plan for stringent limits on SO{sub 2} emissions that would take the local-coal card out of NB Power`s hand. Containing up to 8% sulfur, New Brunswick coal would be too dirty to burn by itself; emissions from a 200-MW unit would alone use up nearly half of the utility`s system-wide annual quota for SO{sub 2} emissions schedules for imposition in 1994. Enter Bitor America Corp, the Boca Raton (Fla) marketing subsidiary of the world`s third-largest oil company, Petroleos de Venezuela SA (PdVSA). Looking to further the fortunes of Orimulsion, a liquid emulsion of bitumen and water from the Orinoco region of Venezuela, Bitor funded and provided technical support for the first large-scale test burn of the fuel in the 100-MW Unit 1 of NB Power`s Dalhousie station in northern New Brunswick. After making the required modifications, NB Power burned Orimulsion in Unit 1 for two years. By 1991, the utility had cleanly converted more than a million barrels of the fuel to nearly half a million megawatt-hours of electricity-in the process finding few reasons not to commit to permanently converting Dalhousie`s Unit 1, as well as coal fired 215-MW Unit 2, to burn Orimulsion.

  11. Nuclear Fuel Cycle

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering ...

  12. Hydrogen milestone could help lower fossil fuel refining costs

    ScienceCinema (OSTI)

    McGraw, Jennifer

    2013-05-28

    Hydrogen researchers at the U.S. Department of Energy's Idaho National Laboratory have reached another milestone on the road to reducing carbon emissions and protecting the nation against the effects of peaking world oil production. Stephen Herring, laboratory fellow and technical director of the INL High Temperature Electrolysis team, today announced that the latest fuel cell modification has set a new mark in endurance. The group's Integrated Laboratory Scale experiment has now operated continuously for 2,583 hours at higher efficiencies than previously attained. Learn more about INL research at http://www.facebook.com/idahonationallaboratory.

  13. Timing is everything : along the fossil fuel transition pathway.

    SciTech Connect (OSTI)

    Kobos, Peter Holmes; Walker, La Tonya Nicole; Malczynski, Leonard A.

    2013-10-01

    People save for retirement throughout their career because it is virtually impossible to save all you'll need in retirement the year before you retire. Similarly, without installing incremental amounts of clean fossil, renewable or transformative energy technologies throughout the coming decades, a radical and immediate change will be near impossible the year before a policy goal is set to be in place. Therefore, our research question is,To meet our desired technical and policy goals, what are the factors that affect the rate we must install technology to achieve these goals in the coming decades?' Existing models do not include full regulatory constraints due to their often complex, and inflexible approaches to solve foroptimal' engineering instead ofrobust' and multidisciplinary solutions. This project outlines the theory and then develops an applied software tool to model the laboratory-to-market transition using the traditional technology readiness level (TRL) framework, but develops subsequent and a novel regulatory readiness level (RRL) and market readiness level (MRL). This tool uses the ideally-suited system dynamics framework to incorporate feedbacks and time delays. Future energy-economic-environment models, regardless of their programming platform, may adapt this software model component framework ormodule' to further vet the likelihood of new or innovative technology moving through the laboratory, regulatory and market space. The prototype analytical framework and tool, called the Technology, Regulatory and Market Readiness Level simulation model (TRMsim) illustrates the interaction between technology research, application, policy and market dynamics as they relate to a new or innovative technology moving from the theoretical stage to full market deployment. The initial results that illustrate the model's capabilities indicate for a hypothetical technology, that increasing the key driver behind each of the TRL, RRL and MRL components individually decreases the time required for the technology to progress through each component by 63, 68 and 64%, respectively. Therefore, under the current working assumptions, to decrease the time it may take for a technology to move from the conceptual stage to full scale market adoption one might consider expending additional effort to secure regulatory approval and reducing the uncertainty of the technology's demand in the marketplace.

  14. Nuclear Fuel Cycle | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Cycle Nuclear Fuel Cycle This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. The mission of NE-54 is primarily focused on activities related to the front end of the nuclear fuel cycle which includes mining,

  15. Nuclear reactor composite fuel assembly

    DOE Patents [OSTI]

    Burgess, Donn M.; Marr, Duane R.; Cappiello, Michael W.; Omberg, Ronald P.

    1980-01-01

    A core and composite fuel assembly for a liquid-cooled breeder nuclear reactor including a plurality of elongated coextending driver and breeder fuel elements arranged to form a generally polygonal bundle within a thin-walled duct. The breeder elements are larger in cross section than the driver elements, and each breeder element is laterally bounded by a number of the driver elements. Each driver element further includes structure for spacing the driver elements from adjacent fuel elements and, where adjacent, the thin-walled duct. A core made up of the fuel elements can advantageously include fissile fuel of only one enrichment, while varying the effective enrichment of any given assembly or core region, merely by varying the relative number and size of the driver and breeder elements.

  16. Assessment of a multi-stage underwater vehicle concept using a fossil-fuel Stirling engine

    SciTech Connect (OSTI)

    Reader, G.T.; Potter, I.J.

    1995-12-31

    The Stirling Engine because of its inherent closed-cycle operation can be readily modified to work in an airless environment even if the primary source of energy is a fossil fuel. Thus, Stirling engines are well suited for use in the underwater environment and have been operated successfully in manned military submarines since the early 1980s. In recent years fossil fueled Stirling systems have been also proposed for use in small unmanned underwater vehicles (UUVs). However, in this case the need to carry an onboard oxygen supply in a very confined space has presented a number of design difficulties. These are identified in the paper. However, if the oxidant supply to the engine is provided by the membrane extraction of dissolved oxygen from seawater and/or disposable fuel/oxidant pods are used then the UUV Stirling system becomes more attractive. If this latter concept is extended to include multi-stage vehicles then it can be shown that fossil fueled Stirlings could also be put to effective use in long range-long endurance underwater vehicular operations.

  17. Chlorine induced corrosion of steels in fossil fuel power plants

    SciTech Connect (OSTI)

    Spiegel, M.; Grabke, H.J.

    1998-12-31

    The corrosion of steels in power plants (coal combustion, waste incineration) is mainly due to condensed chlorides in the ash deposited on the boiler tubes. These chlorides are stabilized by HCl in the combustion gas. In the case of coal as a fuel, chlorine is present as chloride minerals in the raw material which is converted to HCl during the combustion process. Corrosion of steels in chlorine containing environments occurs by the active oxidation mechanism, which is a self-sustaining accelerated oxidation process, catalyzed by chlorine. This study shows that solid chlorides react with the oxide scale of the steels to form chlorine, which initiates active oxidation. In order to prevent chlorine induced corrosion, the deposition of chlorides on the tubes within the coal ash must be avoided. This is possible by the presence of SO{sub 2}, which is present in the combustion gas, converting the chlorides to sulfates in the gas phase. The paper presents an example of a failure case in a coal fired plant in Germany. In this plant, chlorine induced corrosion was observed after effective removal of SO{sub 2} by additions of CaO. From thermodynamic calculations it can be shown that a certain amount of SO{sub 2} is necessary in order to avoid deposition of chlorides and to prevent corrosion.

  18. Further experience for environmental improvement in fossil fuel combustion

    SciTech Connect (OSTI)

    Lazzeri, L.; Santis, R. de

    1998-12-31

    Reburning is a technology which has proven, by plant demonstration, capable of providing compliance with very stringent regulatory emissions requests (less than 90 ppm NO{sub x} firing oil and gas and less than 160--170 ppm firing coal). Designing a Reburn System requires a contemporary control of many parameters like flow rates, local stoichiometries residence times, etc.; it also requires the availability and capability of using complex and sophisticated numerical modeling. Although the system can be adapted to any already installed hardware it should be noted that the availability of reliable LNB`s and of specifically designed OFA`s and Reburn fuel injectors can greatly enhance the system performance. Design of OFA system is a subcase of a Reburn System design, as it implies same concepts of mixing and residence times which are the basis of Reburn System. As shown in the cases previously presented Reburning always provides additional margins to OFA operation specifically when very low emission limits are pursued. Finally it should be noted that the use of Reburning may create problems of unburned specifically when very low local stoichiometries and when very low sulfur oils are used which are often characterized by asphaltene instability especially when STZ oil is the result of blending high and low sulfur oils. A specific know-how has been jointly developed by Ansaldo and ENEL to solve these problems acting on both atomizer type selection and operation.

  19. CO₂ emission mitigation and fossil fuel markets: Dynamic and international aspects of climate policies

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Bauer, Nico; Bosetti, Valentina; Hamdi-Cherif, Meriem; Kitous, Alban; McCollum, David; Mejean, Aurelie; Rao, Shilpa; Turton, Hal; Paroussos, Leonidas; Ashina, Shuichi; et al

    2015-01-01

    This paper explores a multi-model scenario ensemble to assess the impacts of idealized and non-idealized climate change stabilization policies on fossil fuel markets. Under idealized conditions climate policies significantly reduce coal use in the short- and long-term. Reductions in oil and gas use are much smaller, particularly until 2030, but revenues decrease much more because oil and gas prices are higher than coal prices. A first deviation from optimal transition pathways is delayed action that relaxes global emission targets until 2030 in accordance with the Copenhagen pledges. Fossil fuel markets revert back to the no-policy case: though coal use increasesmore » strongest, revenue gains are higher for oil and gas. To balance the carbon budget over the 21st century, the long-term reallocation of fossil fuels is significantly larger—twice and more—than the short-term distortion. This amplifying effect results from coal lock-in and inter-fuel substitution effects to balance the full-century carbon budget. The second deviation from the optimal transition pathway relaxes the global participation assumption. The result here is less clear-cut across models, as we find carbon leakage effects ranging from positive to negative because trade and substitution patterns of coal, oil, and gas differ across models. In summary, distortions of fossil fuel markets resulting from relaxed short-term global emission targets are more important and less uncertain than the issue of carbon leakage from early mover action.« less

  20. Protected Nuclear Fuel Element

    DOE Patents [OSTI]

    Kittel, J. H.; Schumar, J. F.

    1962-12-01

    A stainless steel-clad actinide metal fuel rod for use in fast reactors is reported. In order to prevert cladding failures due to alloy formation between the actinide metal and the stainless steel, a mesh-like sleeve of expanded metal is interposed between them, the sleeve metal being of niobium, tantalum, molybdenum, tungsten, zirconium, or vanadium. Liquid alkali metal is added as a heat transfer agent. (AEC)

  1. Fossil fuel-fired peak heating for geothermal greenhouses

    SciTech Connect (OSTI)

    Rafferty, K.

    1997-01-01

    Greenhouses are a major application of low-temperature geothermal resources. In virtually all operating systems, the geothermal fluid is used in a hot water heating system to meet 100% of both the peak and annual heating requirements of the structure. This strategy is a result of the relatively low costs associated with the development of most US geothermal direct-use resources and past tax credit programs which penalized systems using any conventional fuel sources. Increasingly, greenhouse operations will encounter limitations in available geothermal resource flow due either to production or disposal considerations. As a result, it will be necessary to operate additions at reduced water temperatures reflective of the effluent from the existing operations. Water temperature has a strong influence on heating system design. Greenhouse operators tend to have unequivocal preferences regarding heating system equipment. Many growers, particularly cut flower and bedding plant operators, prefer the {open_quotes}bare tube{close_quotes} type heating system. This system places small diameter plastic tubes under the benches or adjacent to the plants. Hot water is circulated through the tubes providing heat to the plants and the air in the greenhouse. Advantages include the ability to provide the heat directly to the plants, low cost, simple installation and the lack of a requirement for fans to circulate air. The major disadvantage of the system is poor performance at low (<140{degrees}F) water temperatures, particularly in cold climates. Under these conditions, the quantity of tubing required to meet the peak heating load is substantial. In fact, under some conditions, it is simply impractical to install sufficient tubing in the greenhouse to meet the peak heating load.

  2. World nuclear fuel cycle requirements 1991

    SciTech Connect (OSTI)

    Not Available

    1991-10-10

    The nuclear fuel cycle consists of mining and milling uranium ore, processing the uranium into a form suitable for generating electricity, burning'' the fuel in nuclear reactors, and managing the resulting spent nuclear fuel. This report presents projections of domestic and foreign requirements for natural uranium and enrichment services as well as projections of discharges of spent nuclear fuel. These fuel cycle requirements are based on the forecasts of future commercial nuclear power capacity and generation published in a recent Energy Information Administration (EIA) report. Also included in this report are projections of the amount of spent fuel discharged at the end of each fuel cycle for each nuclear generating unit in the United States. The International Nuclear Model is used for calculating the projected nuclear fuel cycle requirements. 14 figs., 38 tabs.

  3. Fully ceramic nuclear fuel and related methods

    DOE Patents [OSTI]

    Venneri, Francesco; Katoh, Yutai; Snead, Lance Lewis

    2016-03-29

    Various embodiments of a nuclear fuel for use in various types of nuclear reactors and/or waste disposal systems are disclosed. One exemplary embodiment of a nuclear fuel may include a fuel element having a plurality of tristructural-isotropic fuel particles embedded in a silicon carbide matrix. An exemplary method of manufacturing a nuclear fuel is also disclosed. The method may include providing a plurality of tristructural-isotropic fuel particles, mixing the plurality of tristructural-isotropic fuel particles with silicon carbide powder to form a precursor mixture, and compacting the precursor mixture at a predetermined pressure and temperature.

  4. Table 3.1 Fossil Fuel Production Prices, 1949-2011 (Dollars per Million Btu)

    U.S. Energy Information Administration (EIA) Indexed Site

    Fossil Fuel Production Prices, 1949-2011 (Dollars per Million Btu) Year Coal 1 Natural Gas 2 Crude Oil 3 Fossil Fuel Composite 4 Nominal 5 Real 6 Nominal 5 Real 6 Nominal 5 Real 6 Nominal 5 Real 6 Percent Change 7 1949 0.21 1.45 0.05 0.37 0.44 3.02 0.26 1.81 – – 1950 .21 1.41 .06 .43 .43 2.95 [R] .26 1.74 -3.6 1951 .21 1.35 .06 .40 .44 2.78 .26 1.65 -5.4 1952 .21 1.31 [R] .07 .45 .44 2.73 .26 1.63 -1.0 1953 .21 1.29 .08 .50 .46 2.86 .27 1.69 3.3 1954 .19 1.18 .09 .55 .48 2.94 .28 1.70 .7 1955

  5. Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2014

    U.S. Energy Information Administration (EIA) Indexed Site

    Table 1. Fossil fuel sales of production from federal lands, FY 2003-14 Fiscal Year Crude Oil and Lease Condensate Natural Gas Plant Liquids 2 Natural Gas Coal Fossil Fuels Million Barrels 1 Trillion Btu Percent of U.S. Total Million Barrels 1 Trillion Btu Percent of U.S. Total Billion Cubic Feet 1 Trillion Btu Percent of U.S. Total Million Short Tons 1 Trillion Btu Percent of U.S. Total Trillion Btu Percent of U.S. Total 2003 679 3,939 33.0% 93 347 14.7% 6,798 6,981 35.7% 436 8,960 40.6%

  6. Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2014

    U.S. Energy Information Administration (EIA) Indexed Site

    3 Table 2. Fossil fuel sales of production from Indian lands, FY 2003-14 Fiscal Year Crude Oil and Lease Condensate Natural Gas Plant Liquids 2 Natural Gas Coal Fossil Fuels Million Barrels 1 Trillion Btu Percent of U.S. Total Million Barrels 1 Trillion Btu Percent of U.S. Total Billion Cubic Feet 1 Trillion Btu Percent of U.S. Total Million Short Tons 1 Trillion Btu Percent of U.S. Total Trillion Btu Percent of U.S. Total 2003 10 59 0.5% 2 6 0.3% 283 291 1.5% 30 616 2.8% 972 1.7% 2004 10 58

  7. In-situ FT-IR diagnostics for monitoring and control of fossil fuel combustion

    SciTech Connect (OSTI)

    Bonanno, A.S.; Wojtowicz, M.A.; Serio, M.A.; Nelson, C.M.; Solomon, P.R.

    1995-12-31

    This paper describes the development and testing of a prototype fourier transform infrared (FT-IR) based measurement system for continuous emission monitoring (CEM) and process control in fossil fuel-fired power plants. On several occasions, prototype systems have been transported and assembled at full-scale and pilot-scale fossil fuel-fired combustors. The in-situ version of the prototype is able to measure NH{sub 3} and HCl concentrations, which are difficult to measure extractively, as well as CO, CO{sub 2}, NO{sub x}, H{sub 2}O, and SO{sub x} concentrations. The results of recent tests will be presented which involve in-situ monitoring of selective non-catalytic reduction (SNCR) of NO{sub x} based on simultaneous measurement of NO, NH{sub 3} and CO.

  8. Long-term global nuclear energy and fuel cycle strategies

    SciTech Connect (OSTI)

    Krakowski, R.A.

    1997-09-24

    The Global Nuclear Vision Project is examining, using scenario building techniques, a range of long-term nuclear energy futures. The exploration and assessment of optimal nuclear fuel-cycle and material strategies is an essential element of the study. To this end, an established global E{sup 3} (energy/economics/environmental) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed using this multi-regional E{sup 3} model, wherein future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term demographic (population, workforce size and productivity), economic (price-, population-, and income-determined demand for energy services, price- and population-modified GNP, resource depletion, world-market fossil energy prices), policy (taxes, tariffs, sanctions), and top-level technological (energy intensity and end-use efficiency improvements) drivers. Using the framework provided by the global E{sup 3} model, the impacts of both external and internal drivers are investigated. The ability to connect external and internal drivers through this modeling framework allows the study of impacts and tradeoffs between fossil- versus nuclear-fuel burning, that includes interactions between cost, environmental, proliferation, resource, and policy issues.

  9. NREL: Technology Deployment - Fossil Fuel Dependency Falls from 100% to 56%

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    on Alcatraz Island Fossil Fuel Dependency Falls from 100% to 56% on Alcatraz Island News Solar Cells Light Up Prison Cells on 'The Rock' Sponsors U.S. National Park Service American Recovery and Reinvestment Act Key Partners National Park Service Golden Gate National Recreation Area National Park Service Denver Services Center Princeton Power Inc. University of Washington Lawrence Berkeley National Laboratory U.S. DOE Federal Energy Management Program Related Stories U.S. Virgin Islands

  10. March 2016 Most Viewed Documents for Fossil Fuels | OSTI, US Dept of

    Office of Scientific and Technical Information (OSTI)

    Energy, Office of Scientific and Technical Information Fossil Fuels EXPERIMENTAL AND THEORETICAL DETERMINATION OF HEAVY OIL VISCOSITY UNDER RESERVOIR CONDITIONS Dr. Jorge Gabitto; Maria Barrufet (2003) 310 Bamboo: An Overlooked Biomass Resource? Scurlock, J.M.O. (2000) 197 Solubility of methane in water under natural conditions: a laboratory study. Final report, April 1, 1978-June 30, 1982 Blount, C.W.; Price, L.C. (1982) 186 ADVANCED TECHNIQUES FOR RESERVOIR SIMULATION AND MODELING OF

  11. EMGeo: Risk Minimizing Software for Finding Offshore Fossil Fuels by Fluid

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Identification - Energy Innovation Portal Energy Analysis Energy Analysis Find More Like This Return to Search EMGeo: Risk Minimizing Software for Finding Offshore Fossil Fuels by Fluid Identification Lawrence Berkeley National Laboratory Contact LBL About This Technology Plots of electrical conductivity over the Troll Field in the North Sea produced by analyzing 3D electromagnetic field data. Plots of electrical conductivity over the Troll Field in the North Sea produced by analyzing 3D

  12. High capacity fossil fuel fired plant operator training program. Student handbook. Final report

    SciTech Connect (OSTI)

    Pearson, S.; Gardner, M.; Nguyen, Q.

    1994-09-30

    The operator of fossil fuel-fired boilers has a significant responsibility in assuring that the unit is continuously operated in a manner which complies with the various state and federal regulations. The course will emphasize the operating principles for all types of boilers and for all types of control equipment used for controlling air emissions from boilers. The course will emphasize the significant operating parameters that directly influence air emissions.

  13. Reduction of nitrogen oxide emissions from fossil fuels. (Latest citations from Pollution abstracts). Published Search

    SciTech Connect (OSTI)

    1997-05-01

    The bibliography contains citations concerning the removal of nitrogen compounds from fossil fuels and their post-combustion emissions. Removal methods include biological denitrification, fluidized bed combustion, and flue gas denitrification. Applications to utilities, petroleum refineries, and other industries are presented. The design of nitrogen control systems and process optimization are described. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  14. Reduction of nitrogen oxide emissions from fossil fuels. (Latest citations from Pollution abstracts). Published Search

    SciTech Connect (OSTI)

    1996-01-01

    The bibliography contains citations concerning the removal of nitrogen compounds from fossil fuels and their post-combustion emissions. Removal methods include biological denitrification, fluidized bed combustion, and flue gas denitrification. Applications to utilities, petroleum refineries, and other industries are presented. The design of nitrogen control systems and process optimization are described. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  15. Pilot Application to Nuclear Fuel Cycle Options

    Broader source: Energy.gov [DOE]

    A Screening Method for Guiding R&D Decisions: Pilot Application to Screen Nuclear Fuel Cycle Options

  16. NUCLEAR REACTOR FUEL ELEMENT ASSEMBLY

    DOE Patents [OSTI]

    Stengel, F.G.

    1963-12-24

    A method of fabricating nuclear reactor fuel element assemblies having a plurality of longitudinally extending flat fuel elements in spaced parallel relation to each other to form channels is presented. One side of a flat side plate is held contiguous to the ends of the elements and a welding means is passed along the other side of the platertransverse to the direction of the longitudinal extension of the elements. The setting and speed of travel of the welding means is set to cause penetration of the side plate with welds at bridge the gap in each channel between adjacent fuel elements with a weld-through bubble of predetermined size. The fabrication of a high strength, dependable fuel element is provided, and the reduction of distortion and high production costs are facilitated by this method. (AEC)

  17. Compositions and methods for treating nuclear fuel

    DOE Patents [OSTI]

    Soderquist, Chuck Z; Johnsen, Amanda M; McNamara, Bruce K; Hanson, Brady D; Smith, Steven C; Peper, Shane M

    2013-08-13

    Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

  18. Compositions and methods for treating nuclear fuel

    DOE Patents [OSTI]

    Soderquist, Chuck Z; Johnsen, Amanda M; McNamara, Bruce K; Hanson, Brady D; Smith, Steven C; Peper, Shane M

    2014-01-28

    Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

  19. Advanced technologies for co-processing fossil and biomass resources for transportation fuels and power generation

    SciTech Connect (OSTI)

    Steinberg, M.; Dong, Y.

    2004-07-01

    Over the past few decades, a number of processes have been proposed or are under development for coprocessing fossil fuel and biomass for transportation fuels and power generation. The paper gives a brief description of the following processes: the Hydrocarb system for converting biomass and other carbonaceous fuels to elemental carbon and hydrogen, methane or methanol; the Hynol process where the second step of the Hydrocarb process is replaced with a methane steam reformer to convert methane to CO and H{sub 2}S without deposition of carbon; the Carnol process where CO{sub 2} from coal and the biomass power plants is reacted with hydrogen to produce methanol; and advanced biomass high efficiency power generator cycle where a continuous plasma methane decomposition reactor (PDR) is used with direct carbon fuel cell to produce power and carbon and hydrogen. 13 refs., 5 figs., 2 tabs.

  20. Nuclear fuel microsphere gamma analyzer

    DOE Patents [OSTI]

    Valentine, Kenneth H.; Long, Jr., Ernest L.; Willey, Melvin G.

    1977-01-01

    A gamma analyzer system is provided for the analysis of nuclear fuel microspheres and other radioactive particles. The system consists of an analysis turntable with means for loading, in sequence, a plurality of stations within the turntable; a gamma ray detector for determining the spectrum of a sample in one section; means for analyzing the spectrum; and a receiver turntable to collect the analyzed material in stations according to the spectrum analysis. Accordingly, particles may be sorted according to their quality; e.g., fuel particles with fractured coatings may be separated from those that are not fractured, or according to other properties.

  1. EPRI-DOE Joint Report on Fossil Fleet Transition with Fuel Changes and Large Scale Variable Renewable Integration Now Available

    Broader source: Energy.gov [DOE]

    A new report “Fossil Fleet Transition with Fuel Changes and Large Scale Variable Renewable Integration” from the Electric Power Research Institute (EPRI) and jointly funded by the Offices of...

  2. EA-1778: Proposed Rule, 10 CFR 433 and 435, Energy Conservation and Fossil Fuel-Generated Energy

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of DOE's Proposed Rule, 10 CFR Part 433, Energy Conservation and Fossil Fuel-Generated Energy Consumption Reduction Standards for the Design and Construction of New Federal Commercial and Multi-Family High-Rise Residential Buildings and 10 CFR Part 435, Energy Conservation and Fossil Fuel-Generated Energy Consumption Reduction Standards for the Design and Construction of New Federal Low-Rise Residential Buildings.

  3. Method for producing nuclear fuel

    DOE Patents [OSTI]

    Haas, Paul A.

    1983-01-01

    Nuclear fuel is made by contacting an aqueous solution containing an actinide salt with an aqueous solution containing ammonium hydroxide, ammonium oxalate, or oxalic acid in an amount that will react with a fraction of the actinide salt to form a precipitate consisting of the hydroxide or oxalate of the actinide. A slurry consisting of the precipitate and solution containing the unreacted actinide salt is formed into drops which are gelled, calcined, and pressed to form pellets.

  4. Nuclear Fuel Cycle | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Fuel Cycle Nuclear Fuel Cycle GC-52 provides legal advice to DOE regarding research and development of nuclear fuel and waste management technologies that meet the nation's energy supply, environmental, and energy security needs. GC-52 also advises DOE on issues involving support for international fuel cycle initiatives aimed at advancing a common vision of the necessity of the expansion of nuclear energy for peaceful purposes worldwide in a safe and secure manner. In addition, GC-52 provides

  5. Energy-efficient air pollution controls for fossil-fueled plants: Technology assessment

    SciTech Connect (OSTI)

    Sayer, J.H.

    1995-06-01

    The 1990 Clean Air Act Amendments require most fossil-fuel fired power plants to reduce sulfur dioxide, nitrogen oxides, and particulate emissions. While emission-control equipment is available to help most of New York State`s 91 utility units in 31 power plants comply with the new regulations, technologies currently available consume energy, increase carbon dioxide emissions, reduce operating efficiency, and may produce large amounts of solid and/or semisolid byproducts that use additional energy for processing and disposal. This report discribes several pollution-control technologies that are more energy efficient compared to traditional technologies for controlling sulfur dioxide, nitrogen oxide, and particulates, that may have application in New York State. These technologies are either in commercial use, under development, or in the demonstration phase; This report also presents operating characteristics for these technologies and discusses solutions to dispose of pollution-control system byproducts. Estimated energy consumption for emission-control systems relative to a plant`s gross generating capacity is 3 to 5 for reducing up to 90% sulfur dioxide emissions from coal-fired plants. 0.5 to 2.5% for reducing nitrogen oxide emissions by up to 80% from all fossil-fuel fired plants; and 0.5 to 1.5 % for controlling particulate emissions from oil- and coal-fired plants. While fuel switching and/or cofiring with natural gas are options to reduce emissions, these techniques are not considered in this report; the discussion is limited to fossil-fueled steam-generating plants.

  6. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER

    SciTech Connect (OSTI)

    BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

    2003-06-01

    OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficiency and cost, from the high-temperature capabilities of advanced nuclear reactors. The more promising cycles were then analyzed in depth as to their adaptability to advanced high-temperature nuclear reactors. As a result, the Sulfur-Iodine (S-I) cycle was selected for integration into the advanced nuclear reactor system. In Phases 2 and 3, alternative flowsheets were developed and compared. This effort entailed a considerable effort into developing the solution thermodynamics pertinent to the S-I cycle.

  7. ROSE-based compact simulator for fossil fuel-fired power plant

    SciTech Connect (OSTI)

    Dana, H.; Burelle, R.

    1996-11-01

    Nuclear simulators specifications typically ask for {open_quotes}high fidelity full scope replica simulator{close_quotes}. This request is not only the norm but also mandatory due to the strict regulations and safety concerns in that industry. It is an unquestionable fact that these types of simulators do provide the most realistic and effective environment to train control room operators in normal, abnormal operations, and especially in emergency conditions which would be difficult to rehearse otherwise. Utilities in the fossil industry who could afford the price that these top of the line simulators demand would not hesitate long to acquire one. Fortunately for the others, this industry has the luxury to be more flexible in its simulator`s needs which permits utilities to select a simulator within their specific budget. They may chose from a wide range of different types of simulators, including full scope or partial scope, high fidelity or generic, hardware control rooms replicas or CRT-based graphical emulations. In all cases, a simulator must be economically beneficial to plant operations to justify its cost. Taking into account the distinctive requirements of the fossil industry, including their budget constraints, CAE used its vast experience in nuclear simulators to produce a user-friendly, CRT-based compact fossil simulator, using ROSE (Real-time Object-oriented Software Environment). This paper describes the specifics and characteristics of the ROSE-base compact simulator.

  8. Table 1.15 Non-Combustion Use of Fossil Fuels, 1980-2011

    U.S. Energy Information Administration (EIA) Indexed Site

    5 Non-Combustion Use of Fossil Fuels, 1980-2011 Year Petroleum Products Natural Gas 4 Coal Total Percent of Total Energy Consumption Asphalt and Road Oil Liquefied Petroleum Gases 1 Lubricants Petro- chemical Feedstocks 2 Petroleum Coke Special Naphthas Other 3 Total Physical Units 5<//td> 1980 145 230 58 253 14 [R] 37 58 795 [R] 639 2.4 [ – –] [ – –] 1981 125 229 56 216 15 [R] 27 54 722 [R] 518 [R] 2.1 [ – –] [ – –] 1982 125 256 51 157 15 [R] 25 48 678 [R] 448 [R] 1.4 [ – –] [

  9. Fossil Fuel Carbon Dioxide Emissions Data and Data Plots from Project Vulcan

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Gurney, Kevin

    Explore the Vulcan website for the Vulcan gridded data, methodological details, publications, plots and analysis.[Taken from "About Project Vulcan" at http://www.purdue.edu/eas/carbon/vulcan/index.php]Also, see the peer-reviewed paper that provides a "core" description for this project: Gurney, K.R., D. Mendoza, Y. Zhou, M Fischer, S. de la Rue du Can, S. Geethakumar, C. Miller (2009) The Vulcan Project: High resolution fossil fuel combustion CO2 emissions fluxes for the United States, Environ. Sci. Technol., 43, doi:10.1021/es900,806c.

  10. Liquid fossil-fuel technology. Quarterly technical progress report, January-March 1983

    SciTech Connect (OSTI)

    Linville, B.

    1983-07-01

    Accomplishments for the quarter ending March 1983 are presented under the following headings: liquid fossil fuel cycle, processing, utilization, and project integration and technology transfer. Feature articles for this quarter are: (1) abandoned oil field reports issued; (2) oilfield water data bank report published; (3) microbial enhanced recovery report issued; (4) polymer-augmented project could be economic today; (5) carbon dioxide EOR estimates given; (6) BETC passes 65th milestone; and (7) fifty achievements for fifty years (1918-1968). BETC publications are also listed. (ATT)

  11. Evaluation of innovative fossil fuel power plants with CO{sub 2} removal

    SciTech Connect (OSTI)

    2000-07-15

    This interim report presents initial results of an ongoing study of the potential cost of electricity produced in both conventional and innovative fossil fueled power plants that incorporate carbon dioxide (CO{sub 2}) removal for subsequent sequestration or use. The baseline cases are natural gas combined cycle (NGCC) and ultra-supercritical pulverized coal (PC) plants, with and without post combustion CO{sub 2} removal, and integrated gasification combined cycle (IGCC) plants, with and without pre-combustion CO{sub 2} removal.

  12. Comparison of emissions from landfills, municipal waste combustors, and fossil fuel-fired utilities

    SciTech Connect (OSTI)

    1996-11-01

    Landfilling is the most popular disposal method for managing municipal solid waste (MSW). However, air emissions from MSW landfills have generally been unregulated until recently. Instead, EPA has focused on emissions from municipal waste combustors (MWCs), even though they only manage 15% of MSW generated in the United States. In the past, little data have been available comparing landfill and MWC air emissions. Such information is provided by this paper. It also compares emissions from waste-to-energy MWCs and fossil fuel-fired utilities with equivalent electrical generation capacity. 1 refs., 6 tabs.

  13. USVI Makes Headway Toward Goal to Reduce Fossil Fuel 60% by 2025

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Oil prices spike to over $145/ barrel and price of electricity exceeds $0.50/kWh in U.S. Virgin Islands (USVI) USVI announces goal to reduce fossil fuel use 60% by 2025 In 3rd most active hurricane season on record, Earl hits USVI Virgin Islands Energy O ce (VIEO) launches Sun Power Loan Program WAPA installs waste heat recovery plant, adding 19 MW of power without burning a single drop of additional oil VIEO awards nearly $1 million to USVI nonpro ts for energy e ciency and renewable energy

  14. Nuclear Fuel Cycle Option Catalog SAND2015-2174 W

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    benefits and challenges of nuclear fuel cycle options (i.e., the complete nuclear ... of Energy, Office of Nuclear Energy, Fuel Cycle Research and Development program. ...

  15. Nuclear core and fuel assemblies

    DOE Patents [OSTI]

    Downs, Robert E.

    1981-01-01

    A fast flux nuclear core of a plurality of rodded, open-lattice assemblies having a rod pattern rotated relative to a rod support structure pattern. Elongated fuel rods are oriented on a triangular array and laterally supported by grid structures positioned along the length of the assembly. Initial inter-assembly contact is through strongbacks at the corners of the support pattern and peripheral fuel rods between adjacent assemblies are nested so as to maintain a triangular pitch across a clearance gap between the other portions of adjacent assemblies. The rod pattern is rotated relative to the strongback support pattern by an angle .alpha. equal to sin .sup.-1 (p/2c), where p is the intra-assembly rod pitch and c is the center-to-center spacing among adjacent assemblies.

  16. A brief overview of Chinese Design Code on Fossil-Fueled Power Plants

    SciTech Connect (OSTI)

    Xu Zhongqing; He Yehong

    1996-10-01

    The Chinese Design Code on Fossil Fueled Power Plants (DL 5000-94) was issued in April 1994 by the Ministry of Electric Power Industry, P.R. China, and the English version has been drafted and will be formally published in the near future. Based on the 1984 version and the nation`s current policies, the 1994 version was formed to meet the challenges of the nation`s speedy development of electric power construction. In general, the code is primarily a directive document guiding the planning and engineering of China`s large- and medium-sized fossil-fueled power plants. The preparation of the 1984 version and the revision of it to the 1994 version were all carried out by the East China Electric Power Design Institute under the direction of Electric Power Planning and Engineering Institute. For small-sized power plants with unit rating of 25 MW and below, there is another national design code titled Code for Design of Small Sized Power Plants (GB 50049-94) issued in November 1994 jointly by the China`s National Technology Supervision Administration and the Ministry of Construction.

  17. Identifying fly ash at a distance from fossil fuel power stations

    SciTech Connect (OSTI)

    Flanders, P.J.

    1999-02-15

    A method has been developed to identify fly ash originating at fossil fuel power stations, even at a distance where the ash level is lower by a factor of 1000 from that close to a source. Until now such detection has been difficult and uncertain. The technique combines collection of particles, measurement of magnetization and coercive field, and microscopy. The analysis depends on the fact that ash from iron sulfide in fossil fuels is in the form of spherical magnetite. These particles have a relatively high coercive field H{sub c}, near 135 Oe, compared with airborne particulates from soil erosion which have an H{sub c} of {approximately}35 Oe. The coercive field of any sample therefore gives an indication for the percentage of fly ash relative to the total amount of magnetic material that is airborne. The concentration of ash from a large, isolated coal burning power station is found to fall off with the distance from the source, approximately as D{sup {minus}1}. As D increases there is a drop in H{sub c}, associated with the reduced amount of fly ash relative to the airborne particulates from soil erosion.

  18. Fossil Energy | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Fossil Energy Fossil Energy Below are resources for Tribes on fossil energy. Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2011 This paper...

  19. Risks to global biodiversity from fossil-fuel production exceed those from biofuel production

    SciTech Connect (OSTI)

    Dale, Virginia H; Parish, Esther S; Kline, Keith L

    2015-01-01

    Potential global biodiversity impacts from near-term gasoline production are compared to biofuel, a renewable liquid transportation fuel expected to substitute for gasoline in the near term (i.e., from now until c. 2030). Petroleum exploration activities are projected to extend across more than 5.8 billion ha of land and ocean worldwide (of which 3.1 billion is on land), much of which is in remote, fragile terrestrial ecosystems or off-shore oil fields that would remain relatively undisturbed if not for interest in fossil fuel production. Future biomass production for biofuels is projected to fall within 2.0 billion ha of land, most of which is located in areas already impacted by human activities. A comparison of likely fuel-source areas to the geospatial distribution of species reveals that both energy sources overlap with areas with high species richness and large numbers of threatened species. At the global scale, future petroleum production areas intersect more than double the area and higher total number of threatened species than future biofuel production. Energy options should be developed to optimize provisioning of ecosystem services while minimizing negative effects, which requires information about potential impacts on critical resources. Energy conservation and identifying and effectively protecting habitats with high-conservation value are critical first steps toward protecting biodiversity under any fuel production scenario.

  20. Risks to global biodiversity from fossil-fuel production exceed those from biofuel production

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Dale, Virginia H; Parish, Esther S; Kline, Keith L

    2015-01-01

    Potential global biodiversity impacts from near-term gasoline production are compared to biofuel, a renewable liquid transportation fuel expected to substitute for gasoline in the near term (i.e., from now until c. 2030). Petroleum exploration activities are projected to extend across more than 5.8 billion ha of land and ocean worldwide (of which 3.1 billion is on land), much of which is in remote, fragile terrestrial ecosystems or off-shore oil fields that would remain relatively undisturbed if not for interest in fossil fuel production. Future biomass production for biofuels is projected to fall within 2.0 billion ha of land, most ofmore » which is located in areas already impacted by human activities. A comparison of likely fuel-source areas to the geospatial distribution of species reveals that both energy sources overlap with areas with high species richness and large numbers of threatened species. At the global scale, future petroleum production areas intersect more than double the area and higher total number of threatened species than future biofuel production. Energy options should be developed to optimize provisioning of ecosystem services while minimizing negative effects, which requires information about potential impacts on critical resources. Energy conservation and identifying and effectively protecting habitats with high-conservation value are critical first steps toward protecting biodiversity under any fuel production scenario.« less

  1. Monitoring arrangement for vented nuclear fuel elements

    DOE Patents [OSTI]

    Campana, Robert J.

    1981-01-01

    In a nuclear fuel reactor core, fuel elements are arranged in a closely packed hexagonal configuration, each fuel element having diametrically opposed vents permitting 180.degree. rotation of the fuel elements to counteract bowing. A grid plate engages the fuel elements and forms passages for communicating sets of three, four or six individual vents with respective monitor lines in order to communicate vented radioactive gases from the fuel elements to suitable monitor means in a manner readily permitting detection of leakage in individual fuel elements.

  2. Spent Nuclear Fuel (SNF) Project Execution Plan

    SciTech Connect (OSTI)

    LEROY, P.G.

    2000-11-03

    The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

  3. Nuclear fuel: a new market dynamic

    SciTech Connect (OSTI)

    Kee, Edward D.

    2007-12-15

    After almost 20 years of low nuclear fuel prices, buyers have come to expect that these low and stable nuclear fuel prices will continue. This conventional wisdom may not reflect the significant changes and higher prices that growing demand, and the end of secondary sources of uranium and enrichment, will bring. (author)

  4. Linear regression analysis of emissions factors when firing fossil fuels and biofuels in a commercial water-tube boiler

    SciTech Connect (OSTI)

    Sharon Falcone Miller; Bruce G. Miller

    2007-12-15

    This paper compares the emissions factors for a suite of liquid biofuels (three animal fats, waste restaurant grease, pressed soybean oil, and a biodiesel produced from soybean oil) and four fossil fuels (i.e., natural gas, No. 2 fuel oil, No. 6 fuel oil, and pulverized coal) in Penn State's commercial water-tube boiler to assess their viability as fuels for green heat applications. The data were broken into two subsets, i.e., fossil fuels and biofuels. The regression model for the liquid biofuels (as a subset) did not perform well for all of the gases. In addition, the coefficient in the models showed the EPA method underestimating CO and NOx emissions. No relation could be studied for SO{sub 2} for the liquid biofuels as they contain no sulfur; however, the model showed a good relationship between the two methods for SO{sub 2} in the fossil fuels. AP-42 emissions factors for the fossil fuels were also compared to the mass balance emissions factors and EPA CFR Title 40 emissions factors. Overall, the AP-42 emissions factors for the fossil fuels did not compare well with the mass balance emissions factors or the EPA CFR Title 40 emissions factors. Regression analysis of the AP-42, EPA, and mass balance emissions factors for the fossil fuels showed a significant relationship only for CO{sub 2} and SO{sub 2}. However, the regression models underestimate the SO{sub 2} emissions by 33%. These tests illustrate the importance in performing material balances around boilers to obtain the most accurate emissions levels, especially when dealing with biofuels. The EPA emissions factors were very good at predicting the mass balance emissions factors for the fossil fuels and to a lesser degree the biofuels. While the AP-42 emissions factors and EPA CFR Title 40 emissions factors are easier to perform, especially in large, full-scale systems, this study illustrated the shortcomings of estimation techniques. 23 refs., 3 figs., 8 tabs.

  5. Table 1.14 Sales of Fossil Fuels Produced on Federal and American Indian Lands, Fiscal Years 2003-2011

    U.S. Energy Information Administration (EIA) Indexed Site

    4 Sales of Fossil Fuels Produced on Federal and American Indian Lands, Fiscal Years 2003-2011 Fiscal Year 7 Crude Oil and Lease Condensate Natural Gas Plant Liquids 1 Natural Gas 2 Coal 3 Total Fossil Fuels 4 Sales 5,6 Sales as Share of Total U.S. Production Sales 5,6 Sales as Share of Total U.S. Production Sales 5,6 Sales as Share of Total U.S. Production Sales 5,6 Sales as Share of Total U.S. Production Sales 5,6 Sales as Share of Total U.S. Production Million Barrels Trillion Btu Percent

  6. Hydrogen-or-Fossil-Combustion Nuclear Combined-Cycle Systems for Base- and Peak-Load Electricity Production

    SciTech Connect (OSTI)

    Forsberg, Charles W; Conklin, Jim

    2007-09-01

    A combined-cycle power plant is described that uses (1) heat from a high-temperature nuclear reactor to meet base-load electrical demands and (2) heat from the same high-temperature reactor and burning natural gas, jet fuel, or hydrogen to meet peak-load electrical demands. For base-load electricity production, fresh air is compressed; then flows through a heat exchanger, where it is heated to between 700 and 900 C by heat provided by a high-temperature nuclear reactor via an intermediate heat-transport loop; and finally exits through a high-temperature gas turbine to produce electricity. The hot exhaust from the Brayton-cycle gas turbine is then fed to a heat recovery steam generator that provides steam to a steam turbine for added electrical power production. To meet peak electricity demand, the air is first compressed and then heated with the heat from a high-temperature reactor. Natural gas, jet fuel, or hydrogen is then injected into the hot air in a combustion chamber, combusts, and heats the air to 1300 C-the operating conditions for a standard natural-gas-fired combined-cycle plant. The hot gas then flows through a gas turbine and a heat recovery steam generator before being sent to the exhaust stack. The higher temperatures increase the plant efficiency and power output. If hydrogen is used, it can be produced at night using energy from the nuclear reactor and stored until needed. With hydrogen serving as the auxiliary fuel for peak power production, the electricity output to the electric grid can vary from zero (i.e., when hydrogen is being produced) to the maximum peak power while the nuclear reactor operates at constant load. Because nuclear heat raises air temperatures above the auto-ignition temperatures of the various fuels and powers the air compressor, the power output can be varied rapidly (compared with the capabilities of fossil-fired turbines) to meet spinning reserve requirements and stabilize the electric grid. This combined cycle uses the unique characteristics of high-temperature reactors (T>700 C) to produce electricity for premium electric markets whose demands can not be met by other types of nuclear reactors. It may also make the use of nuclear reactors economically feasible in smaller electrical grids, such as those found in many developing countries. The ability to rapidly vary power output can be used to stabilize electric grid performance-a particularly important need in small electrical grids.

  7. Simulated nuclear reactor fuel assembly

    DOE Patents [OSTI]

    Berta, V.T.

    1993-04-06

    An apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inner target tube is surrounded by and radially spaced from the heater tubes and outer target tube. The top of the assembly is generally open to allow for the electrical power connection to the heater tubes, and the bottom of the assembly includes means for completing the electrical circuitry in the heater tubes to provide electrical resistance heating to simulate the power profile in a nuclear reactor. The embedded conductor elements in each heater tube is split into two halves for a substantial portion of its length and provided with electrical isolation such that each half of the conductor is joined at one end and is not joined at the other end.

  8. Simulated nuclear reactor fuel assembly

    DOE Patents [OSTI]

    Berta, Victor T.

    1993-01-01

    An apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inner target tube is surrounded by and radially spaced from the heater tubes and outer target tube. The top of the assembly is generally open to allow for the electrical power connection to the heater tubes, and the bottom of the assembly includes means for completing the electrical circuitry in the heater tubes to provide electrical resistance heating to simulate the power profile in a nuclear reactor. The embedded conductor elements in each heater tube is split into two halves for a substantial portion of its length and provided with electrical isolation such that each half of the conductor is joined at one end and is not joined at the other end.

  9. fuel | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Jobs Working at NNSA Blog Home fuel fuel Cheaper catalyst may lower fuel costs for hydrogen-powered cars Sandia National Laboratories post-doctoral fellow Stan Chou demonstrates...

  10. Small Scale SOFC Demonstration Using Bio-Based and Fossil Fuels

    SciTech Connect (OSTI)

    Michael Petrik; Robert Ruhl

    2012-03-31

    Technology Management, Inc. (TMI) of Cleveland, Ohio, has completed the project entitled “Small Scale SOFC Demonstration using Bio-based and Fossil Fuels.” Under this program, two 1-kW systems were engineered as technology demonstrators of an advanced technology that can operate on either traditional hydrocarbon fuels or renewable biofuels. The systems were demonstrated at Patterson's Fruit Farm of Chesterland, OH and were open to the public during the first quarter of 2012. As a result of the demonstration, TMI received quantitative feedback on operation of the systems as well as qualitative assessments from customers. Based on the test results, TMI believes that > 30% net electrical efficiency at 1 kW on both traditional and renewable fuels with a reasonable entry price is obtainable. The demonstration and analysis provide the confidence that a 1 kW entry-level system offers a viable value proposition, but additional modifications are warranted to reduce sound and increase reliability before full commercial acceptance.

  11. Results of studies on application of CCMHD to advanced fossil fuel power plant cycles

    SciTech Connect (OSTI)

    Foote, J.P.; Wu, Y.C.L.S.; Lineberry, J.T.

    1998-07-01

    A study was conducted to assess the potential for application of a Closed Cycle MHD disk generator (CCMHD) in advanced fossil fuel power generation systems. Cycle analyses were conducted for a variety of candidate power cycles, including simple cycle CCMHD (MHD); a cycle combining CCMHD and gas turbines (MHD/GT); and a triple combined cycle including CCMHD, gas turbines, and steam turbines (MHD/GT/ST). The above cycles were previously considered in cycle studies reported by Japanese researchers. Also considered was a CCMHD cycle incorporating thermochemical heat recovery through reforming of the fuel stream (MHD/REF), which is the first consideration of this approach. A gas turbine/steam turbine combined cycle (GT/ST) was also analyzed for baseline comparison. The only fuel considered in the study was CH4. Component heat and pressure losses were neglected, and the potential for NOx emission due to high combustion temperatures was not considered. Likewise, engineering limitations for cycle components, particularly the high temperature argon heater, were not considered. This approach was adopted to simplify the analysis for preliminary screening of candidate cycles. Cycle calculations were performed using in-house code. Ideal gas thermodynamic properties were calculated using the NASA SP- 273 data base, and thermodynamic properties for steam were calculated using the computerized ASME Steam Tables. High temperature equilibrium compositions for combustion gas were calculated using tabulated values of the equilibrium constants for the important reactions.

  12. Boiler and steam generator corrosion: Fossil-fuel power plants. March 1977-December 1989 (A Bibliography from the NTIS data base). Report for March 1977-December 1989

    SciTech Connect (OSTI)

    Not Available

    1990-05-01

    This bibliography contains citations concerning corrosion effects, mechanisms, detection, and inhibition in fossil fuel fired boilers. Fluidized bed combustors and coal gasification are included in the applications. Hot corrosion, thermal mechanical degradation, and intergranular oxidation corrosion studies performed on the water side and hot gas side of heat exchanger tubes and support structures are presented. Coatings and treatment of material to inhibit corrosion are discussed. Corrosion affecting nuclear powered steam generators is examined in a separate bibliography. (Contains 88 citations fully indexed and including a title list.)

  13. fuel cells | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    fuel cells

  14. Table 3.7 Value of Fossil Fuel Imports, 1949-2011 (Thousand Dollars)

    U.S. Energy Information Administration (EIA) Indexed Site

    7 Value of Fossil Fuel Imports, 1949-2011 (Thousand Dollars) Year Coal Coal Coke Natural Gas Crude Oil 1 Petroleum Products 2 Total Nominal 3 Real 4 Nominal 3 Real 4 Nominal 3 Real 4 Nominal 3 Real 4 Nominal 3 Real 4 Nominal 3 Real 4 1949 2,368 16,332 [R] 3,976 27,423 [R] 0 0 304,658 2,101,235 [R] 137,130 945,789 [R] 448,132 3,090,779 [R] 1950 2,624 17,904 [R] 5,297 36,142 [R] 0 0 369,208 2,519,159 [R] 214,629 1,464,445 [R] 591,758 4,037,650 [R] 1951 2,420 15,402 [R] 1,932 12,296 [R] 0 0 374,869

  15. Table 3.8 Value of Fossil Fuel Exports, 1949-2011 (Thousand Dollars)

    U.S. Energy Information Administration (EIA) Indexed Site

    8 Value of Fossil Fuel Exports, 1949-2011 (Thousand Dollars) Year Coal Coal Coke Natural Gas Crude Oil Petroleum Products 1 Total Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 1949 297,179 2,049,652 [R] 8,323 57,404 [R] 1,823 12,573 [R] 98,425 678,840 [R] 461,439 3,182,557 [R] 867,189 5,981,026 [R] 1950 269,195 1,836,756 [R] 6,159 42,024 [R] 3,199 21,827 [R] 102,717 700,853 [R] 394,434 2,691,280 [R] 775,704 5,292,740 [R] 1951 586,056

  16. Table 3.9 Value of Fossil Fuel Net Imports, 1949-2011 (Thousand Dollars)

    U.S. Energy Information Administration (EIA) Indexed Site

    9 Value of Fossil Fuel Net Imports, 1949-2011 (Thousand Dollars) Year Coal Coal Coke Natural Gas Crude Oil Petroleum Products 1 Total Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 Nominal 2 Real 3 1949 -294,811 -2,033,320 [R] -4,347 -29,981 [R] -1,823 -12,573 [R] 206,233 1,422,395 [R] -324,309 -2,236,768 [R] -419,057 -2,890,248 [R] 1950 -266,571 -1,818,852 [R] -862 -5,882 [R] -3,199 -21,827 [R] 266,491 1,818,306 [R] -179,805 -1,226,835 [R] -183,946

  17. Sales of Fossil Fuels Produced from Federal and Indian Lands, FY 2003 through FY 2014

    U.S. Energy Information Administration (EIA) Indexed Site

    8 Table 7. Sales of fossil fuel production from federal and Indian lands by state/area, FY 2003-14 trillion Btu State 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 Alabama 75 57 51 47 40 42 60 88 86 71 46 29 Alaska 61 66 68 52 32 28 27 23 21 19 18 21 Arizona 258 273 280 193 180 162 157 154 164 163 167 158 Arkansas 7 8 10 10 10 11 15 18 14 13 11 11 California 141 125 124 139 146 129 116 115 121 125 121 119 Colorado 785 842 960 906 905 931 846 868 917 952 875 877 Florida 0 - - - - -

  18. Integrated capture of fossil fuel gas pollutants including CO.sub.2 with energy recovery

    DOE Patents [OSTI]

    Ochs, Thomas L.; Summers, Cathy A.; Gerdemann, Steve; Oryshchyn, Danylo B.; Turner, Paul; Patrick, Brian R.

    2011-10-18

    A method of reducing pollutants exhausted into the atmosphere from the combustion of fossil fuels. The disclosed process removes nitrogen from air for combustion, separates the solid combustion products from the gases and vapors and can capture the entire vapor/gas stream for sequestration leaving near-zero emissions. The invention produces up to three captured material streams. The first stream is contaminant-laden water containing SO.sub.x, residual NO.sub.x particulates and particulate-bound Hg and other trace contaminants. The second stream can be a low-volume flue gas stream containing N.sub.2 and O.sub.2 if CO2 purification is needed. The final product stream is a mixture comprising predominantly CO.sub.2 with smaller amounts of H.sub.2O, Ar, N.sub.2, O.sub.2, SO.sub.X, NO.sub.X, Hg, and other trace gases.

  19. A creep damage estimation method for in-service fossil fuel boiler superheater tubes

    SciTech Connect (OSTI)

    Nogata, F. . Dept. of Mechanical Engineering); Takahashi, H. . Research Inst. of Fracture Technology)

    1995-02-01

    Because mechanical properties of structural materials for high-temperature use, such as boiler tubing, degrade during long-term service, it is essential to detect toughness degradation by means of a nondestructive and simple field test technique. A grain boundary etching technique is developed to detect material degradation, and assess creep strength and notch toughness. An etching test using a picric acid solution with a wetting agent or using 20 percent HNO[sub 3] with alcoholic solution was found to have great potential for the nondestructive estimation of grain boundary embrittlement caused by carbide and sigma precipitation in SUS stainless steel. The feasibility of this estimation procedure was determined showing the relationships between Charpy impact energy (CVN) and grooving width (W[sub GS]), and creep damage ratio ([Phi]) and W[sub GS]. Superheater tubes of fossil fuel boiler were tested on site to demonstrate the validity of this technique.

  20. An optical gas temperature probe for high temperature fossil fuel process streams

    SciTech Connect (OSTI)

    Bauman, L.E.; Cook, R.L.; Lineberry, J.T.; Litchford, R.J.

    1995-12-31

    Reported here are the results of a feasibility study of a modular optical gas temperature probe for direct measurement of gas temperature in fossil-fueled combustion streams. A probe based upon the spectroscopic technique of line reversal would be superior to currently available gas temperature technology. The study concluded that a modular form of the line reversal optical temperature probe is feasible and, as such. the probe should be a commercially viable product with potential economic benefits from improved monitoring and control of utility furnaces. Such a probe will have the capability of making direct measurements of gas temperature in hot (>1500 K) process streams of coal combustion systems and large-scale power plant facilities.

  1. Device for separating CO2 from fossil-fueled power plant emissions

    DOE Patents [OSTI]

    Burchell, Timothy D.; Judkins, Roddie R.; Wilson, Kirk A.

    2002-04-23

    A gas separation device includes an inner conduit, and a concentric outer conduit. An electrically conductive filter media, preferably a carbon fiber composite molecular sieve, is provided in the annular space between the inner conduit and the outer conduit. Gas flows through the inner conduit and the annular space between the inner conduit and the outer conduit, so as to contact the filter media. The filter media preferentially adsorbs at least one constituent of the gas stream. The filter media is regenerated by causing an electric current to flow through the filter media. The inner conduit and outer conduit are preferably electrically conductive whereby the regeneration of the filter media can be electrically stimulated. The invention is particularly useful for the removal of CO.sub.2 from the exhaust gases of fossil-fueled power plants.

  2. World nuclear fuel cycle requirements 1990

    SciTech Connect (OSTI)

    Not Available

    1990-10-26

    This analysis report presents the projected requirements for uranium concentrate and uranium enrichment services to fuel the nuclear power plants expected to be operating under three nuclear supply scenarios. Two of these scenarios, the Lower Reference and Upper Reference cases, apply to the United States, Canada, Europe, the Far East, and other countries with free market economies (FME countries). A No New Orders scenario is presented only for the United States. These nuclear supply scenarios are described in Commercial Nuclear Power 1990: Prospects for the United States and the World (DOE/EIA-0438(90)). This report contains an analysis of the sensitivities of the nuclear fuel cycle projections to different levels and types of projected nuclear capacity, different enrichment tails assays, higher and lower capacity factors, changes in nuclear fuel burnup levels, and other exogenous assumptions. The projections for the United States generally extend through the year 2020, and the FME projections, which include the United States, are provided through 2010. The report also presents annual projections of spent nuclear fuel discharges and inventories of spent fuel. Appendix D includes domestic spent fuel projections through the year 2030 for the Lower and Upper Reference cases and through 2040, the last year in which spent fuel is discharged, for the No New Orders case. These disaggregated projections are provided at the request of the Department of Energy's Office of Civilian Radioactive Waste Management.

  3. Current Status of the Spent Nuclear Fuel Management Program in...

    Office of Scientific and Technical Information (OSTI)

    Current Status of the Spent Nuclear Fuel Management Program in the United States. Citation Details In-Document Search Title: Current Status of the Spent Nuclear Fuel Management...

  4. Energy Department Announces New Investment in Nuclear Fuel Storage...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Investment in Nuclear Fuel Storage Research Energy Department Announces New Investment in Nuclear Fuel Storage Research April 16, 2013 - 12:19pm Addthis NEWS MEDIA CONTACT (202)...

  5. Used Nuclear Fuel Loading and Structural Performance Under Normal...

    Office of Environmental Management (EM)

    Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan Used Nuclear Fuel Loading and ...

  6. A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu...

  7. Review of Used Nuclear Fuel Storage and Transportation Technical...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis While both wet and dry...

  8. Sustainable thorium nuclear fuel cycles: A comparison of intermediate...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Sustainable thorium nuclear fuel cycles: A comparison of intermediate and ... May 20, 2017 Title: Sustainable thorium nuclear fuel cycles: A comparison of intermediate ...

  9. Nuclear Fuel Cycle & Vulnerabilities (Technical Report) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Nuclear Fuel Cycle & Vulnerabilities Citation Details In-Document Search Title: Nuclear Fuel Cycle & Vulnerabilities The objective of safeguards is the timely detection of ...

  10. RADIOACTIVE WASTE STREAMS FROM VARIOUS POTENTIAL NUCLEAR FUEL...

    Office of Scientific and Technical Information (OSTI)

    FROM VARIOUS POTENTIAL NUCLEAR FUEL CYCLE OPTIONS Citation Details In-Document Search Title: RADIOACTIVE WASTE STREAMS FROM VARIOUS POTENTIAL NUCLEAR FUEL CYCLE OPTIONS Five ...

  11. Nuclear Fuel Cycle & Vulnerabilities (Technical Report) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Nuclear Fuel Cycle & Vulnerabilities Citation Details In-Document Search Title: Nuclear Fuel Cycle & Vulnerabilities You are accessing a document from the ...

  12. Nuclear Energy Systems Laboratory (NESL) / Transient Nuclear Fuels Testing

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Transient Nuclear Fuels Testing - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs

  13. Nuclear fuel elements having a composite cladding

    DOE Patents [OSTI]

    Gordon, Gerald M.; Cowan, II, Robert L.; Davies, John H.

    1983-09-20

    An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a composite cladding of an outer portion forming a substrate having on the inside surface a metal layer selected from the group consisting of copper, nickel, iron and alloys of the foregoing with a gap between the composite cladding and the core of nuclear fuel. The nuclear fuel element comprises a container of the elongated composite cladding, a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity. The metal layer of the composite cladding prevents perforations or failures in the cladding substrate from stress corrosion cracking or from fuel pellet-cladding interaction or both. The substrate of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy.

  14. Ukraine Fuel Removal: Fact Sheet | National Nuclear Security...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fuel Removal: Fact Sheet | National Nuclear Security Administration Facebook Twitter ... Blog Home Library Fact Sheets Ukraine Fuel Removal: Fact Sheet Ukraine Fuel Removal: ...

  15. Used Fuel Disposition Used Nuclear Fuel Storage and Transportation

    Energy Savers [EERE]

    Storage and Transportation Overview Steve Marschman Field Demonstration Lead Idaho National Laboratory NEET ASI Review Meeting September 17, 2014 Used Fuel Disposition Today's Discussion n Our R&D Objectives n What Guides Our Work n FY14 and FY15 Work - Full-Scale High Burn-Up Demo - Experiments - Transportation - Analysis Used Fuel Disposition 3 Overall Objectives * Develop the technical bases to demonstrate the continued safe and secure storage of used nuclear fuel for extended

  16. Relative Economic Incentives for Hydrogen from Nuclear, Renewable, and Fossil Energy Sources

    SciTech Connect (OSTI)

    Forsberg, Charles W [ORNL] [ORNL; Gorensek, M. B. [Savannah River National Laboratory (SRNL)] [Savannah River National Laboratory (SRNL)

    2007-01-01

    The specific hydrogen market determines the value of hydrogen from different sources. Each hydrogen production technology has its own distinct characteristics. For example, steam reforming of natural gas produces only hydrogen. In contrast, nuclear and solar hydrogen production facilities produce hydrogen together with oxygen as a by-product or co-product. For a user who needs both oxygen and hydrogen, the value of hydrogen from nuclear and solar plants is higher than that from a fossil plant because 'free' oxygen is produced as a by-product. Six factors that impact the relative economics of fossil, nuclear, and solar hydrogen production to the customer are identified: oxygen by-product, avoidance of carbon dioxide emissions, hydrogen transport costs, storage costs, availability of low-cost heat, and institutional factors. These factors imply that different hydrogen production technologies will be competitive in different markets and that the first markets for nuclear and solar hydrogen will be those markets in which they have a unique competitive advantage. These secondary economic factors are described and quantified in terms of dollars per kilogram of hydrogen.

  17. RELATIVE ECONOMIC INCENTIVES FOR HYDROGEN FROM NUCLEAR, RENEWABLE, AND FOSSIL ENERGY SOURCES

    SciTech Connect (OSTI)

    Gorensek, M; Charles W. Forsberg, C

    2008-08-04

    The specific hydrogen market determines the value of hydrogen from different sources. Each hydrogen production technology has its own distinct characteristics. For example, steam reforming of natural gas produces only hydrogen. In contrast, nuclear and solar hydrogen production facilities produce hydrogen together with oxygen as a by-product or co-product. For a user who needs both oxygen and hydrogen, the value of hydrogen from nuclear and solar plants is higher than that from a fossil plant because 'free' oxygen is produced as a by-product. Six factors that impact the relative economics of fossil, nuclear, and solar hydrogen production to the customer are identified: oxygen by-product, avoidance of carbon dioxide emissions, hydrogen transport costs, storage costs, availability of low-cost heat, and institutional factors. These factors imply that different hydrogen production technologies will be competitive in different markets and that the first markets for nuclear and solar hydrogen will be those markets in which they have a unique competitive advantage. These secondary economic factors are described and quantified in terms of dollars per kilogram of hydrogen.

  18. Strategic backdrop analysis for fossil fuel planning. Task 1. Default Case. Report 468-117-07/03

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    This report presents data describing a default case analysis performed using the strategic backdrop analytical framework developed to facilitate fossil fuel planning within the DOE. Target years are 1985, 2000, and 2025. Residential, commercial, and industrial energy demands and impacts of energy technology implementation and market penetration are forecast using a set of energy technology assumptions.

  19. Strategic backdrop analysis for fossil fuel planning. Task 1. Default Case. Report 468-117-07/02

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    This report presents data describing a default case analysis performed using the strategic backdrop analytical framework developed to facilitate fossil fuel planning within the DOE. Target years are 1985, 2000, and 2025. Residential, commercial, and industrial energy demands and impacts of energy technology implementation and market penetration are forecast using a set of energy technology assumptions. (DMC)

  20. Fossil-fuel power plants and power generation: Economic analysis. (Latest citations from the NTIS data base). Published Search

    SciTech Connect (OSTI)

    Not Available

    1992-06-01

    The bibliography contains citations concerning economic analyses and evaluations of utility and industrial fossil-fuel power generation. Coal-fired, oil-fired, and natural gas-fired electric power generating systems are discussed. Specific technologies, experiences, and locations are also considered. (Contains 250 citations and includes a subject term index and title list.)

  1. Fossil-fuel power plants and power generation: Economic analysis. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    1995-10-01

    The bibliography contains citations concerning economic analyses and evaluations of utility and industrial fossil-fuel power generation. Coal-fired, oil-fired, and natural gas-fired electric power generating systems are discussed. Specific technologies, experiences, and locations are also considered. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  2. Fossil-fuel power plants and power generation: Economic analysis. (Latest citations from the NTIS Bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1993-12-01

    The bibliography contains citations concerning economic analyses and evaluations of utility and industrial fossil-fuel power generation. Coal-fired, oil-fired, and natural gas-fired electric power generating systems are discussed. Specific technologies, experiences, and locations are also considered. (Contains 250 citations and includes a subject term index and title list.)

  3. Fossil-fuel power plants and power generation: Economic analysis. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    The bibliography contains citations concerning economic analyses and evaluations of utility and industrial fossil-fuel power generation. Coal-fired, oil-fired, and natural gas-fired electric power generating systems are discussed. Specific technologies, experiences, and locations are also considered. (Contains 250 citations and includes a subject term index and title list.)

  4. Fossil-fuel power plants and power generation: Economic analysis. (Latest citations from the NTIS Bibliographic database). Published Search

    SciTech Connect (OSTI)

    1993-09-01

    The bibliography contains citations concerning economic analyses and evaluations of utility and industrial fossil-fuel power generation. Coal-fired, oil-fired, and natural gas-fired electric power generating systems are discussed. Specific technologies, experiences, and locations are also considered. (Contains 250 citations and includes a subject term index and title list.)

  5. Fossil-fuel power plants and power generation: Economic analysis. (Latest citations from the NTIS bibliographic database). Published Search

    SciTech Connect (OSTI)

    1997-02-01

    The bibliography contains citations concerning economic analyses and evaluations of utility and industrial fossil-fuel power generation. Coal-fired, oil-fired, and natural gas-fired electric power generating systems are discussed. Specific technologies, experiences, and locations are also considered. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  6. Strategic backdrop analysis for fossil fuel planning. Task 1. Default Case. Report 468-117-07/01

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    This report presents data describing a default case analysis performed using the strategic backdrop analytical framework developed to facilitate fossil fuel planning within the DOE. Target years are 1985 and 2025. Residential, commercial, and industrial energy demands are forecast as well as the impacts of energy technology implementation and market penetration using a set of energy technology assumptions. (DMC)

  7. sparse-msrf:A package for sparse modeling and estimation of fossil-fuel CO2 emission fields

    Energy Science and Technology Software Center (OSTI)

    2014-10-06

    The software is used to fit models of emission fields (e.g., fossil-fuel CO2 emissions) to sparse measurements of gaseous concentrations. Its primary aim is to provide an implementation and a demonstration for the algorithms and models developed in J. Ray, V. Yadav, A. M. Michalak, B. van Bloemen Waanders and S. A. McKenna, "A multiresolution spatial parameterization for the estimation of fossil-fuel carbon dioxide emissions via atmospheric inversions", accepted, Geoscientific Model Development, 2014. The softwaremore » can be used to estimate emissions of non-reactive gases such as fossil-fuel CO2, methane etc. The software uses a proxy of the emission field being estimated (e.g., for fossil-fuel CO2, a population density map is a good proxy) to construct a wavelet model for the emission field. It then uses a shrinkage regression algorithm called Stagewise Orthogonal Matching Pursuit (StOMP) to fit the wavelet model to concentration measurements, using an atmospheric transport model to relate emission and concentration fields. Algorithmic novelties described in the paper above (1) ensure that the estimated emission fields are non-negative, (2) allow the use of guesses for emission fields to accelerate the estimation processes and (3) ensure that under/overestimates in the guesses do not skew the estimation.« less

  8. sparse-msrf:A package for sparse modeling and estimation of fossil-fuel CO2 emission fields

    SciTech Connect (OSTI)

    2014-10-06

    The software is used to fit models of emission fields (e.g., fossil-fuel CO2 emissions) to sparse measurements of gaseous concentrations. Its primary aim is to provide an implementation and a demonstration for the algorithms and models developed in J. Ray, V. Yadav, A. M. Michalak, B. van Bloemen Waanders and S. A. McKenna, "A multiresolution spatial parameterization for the estimation of fossil-fuel carbon dioxide emissions via atmospheric inversions", accepted, Geoscientific Model Development, 2014. The software can be used to estimate emissions of non-reactive gases such as fossil-fuel CO2, methane etc. The software uses a proxy of the emission field being estimated (e.g., for fossil-fuel CO2, a population density map is a good proxy) to construct a wavelet model for the emission field. It then uses a shrinkage regression algorithm called Stagewise Orthogonal Matching Pursuit (StOMP) to fit the wavelet model to concentration measurements, using an atmospheric transport model to relate emission and concentration fields. Algorithmic novelties described in the paper above (1) ensure that the estimated emission fields are non-negative, (2) allow the use of guesses for emission fields to accelerate the estimation processes and (3) ensure that under/overestimates in the guesses do not skew the estimation.

  9. W.T.; Rainey, R.H. 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS;...

    Office of Scientific and Technical Information (OSTI)

    thorium fuel reprocessing experience Brooksbank, R.E.; McDuffee, W.T.; Rainey, R.H. 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NUCLEAR MATERIALS DIVERSION; SAFEGUARDS; SPENT FUELS;...

  10. Pyrochemical Treatment of Spent Nuclear Fuel

    SciTech Connect (OSTI)

    K. M. Goff; K. L. Howden; G. M. Teske; T. A. Johnson

    2005-10-01

    Over the last 10 years, pyrochemical treatment of spent nuclear fuel has progressed from demonstration activities to engineering-scale production operations. As part of the Advanced Fuel Cycle Initiative within the U.S. Department of Energys Office of Nuclear Energy, Science and Technology, pyrochemical treatment operations are being performed as part of the treatment of fuel from the Experimental Breeder Reactor II at the Idaho National Laboratory. Integral to these treatment operations are research and development activities that are focused on scaling further the technology, developing and implementing process improvements, qualifying the resulting high-level waste forms, and demonstrating the overall pyrochemical fuel cycle.

  11. Method for shearing spent nuclear fuel assemblies

    DOE Patents [OSTI]

    Weil, Bradley S.; Watson, Clyde D.

    1977-01-01

    A method is disclosed for shearing spent nuclear fuel assemblies of the type wherein a plurality of long metal tubes packed with ceramic fuel are supported in a spaced apart relationship within an outer metal shell or shroud which provides structural support to the assembly. Spent nuclear fuel assemblies are first compacted in a stepwise manner between specially designed gag-compactors and then sheared into short segments amenable to chemical processing by shear blades contoured to mate with the compacted surface of the fuel assembly.

  12. Nuclear-Renewable Hybrid System Economic Basis for Electricity, Fuel, and Hydrogen

    SciTech Connect (OSTI)

    Charles Forsberg; Steven Aumeier

    2014-04-01

    Concerns about climate change and altering the ocean chemistry are likely to limit the use of fossil fuels. That implies a transition to a low-carbon nuclear-renewable electricity grid. Historically variable electricity demand was met using fossil plants with low capital costs, high operating costs, and substantial greenhouse gas emissions. However, the most easily scalable very-low-emissions generating options, nuclear and non-dispatchable renewables (solar and wind), are capital-intensive technologies with low operating costs that should operate at full capacities to minimize costs. No combination of fully-utilized nuclear and renewables can meet the variable electricity demand. This implies large quantities of expensive excess generating capacity much of the time. In a free market this results in near-zero electricity prices at times of high nuclear renewables output and low electricity demand with electricity revenue collapse. Capital deployment efficiency—the economic benefit derived from energy systems capital investment at a societal level—strongly favors high utilization of these capital-intensive systems, especially if low-carbon nuclear renewables are to replace fossil fuels. Hybrid energy systems are one option for better utilization of these systems that consumes excess energy at times of low prices to make some useful product.The economic basis for development of hybrid energy systems is described for a low-carbon nuclear renewable world where much of the time there are massivequantities of excess energy available from the electric sector.Examples include (1) high-temperature electrolysis to generate hydrogen for non-fossil liquid fuels, direct use as a transport fuel, metal reduction, etc. and (2) biorefineries.Nuclear energy with its concentrated constant heat output may become the enabling technology for economically-viable low-carbon electricity grids because hybrid nuclear systems may provide an economic way to produce dispatachable variable electricity with economic base-load operation of the reactor.

  13. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I.W.; Patridge, M.D.

    1991-05-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECN/NEA activities reports; not reflect any one single source but frequently represent a consolidation/combination of information.

  14. Annotated Bibliography for Drying Nuclear Fuel

    SciTech Connect (OSTI)

    Rebecca E. Smith

    2011-09-01

    Internationally, the nuclear industry is represented by both commercial utilities and research institutions. Over the past two decades many of these entities have had to relocate inventories of spent nuclear fuel from underwater storage to dry storage. These efforts were primarily prompted by two factors: insufficient storage capacity (potentially precipitated by an open-ended nuclear fuel cycle) or deteriorating quality of existing underwater facilities. The intent of developing this bibliography is to assess what issues associated with fuel drying have been identified, to consider where concerns have been satisfactorily addressed, and to recommend where additional research would offer the most value to the commercial industry and the U. S. Department of Energy.

  15. FUEL ELEMENT FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Bassett, C.H.

    1961-11-21

    A fuel element is designed which is particularly adapted for reactors of high power density used to generate steam for the production of electricity. The fuel element consists of inner and outer concentric tubes forming an annular chamber within which is contained fissionable fuel pellet segments, wedge members interposed between the fuel segments, and a spring which, acting with wedge members, urges said fuel pellets radially into contact against the inner surface of the outer tube. The wedge members may be a fertile material convertible into fissionable fuel material by absorbing neutrons emitted from the fissionable fuel pellet segments. The costly grinding of cylindrical fuel pellets to close tolerances for snug engagement is reduced because the need to finish the exact size is eliminated. (AEC)

  16. Apparatus for shearing spent nuclear fuel assemblies

    DOE Patents [OSTI]

    Weil, Bradley S.; Metz, III, Curtis F.

    1980-01-01

    A method and apparatus are described for shearing spent nuclear fuel assemblies of the type comprising an array of fuel pins disposed within an outer metal shell or shroud. A spent fuel assembly is first compacted in a known manner and then incrementally sheared using fixed and movable shear blades having matched laterally projecting teeth which slidably intermesh to provide the desired shearing action. Incremental advancement of the fuel assembly after each shear cycle is limited to a distance corresponding to the lateral projection of the teeth to ensure fuel assembly breakup into small uniform segments which are amenable to remote chemical processing.

  17. Electrochemical Processing of Used Nuclear Fuel

    SciTech Connect (OSTI)

    K. M. Goff; J. C. Wass; G. M. Teske

    2011-08-01

    As part of the Department of Energys Fuel Cycle Research and Development Program an electrochemical technology employing molten salts is being developed for recycle of metallic fast reactor fuel and treatment of light water reactor oxide fuel to produce a feed for fast reactors. This technology has been deployed for treatment of used fuel from the Experimental Breeder Reactor II (EBR-II) in the Fuel Conditioning Facility, located at the Materials and Fuel Complex of Idaho National Laboratory. This process is based on dry (non-aqueous) technologies that have been developed and demonstrated since the 1960s. These technologies offer potential advantages compared to traditional aqueous separations including: compactness, resistance to radiation effects, criticality control benefits, compatibility with advanced fuel types, and ability to produce low purity products. This paper will summarize the status of electrochemical development and demonstration activities with used nuclear fuel, including preparation of associated high-level waste forms.

  18. Fuel assembly for nuclear reactors

    DOE Patents [OSTI]

    Creagan, Robert J.; Frisch, Erling

    1977-01-01

    A new and improved fuel assembly is formed to minimize the amount of parasitic structural material wherein a plurality of hollow tubular members are juxtaposed to the fuel elements of the assembly. The tubular members may serve as guide tubes for control elements and are secured to a number of longitudinally spaced grid members along the fuel assembly. The grid members include means thereon engaging each of the fuel elements to laterally position the fuel elements in a predetermined array. Openings in the bottom of each hollow member serve as a shock absorber to cushion shock transmitted to the structure when the control elements are rapidly inserted in their corresponding tubular members.

  19. Composite construction for nuclear fuel containers

    DOE Patents [OSTI]

    Cheng, B. C.; Rosenbaum, H. S.; Armijo, J. S.

    1987-04-21

    Disclosed is an improved method for producing nuclear fuel containers of a composite construction having components providing therein a barrier system for resisting destructive action by volatile fission products or impurities and also interdiffusion of metal constituents, and the product thereof. The composite nuclear fuel containers of the method comprise a casing of zirconium or alloy thereof with a layer of copper overlying an oxidized surface portion of the zirconium or alloy thereof. 1 fig.

  20. Nuclear Fuel Facts: Uranium | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Facts: Uranium Nuclear Fuel Facts: Uranium Nuclear Fuel Facts: Uranium Uranium is a silvery-white metallic chemical element in the periodic table, with atomic number 92. It is assigned the chemical symbol U. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. Uranium has the highest atomic weight (19 kg m) of all naturally occurring elements. Uranium occurs naturally in low concentrations in soil, rock and water, and is commercially extracted from uranium-bearing

  1. Composite construction for nuclear fuel containers

    DOE Patents [OSTI]

    Cheng, Bo-Ching; Rosenbaum, Herman S.; Armijo, Joseph S.

    1987-01-01

    An improved method for producing nuclear fuel containers of a composite construction having components providing therein a barrier system for resisting destructive action by volatile fission products or impurities and also interdiffusion of metal constituents, and the product thereof. The composite nuclear fuel containers of the method comprise a casing of zirconium or alloy thereof with a layer of copper overlying an oxidized surface portion of the zirconium or alloy thereof.

  2. Dry Processing of Used Nuclear Fuel

    SciTech Connect (OSTI)

    K. M. Goff; M. F. Simpson

    2009-09-01

    Dry (non-aqueous) separations technologies have been used for treatment of used nuclear fuel since the 1960s, and they are still being developed and demonstrated in many countries. Dry technologies offer potential advantages compared to traditional aqueous separations including: compactness, resistance to radiation effects, criticality control benefits, compatibility with advanced fuel types, and ability to produce low purity products. Within the Department of Energys Advanced Fuel Cycle Initiative, an electrochemical process employing molten salts is being developed for recycle of fast reactor fuel and treatment of light water reactor oxide fuel to produce a feed for fast reactors. Much of the development of this technology is based on treatment of used Experimental Breeder Reactor II (EBR-II) fuel, which is metallic. Electrochemical treatment of the EBR-II fuel has been ongoing in the Fuel Conditioning Facility, located at the Materials and Fuel Complex of Idaho National Laboratory since 1996. More than 3.8 metric tons of heavy metal of metallic fast reactor fuel have been treated using this technology. This paper will summarize the status of electrochemical development and demonstration activities with used nuclear fuel, including high-level waste work. A historic perspective on the background of dry processing will also be provided.

  3. Pyrolytic carbon-coated nuclear fuel

    DOE Patents [OSTI]

    Lindemer, Terrence B.; Long, Jr., Ernest L.; Beatty, Ronald L.

    1978-01-01

    An improved nuclear fuel kernel having at least one pyrolytic carbon coating and a silicon carbon layer is provided in which extensive interaction of fission product lanthanides with the silicon carbon layer is avoided by providing sufficient UO.sub.2 to maintain the lanthanides as oxides during in-reactor use of said fuel.

  4. Rack for storing spent nuclear fuel elements

    DOE Patents [OSTI]

    Rubinstein, Herbert J.; Clark, Philip M.; Gilcrest, James D.

    1978-06-20

    A rack for storing spent nuclear fuel elements in which a plurality of aligned rows of upright enclosures of generally square cross-sectional areas contain vertically disposed fuel elements. The enclosures are fixed at the lower ends thereof to a base. Pockets are formed between confronting walls of adjacent enclosures for receiving high absorption neutron absorbers, such as Boral, cadmium, borated stainless steel and the like for the closer spacing of spent fuel elements.

  5. Fresh nuclear fuel measurements at Ukrainian nuclear power plants

    SciTech Connect (OSTI)

    Kuzminski, Jozef; Ewing, Tom; Dickman, Debbie; Gavrilyuk, Victor; Drapey, Sergey; Kirischuk, Vladimir; Strilchuk, Nikolay

    2009-01-01

    In 2005, the Provisions on Nuclear Material Measurement System was enacted in Ukraine as an important regulatory driver to support international obligations in nuclear safeguards and nonproliferation. It defines key provisions and requirements for material measurement and measurement control programs to ensure the quality and reliability of measurement data within the framework of the State MC&A System. Implementing the Provisions requires establishing a number of measurement techniques for both fresh and spent nuclear fuel for various types of Ukrainian reactors. Our first efforts focused on measurements of fresh nuclear fuel from a WWR-1000 power reactor.

  6. Utilization of Used Nuclear Fuel (UNF) in a Potential Future...

    Office of Scientific and Technical Information (OSTI)

    Utilization of Used Nuclear Fuel (UNF) in a Potential Future U.S. Fuel Cycle Scenario Citation Details In-Document Search Title: Utilization of Used Nuclear Fuel (UNF) in a ...

  7. The coprocessing of fossil fuels and biomass for CO{sub 2} emission reduction in the transportation sector

    SciTech Connect (OSTI)

    Steinberg, M.; Dong, Yuanji; Borgwardt, R.H.

    1993-10-01

    Research is underway to evaluate the Hydrocarb process for conversion of carbonaceous raw material to clean carbon and methanol products. These products are valuable in the market either as fuel or as chemical commodities. As fuel, methanol and carbon can be used economically, either independently or in slurry form, in efficient heat energies (turbines and internal combustion engines) for both mobile and stationary single and combined cycle power plants. When considering CO{sub 2} emission control in the utilization of fossil fuels, the copressing of those fossil fuels with biomass (which may include, wood, municipal solid waste and sewage sludge) is a viable mitigation approach. By coprocessing both types of feedstock to produce methanol and carbon while sequestering all or part of the carbon, a significant net CO{sub 2} reduction is achieved if the methanol is substituted for petroleum fuels in the transportation sector. The Hydrocarb process has the potential, if the R&D objectives are achieved, to produce alternative transportation fuel from indigenous resources at lower cost than any other biomass conversion process. These comparisons suggest the resulting fuel can significantly displace gasoline at a competitive price while mitigating CO{sub 2} emissions and reducing ozone and other toxics in urban atmospheres.

  8. A comparative analysis of accident risks in fossil, hydro, and nuclear energy chains

    SciTech Connect (OSTI)

    Burgherr, P.; Hirschberg, S.

    2008-07-01

    This study presents a comparative assessment of severe accident risks in the energy sector, based on the historical experience of fossil (coal, oil, natural gas, and LPG (Liquefied Petroleum Gas)) and hydro chains contained in the comprehensive Energy-related Severe Accident Database (ENSAD), as well as Probabilistic Safety Assessment (PSA) for the nuclear chain. Full energy chains were considered because accidents can take place at every stage of the chain. Comparative analyses for the years 1969-2000 included a total of 1870 severe ({>=} 5 fatalities) accidents, amounting to 81,258 fatalities. Although 79.1% of all accidents and 88.9% of associated fatalities occurred in less developed, non-OECD countries, industrialized OECD countries dominated insured losses (78.0%), reflecting their substantially higher insurance density and stricter safety regulations. Aggregated indicators and frequency-consequence (F-N) curves showed that energy-related accident risks in non-OECD countries are distinctly higher than in OECD countries. Hydropower in non-OECD countries and upstream stages within fossil energy chains are most accident-prone. Expected fatality rates are lowest for Western hydropower and nuclear power plants; however, the maximum credible consequences can be very large. Total economic damages due to severe accidents are substantial, but small when compared with natural disasters. Similarly, external costs associated with severe accidents are generally much smaller than monetized damages caused by air pollution.

  9. Nuclear Fuels & Materials Spotlight Volume 4

    SciTech Connect (OSTI)

    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.

  10. Table 3.2 Value of Fossil Fuel Production, 1949-2011 (Billion Dollars)

    U.S. Energy Information Administration (EIA) Indexed Site

    Value of Fossil Fuel Production, 1949-2011 (Billion Dollars) Year Coal 1 Natural Gas 2 Crude Oil 3,4 Total Nominal 5 Real 6 Nominal 5 Real 6 Nominal 5 Real 6 Nominal 5 Real 6 1949 2.52 17.37 [R] 0.33 2.24 4.68 32.27 [R] 7.52 51.88 [R] 1950 2.91 19.84 [R] .44 3.00 4.95 33.80 [R] 8.30 56.64 [R] 1951 3.05 19.40 [R] .52 3.32 [R] 5.69 36.19 [R] 9.26 58.92 [R] 1952 2.67 16.73 [R] .64 4.01 5.79 36.25 [R] 9.11 56.99 [R] 1953 2.55 15.79 [R] .76 4.67 [R] 6.32 39.06 [R] 9.63 59.52 [R] 1954 2.02 12.40 [R]

  11. The impact of environmental regulation on productivity in the US fossil-fueled power plants

    SciTech Connect (OSTI)

    Whang, J.

    1993-12-31

    The purpose of this dissertation is to examine the impact of environmental regulation on productivity in the U.S. fossil fueled electric generating industry. With the oil shocks, environmental regulation has been considered as one of the main culprits for the apparent productivity slowdown during the 1970`s. Even though new pieces of legislation are continuously enacted to regulate hazardous pollutants emitted, it is difficult to find thorough and meaningful analyses on the effects of regulation. Without exact measurement of regulation effects, it is not easy to design socially efficient environmental policies to reconcile several conflicting goals. Using plant-level production and environmental data for the last two decades, the effects of differentiated environmental regulation are carefully examined. Since unbalanced panel data set is used, fixed-effects and random-effects models are also examined. The estimated impact of environmental regulation explains 6 to 10 percent of the variation of total factor productivity growth rates. This appears to be a relatively mild effect compared with several previous studies.

  12. Determining NO{sub x} emissions from fossil fuel-fired sources

    SciTech Connect (OSTI)

    McNeel, A.

    1996-11-01

    To determine nitrogen oxides (NO{sub x}) emissions, the concentration of NO{sub x} within the stack gas must be determined. USEPA Reference Methods 7, 7A, 7C, 7D and/or 7E are the procedures to be used for NO{sub x} measurement as referenced in 40 CFR 60 subparts D, Da, Db and Dc - {open_quotes}Standards of performance for fossil fuel-fired steam generators...{open_quotes}. Depending upon the reason for determining NO{sub x} emissions, information in addition to NO{sub x} concentrations may be needed. Generally, USEPA Reference Methods 1 - 4 will be used to gather the additional data needed to satisfy the specific need for determining NO{sub x} emissions. The following text outlines the individual NO{sub x} sampling methodology, the relative costs of the reference method (RM) sampling, and the use of the resulting reference method data to calculate emissions in units of applicable standards.

  13. Improving the Carbon Dioxide Emission Estimates from the Combustion of Fossil Fuels in California

    SciTech Connect (OSTI)

    de la Rue du Can, Stephane; Wenzel, Tom; Price, Lynn

    2008-08-13

    Central to any study of climate change is the development of an emission inventory that identifies and quantifies the State's primary anthropogenic sources and sinks of greenhouse gas (GHG) emissions. CO2 emissions from fossil fuel combustion accounted for 80 percent of California GHG emissions (CARB, 2007a). Even though these CO2 emissions are well characterized in the existing state inventory, there still exist significant sources of uncertainties regarding their accuracy. This report evaluates the CO2 emissions accounting based on the California Energy Balance database (CALEB) developed by Lawrence Berkeley National Laboratory (LBNL), in terms of what improvements are needed and where uncertainties lie. The estimated uncertainty for total CO2 emissions ranges between -21 and +37 million metric tons (Mt), or -6percent and +11percent of total CO2 emissions. The report also identifies where improvements are needed for the upcoming updates of CALEB. However, it is worth noting that the California Air Resources Board (CARB) GHG inventory did not use CALEB data for all combustion estimates. Therefore the range in uncertainty estimated in this report does not apply to the CARB's GHG inventory. As much as possible, additional data sources used by CARB in the development of its GHG inventory are summarized in this report for consideration in future updates to CALEB.

  14. Separation of particulate from flue gas of fossil fuel combustion and gasification

    DOE Patents [OSTI]

    Yang, Wen-Ching; Newby, Richard A.; Lippert, Thomas E.

    1997-01-01

    The gas from combustion or gasification of fossil fuel contains flyash and other particulate. The flyash is separated from the gas in a plurality of standleg moving granular-bed filter modules. Each module includes a dipleg through which the bed media flows into the standleg. The bed media forms a first filter bed having an upper mass having a first frusto-conical surface in a frusto-conical member at the entrance to the standleg and a lower mass having a second frusto-conical surface of substantially greater area than the first surface after it passes through the standleg. A second filter media bed may be formed above the first filter media bed. The gas is fed tangentially into the module above the first surface. The flyash is captured on the first frusto-conical surface and within the bed mass. The processed gas flows out through the second frusto-conical surface and then through the second filter bed, if present. The bed media is cleaned of the captured flyash and recirculated to the moving granular bed filter. Alternatively, the bed media may be composed of the ash from the combustion which is pelletized to form agglomerates. The ash flows through the bed only once; it is not recycled.

  15. Separation of particulate from flue gas of fossil fuel combustion and gasification

    DOE Patents [OSTI]

    Yang, W.C.; Newby, R.A.; Lippert, T.E.

    1997-08-05

    The gas from combustion or gasification of fossil fuel contains fly ash and other particulates. The fly ash is separated from the gas in a plurality of standleg moving granular-bed filter modules. Each module includes a dipleg through which the bed media flows into the standleg. The bed media forms a first filter bed having an upper mass having a first frusto-conical surface in a frusto-conical member at the entrance to the standleg and a lower mass having a second frusto-conical surface of substantially greater area than the first surface after it passes through the standleg. A second filter media bed may be formed above the first filter media bed. The gas is fed tangentially into the module above the first surface. The fly ash is captured on the first frusto-conical surface and within the bed mass. The processed gas flows out through the second frusto-conical surface and then through the second filter bed, if present. The bed media is cleaned of the captured fly ash and recirculated to the moving granular bed filter. Alternatively, the bed media may be composed of the ash from the combustion which is pelletized to form agglomerates. The ash flows through the bed only once; it is not recycled. 11 figs.

  16. Dry Transfer Systems for Used Nuclear Fuel

    SciTech Connect (OSTI)

    Brett W. Carlsen; Michaele BradyRaap

    2012-05-01

    The potential need for a dry transfer system (DTS) to enable retrieval of used nuclear fuel (UNF) for inspection or repackaging will increase as the duration and quantity of fuel in dry storage increases. This report explores the uses for a DTS, identifies associated general functional requirements, and reviews existing and proposed systems that currently perform dry fuel transfers. The focus of this paper is on the need for a DTS to enable transfer of bare fuel assemblies. Dry transfer systems for UNF canisters are currently available and in use for transferring loaded canisters between the drying station and storage and transportation casks.

  17. Waste Stream Analyses for Nuclear Fuel Cycles

    SciTech Connect (OSTI)

    N. R. Soelberg

    2010-08-01

    A high-level study was performed in Fiscal Year 2009 for the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) Advanced Fuel Cycle Initiative (AFCI) to provide information for a range of nuclear fuel cycle options (Wigeland 2009). At that time, some fuel cycle options could not be adequately evaluated since they were not well defined and lacked sufficient information. As a result, five families of these fuel cycle options are being studied during Fiscal Year 2010 by the Systems Analysis Campaign for the DOE NE Fuel Cycle Research and Development (FCRD) program. The quality and completeness of data available to date for the fuel cycle options is insufficient to perform quantitative radioactive waste analyses using recommended metrics. This study has been limited thus far to qualitative analyses of waste streams from the candidate fuel cycle options, because quantitative data for wastes from the front end, fuel fabrication, reactor core structure, and used fuel for these options is generally not yet available.

  18. Nuclear fuel particles and method of making nuclear fuel compacts therefrom

    DOE Patents [OSTI]

    DeVelasco, Rubin I.; Adams, Charles C.

    1991-01-01

    Methods for making nuclear fuel compacts exhibiting low heavy metal contamination and fewer defective coatings following compact fabrication from a mixture of hardenable binder, such as petroleum pitch, and nuclear fuel particles having multiple layer fission-product-retentive coatings, with the dense outermost layer of the fission-product-retentive coating being surrounded by a protective overcoating, e.g., pyrocarbon having a density between about 1 and 1.3 g/cm.sup.3. Such particles can be pre-compacted in molds under relatively high pressures and then combined with a fluid binder which is ultimately carbonized to produce carbonaceous nuclear fuel compacts having relatively high fuel loadings.

  19. Method of monitoring stored nuclear fuel elements

    SciTech Connect (OSTI)

    Borloo, E.; Buergers, W.; Crutzen, S.; Vinche, C.

    1983-05-24

    To monitor a nuclear fuel element or fuel elements located in a store, e.g. a pond in a swimming pool reactor, the store is illuminated ultrasonically using one or more transducers transmitting ultrasonic signals in one or more predetermined directions to obtain an output which, because it depends on the number and relative location of the fuel elements in the store, and the structure of the store itself is distinctive to the fuel elements or elements stored therein. From this distinctive output is derived an identity unique to the stored fuel element or elements and a reference signal indicative of the whole structure when intact, the reference signal and identity being recorded. Subsequent ultrasonic testing of the store and its contents under identical operating conditions produces a signal which is compared to the recorded reference signal and if different therefrom reveals the occurrence of tampering with the store and/or the fuel element or elements.

  20. MOLTEN FLUORIDE NUCLEAR REACTOR FUEL

    DOE Patents [OSTI]

    Barton, C.J.; Grimes, W.R.

    1960-01-01

    Molten-salt reactor fuel compositions consisting of mixtures of fluoride salts are reported. In its broadest form, the composition contains an alkali fluoride such as sodium fluoride, zirconium tetrafluoride, and a uranium fluoride, the latter being the tetrafluoride or trifluoride or a mixture of the two. An outstanding property of these fuel compositions is a high coeffieient of thermal expansion which provides a negative temperature coefficient of reactivity in reactors in which they are used.

  1. An expanded review and comparison of greenhouse gas emissions from fossil fuel and geothermal electrical generating facilities

    SciTech Connect (OSTI)

    Booth, R.B.; Neil, P.E.

    1998-12-31

    This paper provides a review of the greenhouse gas emissions due to fossil fuel and geothermal electrical generation and to the emissions of their respective support activities. These support activities consist of, exploration, development, and transportation aspects of the fuel source, including waste management. These support activities could amount to an additional 6% for coal, 22% for oil, 13% for natural gas and 1% for geothermal. The presented methodologies and underlying principles can be used to better define the resultant emissions, rankings and global impacts of these electrical generating industries.

  2. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I.W.

    1992-05-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

  3. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I W; Mitchell, S J

    1990-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information.

  4. International nuclear fuel cycle fact book

    SciTech Connect (OSTI)

    Leigh, I.W.

    1988-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source or information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

  5. Comparison of AB2588 multipathway risk factors for California fossil-fuel power stations

    SciTech Connect (OSTI)

    Gratt, L.B.; Levin, L.

    1997-12-31

    Substances released from power plants may travel through various exposure pathways resulting in human health and environmental risks. The stack air emission`s primary pathway is inhalation from the ambient air. Multipathway factors (adjustment factors to the inhalation risk) are used to evaluate the importance of non-inhalation pathways (such as ingestion and dermal contact). The multipathway factor for a specific substance is the health risk by all pathways divided by the inhalation health risk for that substance. These factors are compared for fossil fuel power stations that submitted regulatory risk assessments in compliance with California Toxic Hot Spots Act (AB2588). Substances representing the largest contributions to the cancer risk are of primary concern: arsenic, beryllium, cadmium, chromium (+6), formaldehyde, nickel, lead, selenium, and PAHs. Comparisons of the chemical-specific multipathway factors show the impacts of regulatory policy decisions on the estimated health risk for trace substances. As an example, point estimates of the soil mixing depth, varying from 1 cm to 15 cm, relate to the relative importance of the pathway. For the deeper mixing depths, the root-zone uptake by homegrown tomato plants (for assumed consumption rate of 15% for San Diego) may result in high multipathway factors for several trace metals. For shallower mixing depths, soil ingestion may become the dominant non-inhalation pathway. These differences may lead to significantly different risk estimates for similar facilities located at different California locations such as to be under local regulatory authorities. The overall multipathway factor for the total cancer risk is about 2, much smaller than some of the chemical-specific factors. Science-based multipathway analysis should reduce much of the concern that may be due to policy-based decisions on pathway selection and high-value point-estimates of the parameters.

  6. Double-clad nuclear fuel safety rod

    DOE Patents [OSTI]

    McCarthy, William H.; Atcheson, Donald B.; Vaidyanathan, Swaminathan

    1984-01-01

    A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

  7. FutureGen: Stepping-Stone to Sustainable Fossil-Fuel Power Generation

    SciTech Connect (OSTI)

    Zitney, S.E.

    2006-11-01

    This presentation will highlight the U.S. Department of Energy's FutureGen Initiative. The nearly $1 billion government-industry project is a stepping-stone toward future coal-fired power plants that will produce hydrogen and electricity with zero-emissions, including carbon dioxide. The 275-megawatt FutureGen plant will initiate operations around 2012 and employ advanced coal gasification technology integrated with combined cycle electricity generation, hydrogen production, and carbon capture and sequestration. The initiative is a response to a presidential directive to develop a hydrogen economy by drawing upon the best scientific research to address the issue of global climate change. The FutureGen plant will be based on cutting-edge power generation technology as well as advanced carbon capture and sequestration systems. The centerpiece of the project will be coal gasification technology that can eliminate common air pollutants such as sulfur dioxide and nitrogen oxides and convert them to useable by-products. Gasification will convert coal into a highly enriched hydrogen gas, which can be burned much more cleanly than directly burning the coal itself. Alternatively, the hydrogen can be used in a fuel cell to produce ultra-clean electricity, or fed to a refinery to help upgrade petroleum products. Carbon sequestration will also be a key feature that will set the Futuregen plant apart from other electric power plant projects. The initial goal will be to capture 90 percent of the plant's carbon dioxide, but capture of nearly 100 percent may be possible with advanced technologies. Once captured, the carbon dioxide will be injected as a compressed fluid deep underground, perhaps into saline reservoirs. It could even be injected into oil or gas reservoirs, or into unmineable coal seams, to enhance petroleum or coalbed methane recovery. The ultimate goal for the FutureGen plant is to show how new technology can eliminate environmental concerns over the future use of coal--the most abundant fossil fuel in the United States with supplies projected to last 250 years. FutureGen's co-production of power and hydrogen will also serve as a stepping-stone to an environmentally sustainable energy future.

  8. Tennessee Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,401",15.9,"27,739",33.7 "Coal","8,805",41.1,"43,670",53.0 "Hydro and Pumped ...

  9. Texas Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,966",4.6,"41,335",10.0 "Coal","22,335",20.6,"150,173",36.5 "Hydro and Pumped ...

  10. Nuclear fuel elements made from nanophase materials

    DOE Patents [OSTI]

    Heubeck, N.B.

    1998-09-08

    A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics. 5 figs.

  11. Nuclear fuel elements made from nanophase materials

    DOE Patents [OSTI]

    Heubeck, Norman B.

    1998-01-01

    A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000.degree. F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics.

  12. Advanced LWR Nuclear Fuel Development

    Energy Savers [EERE]

    LWRS Overview and Select Research Highlights J. Busby and K. Leonard Oak Ridge National Laboratory with a host of contributors Overview Presentation for the Nuclear Energy Enabling Technologies September 15, 2015 Video Conference FY16 - Consolidated Innovative Nuclear Research * Light water reactor sustainability (LWRS) is one of the four technical areas in the Reactor Concepts Research, Development and Demonstration Program sections in the FOA. * Activities in LWRS also overlap with NEET

  13. Computational Design of Advanced Nuclear Fuels

    SciTech Connect (OSTI)

    Savrasov, Sergey; Kotliar, Gabriel; Haule, Kristjan

    2014-06-03

    The objective of the project was to develop a method for theoretical understanding of nuclear fuel materials whose physical and thermophysical properties can be predicted from first principles using a novel dynamical mean field method for electronic structure calculations. We concentrated our study on uranium, plutonium, their oxides, nitrides, carbides, as well as some rare earth materials whose 4f eletrons provide a simplified framework for understanding complex behavior of the f electrons. We addressed the issues connected to the electronic structure, lattice instabilities, phonon and magnon dynamics as well as thermal conductivity. This allowed us to evaluate characteristics of advanced nuclear fuel systems using computer based simulations and avoid costly experiments.

  14. SOLID GAS SUSPENSION NUCLEAR FUEL ASSEMBLY

    DOE Patents [OSTI]

    Schluderberg, D.C.; Ryon, J.W.

    1962-05-01

    A fuel assembly is designed for use in a gas-suspension cooled nuclear fuel reactor. The coolant fluid is an inert gas such as nitrogen or helium with particles such as carbon suspended therein. The fuel assembly is contained within an elongated pressure vessel extending down into the reactor. The fuel portion is at the lower end of the vessel and is constructed of cylindrical segments through which the coolant passes. Turbulence promotors within the passageways maintain the particles in agitation to increase its ability to transfer heat away from the outer walls. Shielding sections and alternating passageways above the fueled portion limit the escape of radiation out of the top of the vessel. (AEC)

  15. Locking support for nuclear fuel assemblies

    DOE Patents [OSTI]

    Ledin, Eric

    1980-01-01

    A locking device for supporting and locking a nuclear fuel assembly within a cylindrical bore formed by a support plate, the locking device including a support and locking sleeve having upwardly extending fingers forming wedge shaped contact portions arranged for interaction between an annular tapered surface on the fuel assembly and the support plate bore as well as downwardly extending fingers having wedge shaped contact portions arranged for interaction between an annularly tapered surface on the support plate bore and the fuel assembly whereby the sleeve tends to support and lock the fuel assembly in place within the bore by its own weight while facilitating removal and/or replacement of the fuel assembly.

  16. Development of Metal Oxide Nanostructure-based Optical Sensors for Fossil Fuel Derived Gases Measurement at High Temperature

    SciTech Connect (OSTI)

    Chen, Kevin

    2014-08-31

    This final technical report details research works performed supported by a Department of Energy grant (DE-FE0003859), which was awarded under the University Coal Research Program administrated by National Energy Technology Laboratory. This research program studied high temperature fiber sensor for harsh environment applications. It developed two fiber optical sensor platform technology including regenerative fiber Bragg grating sensors and distributed fiber optical sensing based on Rayleigh backscattering optical frequency domain reflectometry. Through the studies of chemical and thermal regenerative techniques for fiber Bragg grating (FBG) fabrication, high-temperature stable FBG sensors were successfully developed and fabricated in air-hole microstructured fibers, high-attenuation fibers, rare-earth doped fibers, and standard telecommunication fibers. By optimizing the laser processing and thermal annealing procedures, fiber grating sensors with stable performance up to 1100oC have been developed. Using these temperature-stable FBG gratings as sensor platform, fiber optical flow, temperature, pressure, and chemical sensors have been developed to operate at high temperatures up to 800oC. Through the integration of on-fiber functional coating, the use of application-specific air-hole microstructural fiber, and application of active fiber sensing scheme, distributed fiber sensor for temperature, pressure, flow, liquid level, and chemical sensing have been demonstrated with high spatial resolution (1-cm or better) with wide temperature ranges. These include the demonstration of 1) liquid level sensing from 77K to the room temperature, pressure/temperature sensing from the room temperature to 800C and from the 15psi to 2000 psi, and hydrogen concentration measurement from 0.2% to 10% with temperature ranges from the room temperature to 700C. Optical sensors developed by this program has broken several technical records including flow sensors with the highest operation temperature up to 750oC, first distributed chemical measurements at the record high temperature up to 700oC, first distributed pressure measurement at the record high temperature up to 800oC, and the fiber laser sensors with the record high operation temperature up to 700oC. The research performed by this program dramatically expand the functionality, adaptability, and applicability of distributed fiber optical sensors with potential applications in a number of high-temperature energy systems such as fossil-fuel power generation, high-temperature fuel cell applications, and potential for nuclear energy systems.

  17. Fundamental aspects of nuclear reactor fuel elements: solutions...

    Office of Scientific and Technical Information (OSTI)

    Citation Details In-Document Search Title: Fundamental aspects of nuclear reactor fuel ... Research Org: California Univ., Berkeley (USA). Dept. of Nuclear Engineering Country of ...

  18. Surrogate Spent Nuclear Fuel Vibration Integrity Investigation

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Bevard, Bruce Balkcom; Howard, Rob L

    2014-01-01

    Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading encountered during road or rail shipment. ORNL has been developing testing capabilities that can be used to improve our understanding of the impacts of vibration loading on SNF integrity, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet nuclear industry and U.S. Nuclear Regulatory Commission needs in the area of safety of SNF storage and transportation operations.

  19. Future nuclear fuel cycles: prospects and challenges

    SciTech Connect (OSTI)

    Boullis, Bernard

    2008-07-01

    Solvent extraction has played, from the early steps, a major role in the development of nuclear fuel cycle technologies, both in the front end and back end. Today's stakes in the field of energy enhance further than before the need for a sustainable management of nuclear materials. Recycling actinides appears as a main guideline, as much for saving resources as for minimizing the final waste impact, and many options can be considered. Strengthened by the important and outstanding performance of recent PUREX processing plants, solvent-extraction processes seem a privileged route to meet the new and challenging requirements of sustainable future nuclear systems. (author)

  20. Service experience, structural integrity, severe accidents, and erosion in nuclear and fossil plants. PVP-Volume 303

    SciTech Connect (OSTI)

    Paterson, S.R.; Bamford, W.H; Geraets, L.H.; Okazaki, M.; Cipolla, R.C.; Cowfer, C.D.; Means, K.H.

    1995-12-01

    The objective of this symposium was to disseminate information on service degradation and its prevention. Papers have been divided into the following topical sections: Service experience in nuclear plants; DOE high-level waste tank structural integrity panel--Summary reports; Severe accidents; Service experience in operating fossil power plants; and Erosion. Papers have been processed separately for inclusion on the data base.

  1. Spent Nuclear Fuel Alternative Technology Decision Analysis

    SciTech Connect (OSTI)

    Shedrow, C.B.

    1999-11-29

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

  2. Advanced LWR Nuclear Fuel Development

    Energy Savers [EERE]

    LOCALIZED DEFORMATION IN IRRADIATED AUSTENITIC STEELS ORNL: M.N. Gussev*, K.G. Field, J.T. Busby, K.J. Leonard, PNNL: T.S. Byun, University of Michigan: K.J. Stephenson, G.S. Was. 1 *Oak Ridge National Laboratory Fuel Cycle & Isotopes Division P.O. Box 2008, MS-6151 Oak Ridge, TN 37831, USA Tel. (865) 574-44-56 Fax. (865) 241-3650 gussevmn@ornl.gov Credits This presentation is based on several papers and conference talks presented/published recently. Some of these are listed below: SEM-EBSD

  3. Summary of nuclear fuel reprocessing activities around the world

    SciTech Connect (OSTI)

    Mellinger, P.J.; Harmon, K.M.; Lakey, L.T.

    1984-11-01

    This review of international practices for nuclear fuel reprocessing was prepared to provide a nontechnical summary of the current status of nuclear fuel reprocessing activities around the world. The sources of information are widely varied.

  4. Strategy for the Management and Disposal of Used Nuclear Fuel...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level ...

  5. Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of

  6. Spent Nuclear Fuel Containing U.S.-Origin

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany Maxcine Maxted, DOE-SR Spent Nuclear Fuel Program Manager February 4, 2016 Public Meeting on Draft Spent Nuclear Fuel from Germany Environmental Assessment www.energy.gov/EM 2 * Update on the National Environmental Policy Act (NEPA) process and a summary of information in the Draft Spent Nuclear Fuel from Germany Environmental Assessment (EA) * Status of EM's efforts on the feasibility study

  7. Supply Security in Future Nuclear Fuel Markets

    SciTech Connect (OSTI)

    Seward, Amy M.; Wood, Thomas W.; Gitau, Ernest T.; Ford, Benjamin E.

    2013-11-18

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs – that is, reactors likely to be licensed and market ready over the next several decades – that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  8. Ohio Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,134",6.5,"15,805",11.0 "Coal","21,360",64.6,"117,828",82.1 "Hydro and Pumped Storage",101,0.3,429,0.3 "Natural

  9. Pennsylvania Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","9,540",20.9,"77,828",33.9 "Coal","18,481",40.6,"110,369",48.0 "Hydro and Pumped

  10. Louisiana Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,142",8.0,"18,639",18.1 "Coal","3,417",12.8,"23,924",23.3 "Hydro and Pumped Storage",192,0.7,"1,109",1.1

  11. Maryland Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,705",13.6,"13,994",32.1 "Coal","4,886",39.0,"23,668",54.3 "Hydro and Pumped Storage",590,4.7,"1,667",3.8

  12. Massachusetts Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, smmer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",685,5.0,"5,918",13.8 "Coal","1,669",12.2,"8,306",19.4 "Hydro and Pumped Storage","1,942",14.2,659,1.5 "Natural

  13. Michigan Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy Source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,947",13.2,"29,625",26.6 "Coal","11,531",38.7,"65,604",58.8 "Hydro and Pumped Storage","2,109",7.1,228,0.2

  14. Minnesota Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,594",10.8,"13,478",25.1 "Coal","4,789",32.5,"28,083",52.3 "Hydro and Pumped Storage",193,1.3,840,1.6 "Natural

  15. Mississippi Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,251",8.0,"9,643",17.7 "Coal","2,526",16.1,"13,629",25.0 "Natural Gas","11,640",74.2,"29,619",54.4

  16. Nebraska Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,245",15.8,"11,054",30.2 "Coal","3,932",50.0,"23,363",63.8 "Hydro and Pumped Storage",278,3.5,"1,314",3.6

  17. Alabama Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","5,043",15.6,"37,941",24.9 "Coal","11,441",35.3,"63,050",41.4 "Hydro and Pumped

  18. Arizona Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",3937,14.9,"31,200",27.9 "Coal","6,233",23.6,"43,644",39.1 "Hydro and Pumped Storage","2,937",11.1,"6,831",6.1

  19. Arkansas Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,835",11.5,"15,023",24.6 "Coal","4,535",28.4,"28,152",46.2 "Hydro and Pumped

  20. California Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,390",6.5,"32,201",15.8 "Coal",374,0.6,"2,100",1.0 "Hydro and Pumped Storage","13,954",20.7,"33,260",16.3

  1. Connecticut Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,103",25.4,"16,750",50.2 "Coal",564,6.8,"2,604",7.8 "Hydro and Pumped Storage",151,1.8,400,1.2 "Natural

  2. Florida Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,924",6.6,"23,936",10.4 "Coal","9,975",16.9,"59,897",26.1 "Hydro and Pumped Storage",55,0.1,177,0.1 "Natural

  3. Georgia Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,061",11.1,"33,512",24.4 "Coal","13,230",36.1,"73,298",53.3 "Hydro and Pumped

  4. Illinois Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","11,441",25.9,"96,190",47.8 "Coal","15,551",35.2,"93,611",46.5 "Hydro and Pumped Storage",34,0.1,119,0.1 "Natural

  5. Iowa Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",601,4.1,"4,451",7.7 "Coal","6,956",47.7,"41,283",71.8 "Hydro and Pumped Storage",144,1.0,948,1.6 "Natural

  6. Kansas Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,160",9.2,"9,556",19.9 "Coal","5,179",41.3,"32,505",67.8 "Hydro and Pumped Storage",3,"*",13,"*"

  7. Vermont Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",620,55.0,"4,782",72.2 "Hydro and Pumped Storage",324,28.7,"1,347",20.3 "Natural Gas","-","-",4,0.1 "Other

  8. Virginia Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,501",14.5,"26,572",36.4 "Coal","5,868",24.3,"25,459",34.9 "Hydro and Pumped Storage","4,107",17.0,10,"*"

  9. Wisconsin Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,584",8.9,"13,281",20.7 "Coal","8,063",45.2,"40,169",62.5 "Hydro and Pumped Storage",492,2.8,"2,112",3.3

  10. Nuclear Fuel Storage and Transportation Planning Project Overview |

    Energy Savers [EERE]

    Department of Energy Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project Overview PDF icon Nuclear Fuel Storage and Transportation Planning Project Overview More Documents & Publications Section 180(c) Ad Hoc Working Group DOE Office of Nuclear Energy Transportation Plan Ad Hoc Working Group

  11. General circulation model calculations of the direct radiative forcing by anthropogenic sulfate and fossil-fuel soot aerosol

    SciTech Connect (OSTI)

    Haywood, J.M.; Roberts, D.L.; Slingo, A.

    1997-07-01

    A new radiation code within a general circulation model is used to assess the direct solar and thermal radiative forcing by sulfate aerosol of anthropogenic origin and soot aerosol from fossil-fuel burning. The radiative effects of different aerosol profiles, relative humidity parameterizations, chemical compositions, and internal and external mixtures of the two aerosol types are investigated. The contribution to the radiative forcing from cloudy sky regions is found to be negligible for sulfate aerosol; this is in contrast to recent studies where the cloudy sky contribution was estimated using a method in which the spatial correlation between cloud amount and sulfate burden was ignored. However, the radiative forcing due to fossil-fuel soot aerosol is enhanced in cloudy regions if soot aerosol exists within or above the cloud. The global solar radiative forcing due to sulfate aerosol is estimated to be -0.38 W m{sup -2} and the global thermal radiative forcing is estimated to be +0.01 W m{sup -2}. The hemispheric mean radiative forcings vary by only about 10% for reasonable assumptions about the chemical form of the sulfate aerosol and the relative humidity dependence; the uncertainties in the aerosol loading are far more significant. If a soot/sulfate mass ratio of 0.075 is assumed, then the global solar radiative forcing weakens to -0.18 W m{sup -2} for an external mixture and weakens further for an internal mixture. Additionally, the spatial distribution of the radiative forcing shows strong negative/positive forcing contrasts that may influence the dynamical response of the atmosphere. Although these results are extremely sensitive to the adopted soot/sulfate ratio and the assumed vertical profile, they indicate that fossil-fuel soot aerosol may exert a nonnegligible radiative forcing and emphasize the need to consider each anthropogenic aerosol species. 58 refs., 8 figs., 1 tab.

  12. Toward Verifying Fossil Fuel CO2 Emissions with the CMAQ Model: Motivation, Model Description and Initial Simulation

    SciTech Connect (OSTI)

    Liu, Zhen; Bambha, Ray P.; Pinto, Joseph P.; Zeng, Tao; Boylan, Jim; Huang, Maoyi; Lei, Huimin; Zhao, Chun; Liu, Shishi; Mao, Jiafu; Schwalm, Christopher R.; Shi, Xiaoying; Wei, Yaxing; Michelsen, Hope A.

    2014-03-14

    Motivated by the urgent need for emission verification of CO2 and other greenhouse gases, we have developed regional CO2 simulation with CMAQ over the contiguous U.S. Model sensitivity experiments have been performed using three different sets of inputs for net ecosystem exchange (NEE) and two fossil fuel emission inventories, to understand the roles of fossil fuel emissions, atmosphere-biosphere exchange and transport in regulating the spatial and diurnal variability of CO2 near the surface, and to characterize the well-known signal-to-noise problem, i.e. the interference from the biosphere on the interpretation of atmospheric CO2 observations. It is found that differences in the meteorological conditions for different urban areas strongly contribute to the contrast in concentrations. The uncertainty of NEE, as measured by the difference among the three different NEE inputs, has notable impact on regional distribution of CO2 simulated by CMAQ. Larger NEE uncertainty and impact are found over eastern U.S. urban areas than along the western coast. A comparison with tower CO2 measurements at Boulder Atmospheric Observatory (BAO) shows that the CMAQ model using hourly varied and high-resolution CO2 emission from the Vulcan inventory and CarbonTracker optimized NEE reasonably reproduce the observed diurnal profile, whereas switching to different NEE inputs significantly degrades the model performance. Spatial distribution of CO2 is found to correlate with NOx, SO2 and CO, due to their similarity in emission sources and transport processes. These initial results from CMAQ demonstrate the power of a state-of-the art CTM in helping interpret CO2 observations and verify fossil fuel emissions. The ability to simulate CO2 in CMAQ will also facilitate investigations of the utility of traditionally regulated pollutants and other species as tracers to CO2 source attribution.

  13. Nuclear power generation and fuel cycle report 1996

    SciTech Connect (OSTI)

    1996-10-01

    This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

  14. Missouri Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,190",5.5,"8,996",9.7 "Coal","12,070",55.5,"75,047",81.3 "Hydro and Pumped Storage","1,221",5.6,"2,427",2.6

  15. Washington Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary Energy Source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,097",3.6,"9,241",8.9 "Coal","1,340",4.4,"8,527",8.2 "Hydro and Pumped Storage","21,495",70.5,"68,342",66.0

  16. Estimates of health risks associated with radionuclide emissions from fossil-fueled steam-electric generating plants. Final report

    SciTech Connect (OSTI)

    Nelson, C.

    1995-08-01

    Under the Title III, Section 112 of the 1990 Clean Air Act Amendment, Congress directed the U.S. Environmental Protection Agency (EPA) to perform a study of the hazards to public resulting from pollutants emitted by electric utility system generating units. Radionuclides are among the groups of pollutants listed in the amendment. This report updates previously published data and estimates with more recently available information regarding the radionuclide contents of fossil fuels, associated emissions by steam-electric power plants, and potential health effects to exposed population groups.

  17. Nuclear reactor fuel rod attachment system

    DOE Patents [OSTI]

    Not Available

    1980-09-17

    A reusable system is described for removably attaching a nuclear reactor fuel rod to a support member. A locking cap is secured to the fuel rod and a locking strip is fastened to the support member. The locking cap has two opposing fingers shaped to form a socket having a body portion. The locking strip has an extension shaped to rigidly attach to the socket's body portion. The locking cap's fingers are resiliently deflectable. For attachment, the locking cap is longitudinally pushed onto the locking strip causing the extension to temporarily deflect open the fingers to engage the socket's body portion. For removal, the process is reversed.

  18. Categorization of Used Nuclear Fuel Inventory in Support of a Comprehensive National Nuclear Fuel Cycle Strategy

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Energy has conducted a technical review and assessment of the total current inventory [~70,150 MTHM as of 2011] of domestic discharged used nuclear fuel (UNF) and estimated an amount to be considered for retention in support of research, development, demonstration, and national security interests.

  19. Pyrochemical processing of DOE spent nuclear fuel

    SciTech Connect (OSTI)

    Laidler, J.J.

    1995-02-01

    A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (>99.9%) separation of transuranics. The resultant waste forms from the pyroprocess, are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and avoid the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

  20. Method and apparatus for close packing of nuclear fuel assemblies

    DOE Patents [OSTI]

    Newman, D.F.

    1993-03-30

    The apparatus of the present invention is a plate of neutron absorbing material. The plate may have a releasable locking feature permitting the plate to be secured within a nuclear fuel assembly between nuclear fuel rods during storage or transportation then removed for further use or destruction. The method of the present invention has the step of placing a plate of neutron absorbing material between nuclear fuel rods within a nuclear fuel assembly, preferably between the two outermost columns of nuclear fuel rods. Additionally, the plate may be releasably locked in place.

  1. Method and apparatus for close packing of nuclear fuel assemblies

    DOE Patents [OSTI]

    Newman, Darrell F.

    1993-01-01

    The apparatus of the present invention is a plate of neutron absorbing material. The plate may have a releasable locking feature permitting the plate to be secured within a nuclear fuel assembly between nuclear fuel rods during storage or transportation then removed for further use or destruction. The method of the present invention has the step of placing a plate of neutron absorbing material between nuclear fuel rods within a nuclear fuel assembly, preferably between the two outermost columns of nuclear fuel rods. Additionally, the plate may be releasably locked in place.

  2. POWER GENERATION FROM LIQUID METAL NUCLEAR FUEL

    DOE Patents [OSTI]

    Dwyer, O.E.

    1958-12-23

    A nuclear reactor system is described wherein the reactor is the type using a liquid metal fuel, such as a dispersion of fissile material in bismuth. The reactor is designed ln the form of a closed loop having a core sectlon and heat exchanger sections. The liquid fuel is clrculated through the loop undergoing flssion in the core section to produce heat energy and transferrlng this heat energy to secondary fluids in the heat exchanger sections. The fission in the core may be produced by a separate neutron source or by a selfsustained chain reaction of the liquid fuel present in the core section. Additional auxiliary heat exchangers are used in the system to convert water into steam which drives a turbine.

  3. Financing Strategies for Nuclear Fuel Cycle Facility

    SciTech Connect (OSTI)

    David Shropshire; Sharon Chandler

    2005-12-01

    To help meet our nation’s energy needs, reprocessing of spent nuclear fuel is being considered more and more as a necessary step in a future nuclear fuel cycle, but incorporating this step into the fuel cycle will require considerable investment. This report presents an evaluation of financing scenarios for reprocessing facilities integrated into the nuclear fuel cycle. A range of options, from fully government owned to fully private owned, was evaluated using a DPL (Dynamic Programming Language) 6.0 model, which can systematically optimize outcomes based on user-defined criteria (e.g., lowest life-cycle cost, lowest unit cost). Though all business decisions follow similar logic with regard to financing, reprocessing facilities are an exception due to the range of financing options available. The evaluation concludes that lowest unit costs and lifetime costs follow a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. Other financing arrangements, however, including regulated utility ownership and a hybrid ownership scheme, led to acceptable costs, below the Nuclear Energy Agency published estimates. Overwhelmingly, uncertainty in annual capacity led to the greatest fluctuations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; the annual operating costs dominate the government case. It is concluded that to finance the construction and operation of such a facility without government ownership could be feasible with measures taken to mitigate risk, and that factors besides unit costs should be considered (e.g., legal issues, social effects, proliferation concerns) before making a decision on financing strategy.

  4. NUCLEAR REACTOR AND THERMIONIC FUEL ELEMENT THEREFOR

    DOE Patents [OSTI]

    Rasor, N.S.; Hirsch, R.L.

    1963-12-01

    The patent relates to the direct conversion of fission heat to electricity by use of thermionic plasma diodes having fissionable material cathodes, said diodes arranged to form a critical mass in a nuclear reactor. The patent describes a fuel element comprising a plurality of diodes each having a fissionable material cathode, an anode around said cathode, and an ionizable gas therebetween. Provision is made for flowing the gas and current serially through the diodes. (AEC)

  5. Report on interim storage of spent nuclear fuel

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The report on interim storage of spent nuclear fuel discusses the technical, regulatory, and economic aspects of spent-fuel storage at nuclear reactors. The report is intended to provide legislators state officials and citizens in the Midwest with information on spent-fuel inventories, current and projected additional storage requirements, licensing, storage technologies, and actions taken by various utilities in the Midwest to augment their capacity to store spent nuclear fuel on site.

  6. Assessment and comparison of waste management costs for nuclear and fossil energy sources

    SciTech Connect (OSTI)

    Long, F.G.; Zaccai, H.; Ward, R.D.; McNicholas, P.; Albers, R.W.

    1993-12-31

    This paper presents the key results of an assessment of waste management costs undertaken by a group of international experts on behalf of the IAEA, Vienna. The objective of this work is to provide an assessment and comparison of the impact of waste management on the cost of electricity production from nuclear and other energy sources. The study focuses on the cost of managing wastes arising from the production of electricity from a PWR, with and without reprocessing, a coal-fueled conventional steam cycle, and a gas-fueled combined cycle; using data available in the open literature. This study has only assessed the impact of those waste management costs which are typically internalized by an electric utility and passed on as part of the price charged to customers. The data utilized in the study is typically in range form, reflecting worldwide experience with such factors as technology, regulatory requirements and economic parameters. To the extent that estimates can be identified in the literature the study has attempted to include costs associated with waste management from all stages of the fuel cycles. This paper also includes a discussion of future developments which may influence the results of this work including the effect of technology advances and changes in regulatory requirements.

  7. RADIOACTIVE WASTE STREAMS FROM VARIOUS POTENTIAL NUCLEAR FUEL CYCLE OPTIONS

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Conference: RADIOACTIVE WASTE STREAMS FROM VARIOUS POTENTIAL NUCLEAR FUEL CYCLE OPTIONS Citation Details In-Document Search Title: RADIOACTIVE WASTE STREAMS FROM VARIOUS POTENTIAL NUCLEAR FUEL CYCLE OPTIONS Five fuel cycle options, about which little is known compared to more commonly known options, have been studied in the past year for the United States Department of Energy. These fuel cycle options, and their features relative to uranium-fueled light water

  8. Advanced Nuclear Fuel | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Lithium-based Technologies / Advanced Nuclear Fuel Advanced Nuclear Fuel Y-12 developers co-roll zirconium clad LEU-Mo. The Y-12 National Security Complex has over 60 years of reactor fuel experience and for more than 25 years has supplied feedstock material for U.S. research reactor fuel. Now, Y-12's materials science expertise contributes to nonproliferation progress and advances new fuel development. Uranium/molybdenum foils are essential for conversion of high-power research reactors that

  9. Optimally moderated nuclear fission reactor and fuel source therefor

    DOE Patents [OSTI]

    Ougouag, Abderrafi M.; Terry, William K.; Gougar, Hans D.

    2008-07-22

    An improved nuclear fission reactor of the continuous fueling type involves determining an asymptotic equilibrium state for the nuclear fission reactor and providing the reactor with a moderator-to-fuel ratio that is optimally moderated for the asymptotic equilibrium state of the nuclear fission reactor; the fuel-to-moderator ratio allowing the nuclear fission reactor to be substantially continuously operated in an optimally moderated state.

  10. EPRI-DOE Joint Report Focuses on Fossil Fleet Transition with Fuel Changes and Large Scale Variable Renewable Integration

    Broader source: Energy.gov [DOE]

    The Energy Department released a report on fossil fleet transition with renewable integration, describing operational and engineering challenges to the fossil generation fleet.

  11. Dynamic Systems Analysis Report for Nuclear Fuel Recycle

    SciTech Connect (OSTI)

    Brent Dixon; Sonny Kim; David Shropshire; Steven Piet; Gretchen Matthern; Bill Halsey

    2008-12-01

    This report examines the time-dependent dynamics of transitioning from the current United States (U.S.) nuclear fuel cycle where used nuclear fuel is disposed in a repository to a closed fuel cycle where the used fuel is recycled and only fission products and waste are disposed. The report is intended to help inform policy developers, decision makers, and program managers of system-level options and constraints as they guide the formulation and implementation of advanced fuel cycle development and demonstration efforts and move toward deployment of nuclear fuel recycling infrastructure.

  12. Los Alamos Lab: Fossil Energy & Environment, Home

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Office of Fossil Energy, as well as projects supported by the Department of Interior ... to the entire fossil fuel cycle, from exploration and production to capture and storage ...

  13. Pyroprocess for processing spent nuclear fuel

    DOE Patents [OSTI]

    Miller, William E.; Tomczuk, Zygmunt

    2002-01-01

    This is a pyroprocess for processing spent nuclear fuel. The spent nuclear fuel is chopped into pieces and placed in a basket which is lowered in to a liquid salt solution. The salt is rich in ZrF.sub.4 and containing alkali or alkaline earth fluorides, and in particular, the salt chosen was LiF-50 mol % ZrF.sub.4 with a eutectic melting point of 500.degree. C. Prior to lowering the basket, the salt is heated to a temperature of between 550.degree. C. and 700.degree. C. in order to obtain a molten solution. After dissolution the oxides of U, Th, rare earth and other like oxides, the salt bath solution is subject to hydro-fluorination to remove the oxygen and then to a fluorination step to remove U as gaseous UF.sub.6. In addition, after dissolution, the basket contains PuO.sub.2 and undissolved parts of the fuel rods, and the basket and its contents are processed to remove the Pu.

  14. Nuclear fuel rods along the sand dunes

    SciTech Connect (OSTI)

    Regan, M.B.

    1993-05-10

    Just north of the small town of Covert, Michigan, Consumers Power Co. officials and environmental activists are locked in a battle that marks a new phase in the nation's long-running struggle over nuclear power. The company's Palisades power plant reactor needs refueling. But the utility has no more room for the spent fuel rods it must place in its water-filled storage pool. So Consumers is taking advantage of a 1990 Nuclear Regulatory Commission rule that lets utilities store waste above ground without agency review. Palisades officials plan to transfer older radioactive fuel rods from its storage pool into concrete and steel silo-like casks on a site overlooking Lake Michigan. Over the next decade, nearly half of the nation's 109 operating nuclear plants will run out of space in water-filled storage pools and be forced to consider aboveground storage. The Palisades plant is causing a stir because it is the first to exploit the 1990 NRC rule, which doesn't require utilities to seek approval for waste-storage sites as long as the waste is stored in an approved container. Before 1990, five other utilities had received the agency O.K. for above-ground storage - but only after a lengthy and exhaustive analysis of each site.

  15. Spent Nuclear Fuel Vibration Integrity Study

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Jiang, Hao; Yan, Yong; Bevard, Bruce Balkcom

    2016-01-01

    The objective of this research is to collect dynamic experimental data on spent nuclear fuel (SNF) under simulated transportation environments using the Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT), the hot-cell testing technology developed at Oak Ridge National Laboratory (ORNL). The collected CIRFT data will be utilized to support ongoing spent fuel modeling activities, and support SNF transportation related licensing issues. Recent testing to understand the effects of hydride reorientation on SNF vibration integrity is also being evaluated. CIRFT results have provided insight into the fuel/clad system response to transportation related loads. The major findings of CIRFT on the HBU SNF are as follows: SNF system interface bonding plays an important role in SNF vibration performance, Fuel structure contributes to the SNF system stiffness, There are significant variations in stress and curvature of SNF systems during vibration cycles resulting from segment pellets and clad interaction, and SNF failure initiates at the pellet-pellet interface region and appears to be spontaneous. Because of the non-homogeneous composite structure of the SNF system, finite element analyses (FEA) are needed to translate the global moment-curvature measurement into local stress-strain profiles. The detailed mechanisms of the pellet-pellet and pellet-clad interactions and the stress concentration effects at the pellet-pellet interface cannot be readily obtained directly from a CIRFT system measurement. Therefore, detailed FEA is used to understand the global test response, and that data will also be presented.

  16. Nuclear reactor fuel rod attachment system

    DOE Patents [OSTI]

    Christiansen, David W. (Kennewick, WA)

    1982-01-01

    A reusable system for removably attaching a nuclear reactor fuel rod (12) to a support member (14). A locking cap (22) is secured to the fuel rod (12) and a locking strip (24) is fastened to the support member (14). The locking cap (22) has two opposing fingers (24a and 24b) shaped to form a socket having a body portion (26). The locking strip has an extension (36) shaped to rigidly attach to the socket's body portion (26). The locking cap's fingers are resiliently deflectable. For attachment, the locking cap (22) is longitudinally pushed onto the locking strip (24) causing the extension (36) to temporarily deflect open the fingers (24a and 24b) to engage the socket's body portion (26). For removal, the process is reversed.

  17. Fuel handling system for a nuclear reactor

    DOE Patents [OSTI]

    Saiveau, James G.; Kann, William J.; Burelbach, James P.

    1986-01-01

    A pool type nuclear fission reactor has a core, with a plurality of core elements and a redan which confines coolant as a hot pool at a first end of the core separated from a cold pool at a second end of the core by the redan. A fuel handling system for use with such reactors comprises a core element storage basket located outside of the redan in the cold pool. An access passage is formed in the redan with a gate for opening and closing the passage to maintain the temperature differential between the hot pool and the cold pool. A mechanism is provided for opening and closing the gate. A lifting arm is also provided for manipulating the fuel core elements through the access passage between the storage basket and the core when the redan gate is open.

  18. Development of Nano-crystalline Doped-Ceramic Enabled Fiber Sensors for High Temperature In-Situ Monitoring of Fossil Fuel Gases

    SciTech Connect (OSTI)

    Xiao, Hai; Dong, Junhang; Lin, Jerry; Romero, Van

    2012-03-01

    This is a final technical report for the first project year from July 1, 2005 to Jan 31, 2012 for DoE/NETL funded project DE-FC26-05NT42439: Development of Nanocrystalline Doped-Ceramic Enabled Fiber Sensors for High Temperature In-Situ Monitoring of Fossil Fuel Gases. This report summarizes the technical progresses and achievements towards the development of novel nanocrystalline doped ceramic material-enabled optical fiber sensors for in situ and real time monitoring the gas composition of flue or hot gas streams involved in fossil-fuel based power generation and hydrogen production.

  19. Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads

    SciTech Connect (OSTI)

    2013-07-01

    The Global conference is a forum for the discussion of the scientific, technical, social and regulatory aspects of the nuclear fuel cycle. Relevant topics include global utilization of nuclear energy, current fuel cycle technologies, advanced reactors, advanced fuel cycles, nuclear nonproliferation and public acceptance.

  20. Can industry`s `fourth` fossil fuel establish presence in US?

    SciTech Connect (OSTI)

    Armor, A.F.; Dene, C.E.

    1996-09-01

    After five years of commercial experience burning Orimulsion overseas, US utilities are now evaluating the new fuel as a serious alternative to oil. In their relentless drive to remain competitive, electric utilities with oil-fired generating units are searching for lower cost fuel alternatives. Because of high fuel prices, oil-fired units have low capacity factors. Only 23 out of 142 oil-capable units in the US had capacity factors greater than 50% in 1993; the average was a mere 24%. Utility consumption of fuel oil slid from over 600,000 barrels (bbl)/day in 1989 to less than 200,000 bbl/day last year. Orimulsion now fuels nearly 3,000 MW/yr worldwide. The UK`s PowerGen Ltd, currently the world`s largest consumer of Orimulsion, fires some 10-million bbl/yr at two 500-MW units at its Ince plant and three 120-MW units at its Richborough plant. Both plants formerly burned fuel oil, and have been using Orimulsion since 1991. Canada`s New Brunswick Power Corp has fired Orimulsion in two units at its Dalhousie plant since 1994 (Power, April 1995, p 27); one 105-MW unit was originally designed for fuel oil, the other 212-MW unit was designed for coal. Last year, Denmark`s SK Power converted its coal-fired, 700-MW Asnaes Unit 5 to Orimulsion firing. And in the US, Florida Power and Light Co. (FP and L) has signed a 20-yr fuel supply contract with Bitor America Corp (Boca Raton, Fla.), for two 800-MW units at the oil-fired Manatee plant, contingent on securing necessary permits. The Manatee installation (Power, September 1994, p 57) would be the first in the US to burn the fuel. Today, five years after Orimulsion begun to be used commercially, many of the lingering questions involving the new fuel`s handling, transportation, combustion, emissions control, spill control, and waste utilization have been settled. Several US utilities have expressed serious interest in the fuel as an alternative to oil.

  1. Radioactive Semivolatiles in Nuclear Fuel Reprocessing

    SciTech Connect (OSTI)

    Jubin, R. T.; Strachan, D. M.; Ilas, G.; Spencer, B. B.; Soelberg, N. R.

    2014-09-01

    In nuclear fuel reprocessing, various radioactive elements enter the gas phase from the unit operations found in the reprocessing facility. In previous reports, the pathways and required removal were discussed for four radionuclides known to be volatile, 14C, 3H, 129I, and 85Kr. Other, less volatile isotopes can also report to the off-gas streams in a reprocessing facility. These were reported to be isotopes of Cs, Cd, Ru, Sb, Tc, and Te. In this report, an effort is made to determine which, if any, of 24 semivolatile radionuclides could be released from a reprocessing plant and, if so, what would be the likely quantities released. As part of this study of semivolatile elements, the amount of each generated during fission is included as part of the assessment for the need to control their emission. Also included in this study is the assessment of the cooling time (time out of reactor) before the fuel is processed. This aspect is important for the short-lived isotopes shown in the list, especially for cooling times approaching 10 y. The approach taken in this study was to determine if semivolatile radionuclides need to be included in a list of gas-phase radionuclides that might need to be removed to meet Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. A list of possible elements was developed through a literature search and through knowledge and literature on the chemical processes in typical aqueous processing of nuclear fuels. A long list of possible radionuclides present in irradiated fuel was generated and then trimmed by considering isotope half-life and calculating the dose from each to a maximum exposed individual with the US EPA airborne radiological dispersion and risk assessment code CAP88 (Rosnick 1992) to yield a short list of elements that actually need to be considered for control because they require high decontamination factors to meet a reasonable fraction of the regulated release. Each of these elements is then discussed with respect to what is known in the literature about their behavior in a reprocessing facility. The context for the evaluation in this document is a UO2-based fuel processed through an aqueous-based reprocessing system with a TBP-based solvent extraction chemistry. None of these elements form sufficiently volatile compounds in the context of the reprocessing facility to be of regulatory concern.

  2. Fuel assembly transfer basket for pool type nuclear reactor vessels

    DOE Patents [OSTI]

    Fanning, Alan W.; Ramsour, Nicholas L.

    1991-01-01

    A fuel assembly transfer basket for a pool type, liquid metal cooled nuclear reactor having a side access loading and unloading port for receiving and relinquishing fuel assemblies during transfer.

  3. EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing...

    Energy Savers [EERE]

    Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin...

  4. Spent nuclear fuel project path forward preliminary safety evaluation

    SciTech Connect (OSTI)

    Brehm, J.R.; Crowe, R.D.; Siemer, J.M.; Wojdac, L.F.; Hosler, A.G.

    1995-03-01

    This preliminary safety evaluation (PSE) provides validation of the initial project design criteria for the Spent Nuclear Fuel Project (SNFP) Path Forward for removal of fuel from K Basins.

  5. Gap Analysis to Support Extended Storage of Used Nuclear Fuel

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development...

  6. DOE SPENT NUCLEAR FUEL DISPOSAL CONTAINER

    SciTech Connect (OSTI)

    F. Habashi

    1998-06-26

    The DOE Spent Nuclear Fuel Disposal Container (SNF DC) supports the confinement and isolation of waste within the Engineered Barrier System of the Mined Geologic Disposal System (MGDS). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the access mains, and emplaced in emplacement drifts. The DOE Spent Nuclear Fuel Disposal Container provides long term confinement of DOE SNF waste, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The DOE SNF Disposal Containers provide containment of waste for a designated period of time, and limit radionuclide release thereafter. The disposal containers maintain the waste in a designated configuration, withstand maximum handling and rockfall loads, limit the individual waste canister temperatures after emplacement. The disposal containers also limit the introduction of moderator into the disposal container during the criticality control period, resist corrosion in the expected repository environment, and provide complete or limited containment of waste in the event of an accident. Multiple disposal container designs may be needed to accommodate the expected range of DOE Spent Nuclear Fuel. The disposal container will include outer and inner barrier walls and outer and inner barrier lids. Exterior labels will identify the disposal container and contents. Differing metal barriers will support the design philosophy of defense in depth. The use of materials with different failure mechanisms prevents a single mode failure from breaching the waste package. The corrosion-resistant inner barrier and inner barrier lid will be constructed of a high-nickel alloy and the corrosion-allowance outer barrier and outer barrier lid will be made of carbon steel. The DOE Spent Nuclear Fuel Disposal Containers interface with the emplacement drift environment by transferring heat from the waste to the external environment and by protecting the DOE waste canisters and their contents from damage/degradation by the external environment. The disposal containers also interface with the SNF by limiting access of moderator and oxidizing agents to the waste. The disposal containers interface with the Ex-Container System's emplacement drift disposal container supports. The disposal containers interface with the Canister Transfer System, Waste Emplacement System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and remediation of the disposal container.

  7. International nuclear fuel cycle fact book. Revision 6

    SciTech Connect (OSTI)

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

    1986-01-01

    The International Fuel Cycle Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2.

  8. Nonproliferation Uncertainties, a Major Barrier to Used Nuclear Fuel

    Office of Scientific and Technical Information (OSTI)

    Recycle in the United States (Conference) | SciTech Connect SciTech Connect Search Results Conference: Nonproliferation Uncertainties, a Major Barrier to Used Nuclear Fuel Recycle in the United States Citation Details In-Document Search Title: Nonproliferation Uncertainties, a Major Barrier to Used Nuclear Fuel Recycle in the United States A study and comparison of the goals and understandings of nonproliferation authorities with those of used nuclear fuel (UNF) recycle advocates have

  9. EA-1977: Acceptance and Disposition of Spent Nuclear Fuel Containing

    Energy Savers [EERE]

    U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany | Department of Energy 7: Acceptance and Disposition of Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany EA-1977: Acceptance and Disposition of Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany SUMMARY This EA will evaluate the potential environmental impacts of a DOE proposal to accept spent nuclear fuel from the

  10. A multiresolution spatial parametrization for the estimation of fossil-fuel carbon dioxide emissions via atmospheric inversions.

    SciTech Connect (OSTI)

    Ray, Jaideep; Lee, Jina; Lefantzi, Sophia; Yadav, Vineet; Michalak, Anna M.; van Bloemen Waanders, Bart Gustaaf; McKenna, Sean Andrew

    2013-04-01

    The estimation of fossil-fuel CO2 emissions (ffCO2) from limited ground-based and satellite measurements of CO2 concentrations will form a key component of the monitoring of treaties aimed at the abatement of greenhouse gas emissions. To that end, we construct a multiresolution spatial parametrization for fossil-fuel CO2 emissions (ffCO2), to be used in atmospheric inversions. Such a parametrization does not currently exist. The parametrization uses wavelets to accurately capture the multiscale, nonstationary nature of ffCO2 emissions and employs proxies of human habitation, e.g., images of lights at night and maps of built-up areas to reduce the dimensionality of the multiresolution parametrization. The parametrization is used in a synthetic data inversion to test its suitability for use in atmospheric inverse problem. This linear inverse problem is predicated on observations of ffCO2 concentrations collected at measurement towers. We adapt a convex optimization technique, commonly used in the reconstruction of compressively sensed images, to perform sparse reconstruction of the time-variant ffCO2 emission field. We also borrow concepts from compressive sensing to impose boundary conditions i.e., to limit ffCO2 emissions within an irregularly shaped region (the United States, in our case). We find that the optimization algorithm performs a data-driven sparsification of the spatial parametrization and retains only of those wavelets whose weights could be estimated from the observations. Further, our method for the imposition of boundary conditions leads to a 10computational saving over conventional means of doing so. We conclude with a discussion of the accuracy of the estimated emissions and the suitability of the spatial parametrization for use in inverse problems with a significant degree of regularization.

  11. EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EIS-0203-SA-07: Supplement Analysis Proposed Shipment of Commercial Spent Nuclear Fuel to DOE National Laboratories for Research and Development Purposes (DOEEIS-0203-SA-07 and ...

  12. EM Safely and Efficiently Manages Spent Nuclear Fuel

    Broader source: Energy.gov [DOE]

    EM's mission is to safely and efficiently manage its spent nuclear fuel and prepare it for disposal in a geologic repository.

  13. Spent Nuclear Fuel project integrated safety management plan

    SciTech Connect (OSTI)

    Daschke, K.D.

    1996-09-17

    This document is being revised in its entirety and the document title is being revised to ``Spent Nuclear Fuel Project Integrated Safety Management Plan.

  14. Method and means of packaging nuclear fuel rods for handling

    DOE Patents [OSTI]

    Adam, Milton F.

    1979-01-01

    Nuclear fuel rods, especially spent nuclear fuel rods that may show physical distortion, are encased within a metallic enclosing structure by forming a tube about the fuel rod. The tube has previously been rolled to form an overlapping tubular structure and then unrolled and coiled about an axis perpendicular to the tube. The fuel rod is inserted into the tube as the rolled tube is removed from a coiled strip and allowed to reassume its tubular shape about the fuel rod. Rollers support the coiled strip in an open position as the coiled strip is uncoiled and allowed to roll about the fuel rod.

  15. Fundamental aspects of nuclear reactor fuel elements (Technical...

    Office of Scientific and Technical Information (OSTI)

    Citation Details In-Document Search Title: Fundamental aspects of nuclear reactor fuel ... text for first-year graduate courses in nuclear materials and as a reference for workers ...

  16. Control of SO{sub 2} and NOx emissions from fossil fuel-fired power plants: Research and practice of TPRI

    SciTech Connect (OSTI)

    Ming-Chuan Zhang

    1993-12-31

    The generation of electric power in China has been dominated by coal for many years. By the end of 1990, total installed generating capacity reached 135 GW, of which fossil fuel-fired plants accounted for 74 percent. The total electricity generated reached 615 TWh, with fossil fuels accounting for 80.5 percent. About 276 million tons of raw coal are consumed in these fossil fuel-burning units per year, accounting for about 25 percent of the total output of the country. According to the government, by the year 2000, the total installed capacity of Chinese power systems should be at least 240 GW, of which fossil fuels will account for about 77 percent. The coal required for power generation will increase to about 530 million tons per year, accounting for about 38 percent of the total coal output. So, it is obvious that coal consumed in coal-fired power plants occupies a very important place in the national fuel balance. The current environmental protection standards, which are based on ground-level concentrations of pollutants, do not effectively lead to the control of pollution emission concentrations or total SO{sub 2} emissions. Due to the practical limitations of the Chinese economy, there is a limited capability to introduce advanced sulfur emission control technologies. Thus, except for the two 360 MW units imported from Japan for the Luohuang Power Plant in Shichuan province, all the other fossil fuel-fired units have not yet adopted any kind of SO{sub 2} removal measures. The Luohuang units are equipped with Mitsubishi limestone flue gas desulfurization systems. Because of the lack of effective pollution control technologies, large areas of the country have been seriously polluted by SO{sub 2}, and some of them even by acid rain.

  17. A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu Former Secretary of Energy The Blue Ribbon Commission on America's Nuclear Future was formed at the direction of the President to conduct a comprehensive review of polices for managing the back end of the nuclear fuel cycle. If we are going to ensure that the United States remains at the forefront of nuclear

  18. Fossil Energy-Developed Fuel Cell Technology Being Adapted by Navy for Advanced Unmanned Undersea Vehicles

    Broader source: Energy.gov [DOE]

    Solid oxide fuel cell (SOFC) technology being developed by the U.S. Department of Energy (DOE) for coal-based central power generation is being adapted by the U.S. Office of Naval Research for use in advanced unmanned undersea vehicles (UUVs).

  19. Used Fuel Disposition Used Nuclear Fuel Storage and Transportation

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ASI Review Meeting September 17, 2014 Used Fuel Disposition Today's Discussion n Our ... - Transportation - Analysis Used Fuel Disposition 3 Overall Objectives * Develop ...

  20. Fossil fuel power plants: Computer systems for power plant control, maintenance, and operation. (Latest citations from the Compendex database). Published Search

    SciTech Connect (OSTI)

    Not Available

    1993-07-01

    The bibliography contains citations concerning fossil fuel power plant computer systems. Minicomputer and microcomputer systems used for monitoring, process control, performance calculations, alarming, and administrative applications are discussed. Topics emphasize power plant control, maintenance and operation. (Contains 250 citations and includes a subject term index and title list.)

  1. Crude Glycerol as Cost-Effective Fuel for Combined Heat and Power to Replace Fossil Fuels, Final Technical Report

    SciTech Connect (OSTI)

    Roberts, William L

    2012-10-31

    The primary objectives of this work can be summed into two major categories. Firstly, the fundamentals of the combustion of glycerol (in both a refined and unrefined form) were to be investigated, with emphasis of the development of a system capable of reliably and repeatedly combusting glycerol as well as an analysis of the emissions produced during glycerol combustion. Focus was placed on quantifying common emissions in comparison to more traditional fuels and this work showed that the burner developed was able to completely combust glycerol within a relatively wide range of operating conditions. Additionally, focus was placed on examining specific emissions in more detail, namely interesting NOx emissions observed in initial trials, acrolein and other volatile organic emissions, and particulate and ash emissions. This work showed that the combustion of crude glycerol could result in significantly reduced NOx emissions as a function of the high fuel bound oxygen content within the glycerol fuel. It also showed that when burned properly, the combustion of crude glycerol did not result in excessive emissions of acrolein or any other VOC compared to the combustion from more traditional fuels. Lastly however, this work has shown that in any practical application in which glycerol is being burned, it will be necessary to explore ash mitigation techniques due to the very high particulate matter concentrations produced during glycerol combustion. These emissions are comparable to unfiltered coal combustion and are directly tied to the biodiesel production method. The second focus of this work was directed to developing a commercialization strategy for the use of glycerol as a fuel replacement. This strategy has identified a 30 month plan for the scaling up of the laboratory scale burner into a pre-pilot scale system. Additionally, financing options were explored and an assessment was made of the economics of replacing a traditional fuel (namely natural gas) with crude glycerol from biodiesel production. This analysis showed that the cost of replacing natural gas with crude glycerol requires a strong function of the market price per unit of energy for the traditional fuel. However, the economics can be improved through the inclusion of a federal tax credit for the use of a renewable fuel. The conclusion of this analysis also shows that the ideal customer for energy replacement via crude glycerol is biodiesel producers who are located in remote regions, where the cost of energy is higher and the cost of crude glycerol is lowest. Lastly, the commercialization strategy analyzed competing technologies, namely traditional natural gas and electric heaters, as well as competing glycerol burners, and concludes with a discussion of the requirements for a pilot demonstration.

  2. A formalized approach to cycle chemistry improvement in fossil fuel power plants

    SciTech Connect (OSTI)

    Dimmer, J.P.; Dooley, R.B.

    1995-01-01

    The overall cost impact of cycle chemistry problems in fossil plants is typically hidden within the statistics of component forced outages, efficiency losses and premature end of useful component life. Corrosion of components in US utility steam generating plants is responsible for an estimated 50% of forced outages and over three billion dollars a year in additional operating and maintenance costs. These problems are usually the direct result of repeat incidents of impurity ingress, corrosion, and/or corrosion product generation transport, and deposition on heat transfer and power generation process equipment surfaces. The only way to prevent repeat incidents of cycle chemistry corrosion and/or deposition-influenced equipment problems is to implement a formalized cycle chemistry improvement program that addresses the root-causes of these problems. This paper describes such a program being implemented at twelve (12) utilities under EPRI research project RP2712-11, {open_quotes}Cycle Chemistry Improvement Program.{close_quotes} Interim utility results, after almost three years of project participation, have demonstrated substantial reductions in availability/performance losses and water treatment costs due to applications of state-of-the-art cycle chemistry, monitoring equipment and/or process control systems.

  3. Separator assembly for use in spent nuclear fuel shipping cask

    DOE Patents [OSTI]

    Bucholz, James A.

    1983-01-01

    A separator assembly for use in a spent nuclear fuel shipping cask has a honeycomb-type wall structure defining parallel cavities for holding nuclear fuel assemblies. Tubes formed of an effective neutron-absorbing material are embedded in the wall structure around each of the cavities and provide neutron flux traps when filled with water.

  4. Electric heater for nuclear fuel rod simulators

    DOE Patents [OSTI]

    McCulloch, Reginald W.; Morgan, Jr., Chester S.; Dial, Ralph E.

    1982-01-01

    The present invention is directed to an electric cartridge-type heater for use as a simulator for a nuclear fuel pin in reactor studies. The heater comprises an elongated cylindrical housing containing a longitudinally extending helically wound heating element with the heating element radially inwardly separated from the housing. Crushed cold-pressed preforms of boron nitride electrically insulate the heating element from the housing while providing good thermal conductivity. Crushed cold-pressed preforms of magnesia or a magnesia-15 percent boron nitride mixture are disposed in the cavity of the helical heating element. The coefficient of thermal expansion of the magnesia or the magnesia-boron nitride mixture is higher than that of the boron nitride disposed about the heating element for urging the boron nitride radially outwardly against the housing during elevated temperatures to assure adequate thermal contact between the housing and the boron nitride.

  5. Characterization plan for Hanford spent nuclear fuel

    SciTech Connect (OSTI)

    Abrefah, J.; Thornton, T.A.; Thomas, L.E.; Berting, F.M.; Marschman, S.C.

    1994-12-01

    Reprocessing of spent nuclear fuel (SNF) at the Hanford Site Plutonium-Uranium Extraction Plant (PUREX) was terminated in 1972. Since that time a significant quantity of N Reactor and Single-Pass Reactor SNF has been stored in the 100 Area K-East (KE) and K-West (KW) reactor basins. Approximately 80% of all US Department of Energy (DOE)-owned SNF resides at Hanford, the largest portion of which is in the water-filled KE and KW reactor basins. The basins were not designed for long-term storage of the SNF and it has become a priority to move the SNF to a more suitable location. As part of the project plan, SNF inventories will be chemically and physically characterized to provide information that will be used to resolve safety and technical issues for development of an environmentally benign and efficient extended interim storage and final disposition strategy for this defense production-reactor SNF.

  6. FUEL ELEMENT FOR A NUCLEAR REACTOR

    DOE Patents [OSTI]

    Duffy, J.G. Jr.

    1961-05-30

    A lattice type fissionable fuel structure for a nuclear reactor is described. The fissionable material is formed into a plurality of rod-llke bodies with each encased in a fluid-tight jacket. A plurality of spaced longitudinal fins are mounted on the exterior and extend radially from each jacket, with a portion of the fins extending radially beyond the remainder of the fins. A collar of short length for each body is mounted on the extended fins for spacing the bodies, and adjacent bodies abut each other through these collars. Should distortion of the bodies take place, coilapse of the outer fins is limited by the shorter flns, thereby insuring some coolant flow at all times. (AEC)

  7. Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development

    SciTech Connect (OSTI)

    Jon Carmack

    2014-01-01

    The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

  8. METHOD OF PREPARING A FUEL ELEMENT FOR A NUCLEAR REACTOR

    DOE Patents [OSTI]

    Roake, W.E.; Evans, E.A.; Brite, D.W.

    1960-06-21

    A method of preparing a fuel element for a nuclear reactor is given in which an internally and externally cooled fuel element consisting of two coaxial tubes having a plurality of integral radial ribs extending between the tubes and containing a powdered fuel material is isostatically pressed to form external coolant channels and compact the powder simultaneously.

  9. Coupon Surveillance For Corrosion Monitoring In Nuclear Fuel Basin

    SciTech Connect (OSTI)

    Mickalonis, J. I.; Murphy, T. R.; Deible, R.

    2012-10-01

    Aluminum and stainless steel coupons were put into a nuclear fuel basin to monitor the effect of water chemistry on the corrosion of fuel cladding. These coupons have been monitored for over ten years. The corrosion and pitting data is being used to model the kinetics and estimate the damage that is occurring to the fuel cladding.

  10. Spent nuclear fuel discharges from U.S. reactors 1994

    SciTech Connect (OSTI)

    1996-02-01

    Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US. This year`s report provides data on the current inventories and storage capacities at these reactors. Detailed statistics on the data are presented in four chapters that highlight 1994 spent fuel discharges, storage capacities and inventories, canister and nonfuel component data, and assembly characteristics. Five appendices, a glossary, and bibliography are also included. 10 figs., 34 tabs.

  11. Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear

    Office of Scientific and Technical Information (OSTI)

    Research Reactors (Technical Report) | SciTech Connect Technical Report: Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors Citation Details In-Document Search Title: Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors Turbulent flow coupled with heat transfer is investigated for a High Flux Isotope Reactor (HFIR) fuel plate. The Reynolds Averaged Navier-Stokes Models are used for fluid dynamics and the transfer of

  12. World nuclear capacity and fuel cycle requirements, November 1993

    SciTech Connect (OSTI)

    Not Available

    1993-11-30

    This analysis report presents the current status and projections of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. Long-term projections of US nuclear capacity, generation, fuel cycle requirements, and spent fuel discharges for three different scenarios through 2030 are provided in support of the Department of Energy`s activities pertaining to the Nuclear Waste Policy Act of 1982 (as amended in 1987). The projections of uranium requirements also support the Energy Information Administration`s annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment.

  13. Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

    SciTech Connect (OSTI)

    Dixon, B.W.; Piet, S.J.

    2004-10-03

    The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository. There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel management options in the context of a full range of possible nuclear energy futures. The analysis indicates the best option to implement varies depending on the nuclear energy future selected.

  14. A 48-month extended fuel cycle for the B and W mPower{sup TM} small modular nuclear reactor

    SciTech Connect (OSTI)

    Erighin, M. A. [Babcock and Wilcox Company, 109 Ramsey Place, Lynchburg, VA 24502 (United States)

    2012-07-01

    The B and W mPower{sup TM} reactor is a small, rail-shippable pressurized water reactor (PWR) with an integral once-through steam generator and an electric power output of 150 MW, which is intended to replace aging fossil power plants of similar output. The core is composed of 69 reduced-height, but otherwise standard, PWR assemblies with the familiar 17 x 17 fuel rod array on a 21.5 cm inter-assembly pitch. The B and W mPower core design and cycle management plan, which were performed using the Studsvik core design code suite, follow the pattern of a typical nuclear reactor fuel cycle design and analysis performed by most nuclear fuel management organizations, such as fuel vendors and utilities. However, B and W is offering a core loading and cycle management plan for four years of continuous power operations without refueling and without the hurdles of chemical shim. (authors)

  15. Benefits and concerns of a closed nuclear fuel cycle

    SciTech Connect (OSTI)

    Widder, Sarah H.

    2010-11-17

    Nuclear power can play an important role in our energy future, contributing to increasing electricity demand while at the same time decreasing carbon dioxide emissions. However, the nuclear fuel cycle in the United States today is unsustainable. As stated in the 1982 Nuclear Waste Policy Act, the U.S. Department of Energy is responsible for disposing of spent nuclear fuel generated by commercial nuclear power plants operating in a once-through fuel cycle in the deep geologic repository located at Yucca Mountain. However, unyielding political opposition to the site has hindered the commissioning process to the extant that the current administration has recently declared the unsuitability of the Yucca Mountain site. In light of this the DOE is exploring other options, including closing the fuel cycle through recycling and reprocessing of spent nuclear fuel. The possibility of closing the fuel cycle is receiving special attention because of its ability to minimize the final high level waste (HLW) package as well as recover additional energy value from the original fuel. The technology is, however, still very controversial because of the increased cost and proliferation risk it can present. To lend perspective on the closed fuel cycle alternative, this presents the arguments for and against closing the fuel cycle with respect to sustainability, proliferation risk, commercial viability, waste management, and energy security.

  16. Nuclear fuel cycle facility accident analysis handbook

    SciTech Connect (OSTI)

    1998-03-01

    The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

  17. Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay

    SciTech Connect (OSTI)

    Quiter, Brian; Ludewigt, Bernhard; Ambers, Scott

    2011-06-30

    In nuclear resonance fluorescence (NRF) measurements, resonances are excited by an external photon beam leading to the emission of gamma rays with specific energies that are characteristic of the emitting isotope. NRF promises the unique capability of directly quantifying a specific isotope without the need for unfolding the combined responses of several fissile isotopes as is required in other measurement techniques. We have analyzed the potential of NRF as a non-destructive analysis technique for quantitative measurements of Pu isotopes in spent nuclear fuel (SNF). Given the low concentrations of 239Pu in SNF and its small integrated NRF cross sections, the main challenge in achieving precise and accurate measurements lies in accruing sufficient counting statistics in a reasonable measurement time. Using analytical modeling, and simulations with the radiation transport code MCNPX that has been experimentally tested recently, the backscatter and transmission methods were quantitatively studied for differing photon sources and radiation detector types. Resonant photon count rates and measurement times were estimated for a range of photon source and detection parameters, which were used to determine photon source and gamma-ray detector requirements. The results indicate that systems based on a bremsstrahlung source and present detector technology are not practical for high-precision measurements of 239Pu in SNF. Measurements that achieve the desired uncertainties within hour-long measurements will either require stronger resonances, which may be expressed by other Pu isotopes, or require quasi-monoenergetic photon sources with intensities that are approximately two orders of magnitude higher than those currently being designed or proposed.This work is part of a larger effort sponsored by the Next Generation Safeguards Initiative to develop an integrated instrument, comprised of individual NDA techniques with complementary features, that is fully capable of determining Pu mass in spent fuel assemblies.

  18. Nuclear Regulatory Commission's Integrated Strategy for Spent Fuel

    Office of Environmental Management (EM)

    Management | Department of Energy Commission's Integrated Strategy for Spent Fuel Management Nuclear Regulatory Commission's Integrated Strategy for Spent Fuel Management * 20+ years of preparation for the licensing review * DOE application received in June 2008 and accepted for review in September 2008 * President Obama pursues alternatives to Yucca Mountain * DOE motion to withdraw in March 2010 * Blue Ribbon Commission on America's Nuclear Future PDF icon Nuclear Regulatory Commission's

  19. Fuel rod retention device for a nuclear reactor

    DOE Patents [OSTI]

    Hylton, Charles L. (Madison Heights, VA)

    1984-01-01

    A device is described for supporting a nuclear fuel rod in a fuel rod assembly which allows the rod to be removed without disturbing other rods in the assembly. A fuel rod cap connects the rod to a bolt which is supported in the assembly end fitting by means of a locking assembly. The device is designed so that the bolt is held securely during normal reactor operation yet may be easily disengaged and the fuel rod removed when desired.

  20. An Internet-based interactive module for air emissions from fossil fuel based power generation

    SciTech Connect (OSTI)

    Karman, D.; O`Leary, K.; O`Reilly, S.

    1997-12-31

    The proliferation of the Internet, Web pages and associated software tools available for developing multimedia material provides significant opportunities in training, education and information transfer. This paper will describe the development, testing and evaluation of an interactive teaching module aimed at college and university students that have previous education in thermodynamics and basic chemistry. The module is currently in development at the Department of Civil and Environmental Engineering at Carleton University with support from Environment Canada. Preliminary testing of this module is expected to begin late January. The module contains options to look at CO, CO{sub 2}, SO{sub 2} and NO{sub x} emissions associated with electric power generation in thermal stations that use coal, natural gas, crude and distillate oil. Factors governing the thermal efficiency of typical boiler systems and the thermodynamic limitations for converting heat into work are discussed. Supporting background information such as emission trends and emission factors used in calculations are also included as part of this module. A simple Rankine cycle without reheat or regeneration is considered to compare the emissions per unit energy delivered from each of the fuels considered. For natural gas and distillate oil, combined cycle operation is considered with a gas turbine-heat recovery steam generator combination replacing the boiler in the simple Rankine cycle. For all fuels, the cogeneration option is investigated by expanding the steam to an intermediate pressure in the turbine and utilizing the remaining heat by condensing the steam in a heat recovery application. Emission factors and basic information on CO, SO{sub 2} and NO{sub x} control technologies are utilized to calculate and report the emissions per unit energy delivered under the various scenarios investigated.

  1. TASK 3.4--IMPACTS OF COFIRING BIOMASS WITH FOSSIL FUELS

    SciTech Connect (OSTI)

    Christopher J. Zygarlicke; Donald P. McCollor; Kurt E. Eylands; Melanie D. Hetland; Mark A. Musich; Charlene R. Crocker; Jonas Dahl; Stacie Laducer

    2001-08-01

    With a major worldwide effort now ongoing to reduce greenhouse gas emissions, cofiring of renewable biomass fuels at conventional coal-fired utilities is seen as one of the lower-cost options to achieve such reductions. The Energy & Environmental Research Center has undertaken a fundamental study to address the viability of cofiring biomass with coal in a pulverized coal (pc)-fired boiler for power production. Wheat straw, alfalfa stems, and hybrid poplar were selected as candidate biomass materials for blending at a 20 wt% level with an Illinois bituminous coal and an Absaloka subbituminous coal. The biomass materials were found to be easily processed by shredding and pulverizing to a size suitable for cofiring with pc in a bench-scale downfired furnace. A literature investigation was undertaken on mineral uptake and storage by plants considered for biomass cofiring in order to understand the modes of occurrence of inorganic elements in plant matter. Sixteen essential elements, C, H, O, N, P, K, Ca, Mg, S, Zn, Cu, Fe, Mn, B, Mo, and Cl, are found throughout plants. The predominant inorganic elements are K and Ca, which are essential to the function of all plant cells and will, therefore, be evenly distributed throughout the nonreproductive, aerial portions of herbaceous biomass. Some inorganic constituents, e.g., N, P, Ca, and Cl, are organically associated and incorporated into the structure of the plant. Cell vacuoles are the repository for excess ions in the plant. Minerals deposited in these ubiquitous organelles are expected to be most easily leached from dry material. Other elements may not have specific functions within the plant, but are nevertheless absorbed and fill a need, such as silica. Other elements, such as Na, are nonessential, but are deposited throughout the plant. Their concentration will depend entirely on extrinsic factors regulating their availability in the soil solution, i.e., moisture and soil content. Similarly, Cl content is determined less by the needs of the plant than by the availability in the soil solution; in addition to occurring naturally, Cl is present in excess as the anion complement in K fertilizer applications. An analysis was performed on existing data for switchgrass samples from ten different farms in the south-central portion of Iowa, with the goal of determining correlations between switchgrass elemental composition and geographical and seasonal changes so as to identify factors that influence the elemental composition of biomass. The most important factors in determining levels of various chemical compounds were found to be seasonal and geographical differences related to soil conditions. Combustion testing was performed to obtain deposits typical of boiler fouling and slagging conditions as well as fly ash. Analysis methods using computer-controlled scanning electron microscopy and chemical fractionation were applied to determine the composition and association of inorganic materials in the biomass samples. Modified sample preparation techniques and mineral quantification procedures using cluster analysis were developed to characterize the inorganic material in these samples. Each of the biomass types exhibited different inorganic associations in the fuel as well as in the deposits and fly ash. Morphological analyses of the wheat straw show elongated 10-30-{micro}m amorphous silica particles or phytoliths in the wheat straw structure. Alkali such as potassium, calcium, and sodium is organically bound and dispersed in the organic structure of the biomass materials. Combustion test results showed that the blends fed quite evenly, with good burnout. Significant slag deposit formation was observed for the 100% wheat straw, compared to bituminous and subbituminous coals burned under similar conditions. Although growing rapidly, the fouling deposits of the biomass and coal-biomass blends were significantly weaker than those of the coals. Fouling was only slightly worse for the 100% wheat straw fuel compared to the coals. The wheat straw ash was found to show the greatest similarity from the fuel to the ash analyzed. A high percentage of particles from both fuel and ash samples contained both Si and K. While Cl was a significant component in the fuel, very little was detected in the ash sample.

  2. Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy...

    Office of Scientific and Technical Information (OSTI)

    Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding Citation Details In-Document Search Title: Improving Accident Tolerance of Nuclear Fuel with Coated ...

  3. Carbon Capture and Water Emissions Treatment System (CCWESTRS) at Fossil-Fueled Electric Generating Plants

    SciTech Connect (OSTI)

    P. Alan Mays; Bert R. Bock; Gregory A. Brodie; L. Suzanne Fisher; J. Devereux Joslin; Donald L. Kachelman; Jimmy J. Maddox; N. S. Nicholas; Larry E. Shelton; Nick Taylor; Mark H. Wolfe; Dennis H. Yankee; John Goodrich-Mahoney

    2005-08-30

    The Tennessee Valley Authority (TVA), the Electric Power Research Institute (EPRI), and the Department of Energy-National Energy Technologies Laboratory (DOE-NETL) are evaluating and demonstrating integration of terrestrial carbon sequestration techniques at a coal-fired electric power plant through the use of Flue Gas Desulfurization (FGD) system gypsum as a soil amendment and mulch, and coal fly ash pond process water for periodic irrigation. From January to March 2002, the Project Team initiated the construction of a 40 ha Carbon Capture and Water Emissions Treatment System (CCWESTRS) near TVA's Paradise Fossil Plant on marginally reclaimed surface coal mine lands in Kentucky. The CCWESTRS is growing commercial grade trees and cover crops and is expected to sequester 1.5-2.0 MT/ha carbon per year over a 20-year period. The concept could be used to meet a portion of the timber industry's needs while simultaneously sequestering carbon in lands which would otherwise remain non-productive. The CCWESTRS includes a constructed wetland to enhance the ability to sequester carbon and to remove any nutrients and metals present in the coal fly ash process water runoff. The CCWESTRS project is a cooperative effort between TVA, EPRI, and DOE-NETL, with a total budget of $1,574,000. The proposed demonstration project began in October 2000 and has continued through December 2005. Additional funding is being sought in order to extend the project. The primary goal of the project is to determine if integrating power plant processes with carbon sequestration techniques will enhance carbon sequestration cost-effectively. This goal is consistent with DOE objectives to provide economically competitive and environmentally safe options to offset projected growth in U.S. baseline emissions of greenhouse gases after 2010, achieve the long-term goal of $10/ton of avoided net costs for carbon sequestration, and provide half of the required reductions in global greenhouse gases by 2025. Other potential benefits of the demonstration include developing a passive technology for water treatment for trace metal and nutrient release reductions, using power plant by-products to improve coal mine land reclamation and carbon sequestration, developing wildlife habitat and green-space around production facilities, generating Total Maximum Daily Load (TMDL) credits for the use of process water, and producing wood products for use by the lumber and pulp and paper industry. Project activities conducted during the five year project period include: Assessing tree cultivation and other techniques used to sequester carbon; Project site assessment; Greenhouse studies to determine optimum plant species and by-product application; Designing, constructing, operating, monitoring, and evaluating the CCWESTRS system; and Reporting (ongoing). The ability of the system to sequester carbon will be the primary measure of effectiveness, measured by accessing survival and growth response of plants within the CCWESTRS. In addition, costs associated with design, construction, and monitoring will be evaluated and compared to projected benefits of other carbon sequestration technologies. The test plan involves the application of three levels each of two types of power plant by-products--three levels of FGD gypsum mulch, and three levels of ash pond irrigation water. This design produces nine treatment levels which are being tested with two species of hardwood trees (sweet gum and sycamore). The project is examining the effectiveness of applications of 0, 8-cm, and 15-cm thick gypsum mulch layers and 0, 13 cm, and 25 cm of coal fly ash water for irrigation. Each treatment combination is being replicated three times, resulting in a total of 54 treatment plots (3 FGD gypsum levels X 3 irrigation water levels x 2 tree species x 3 replicates). Survival and growth response of plant species in terms of sequestering carbon in plant material and soil will be the primary measure of effectiveness of each treatment. Additionally, the ability of the site soils and unsaturated zone subsurface m

  4. Spent nuclear fuel discharges from US reactors 1993

    SciTech Connect (OSTI)

    Not Available

    1995-02-01

    The Energy Information Administration (EIA) of the U.S. Department of Energy (DOE) administers the Nuclear Fuel Data Survey, Form RW-859. This form is used to collect data on fuel assemblies irradiated at commercial nuclear reactors operating in the United States, and the current inventories and storage capacities of those reactors. These data are important to the design and operation of the equipment and facilities that DOE will use for the future acceptance, transportation, and disposal of spent fuels. The data collected and presented identifies trends in burnup, enrichment, and spent nuclear fuel discharged form commercial light-water reactor as of December 31, 1993. The document covers not only spent nuclear fuel discharges; but also site capacities and inventories; canisters and nonfuel components; and assembly type characteristics.

  5. Methods for making a porous nuclear fuel element

    DOE Patents [OSTI]

    Youchison, Dennis L; Williams, Brian E; Benander, Robert E

    2014-12-30

    Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

  6. Thermoacoustic sensor for nuclear fuel temperaturemonitoring and heat transfer enhancement

    SciTech Connect (OSTI)

    James A. Smith; Dale K. Kotter; Randall A. Alli; Steven L. Garrett

    2013-05-01

    A new acoustical sensing system for the nuclear power industry has been developed at The Pennsylvania State University in collaboration with Idaho National Laboratories. This sensor uses the high temperatures of nuclear fuel to convert a nuclear fuel rod into a standing-wave thermoacoustic engine. When a standing wave is generated, the sound wave within the fuel rod will be propagated, by acoustic radiation, through the cooling fluid within the reactor or spent fuel pool and can be monitored a remote location external to the reactor. The frequency of the sound can be correlated to an effective temperature of either the fuel or the surrounding coolant. We will present results for a thermoacoustic resonator built into a Nitonic-60 (stainless steel) fuel rod that requires only one passive component and no heat exchangers.

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

    SciTech Connect (OSTI)

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

    2013-09-30

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

  8. Fossil fuel and hydrocarbon conversion using hydrogen-rich plasmas. Topical report February 1994--February 1995

    SciTech Connect (OSTI)

    1995-02-01

    Experiments were made on use of H and CH plasmas for converting waste materials and heavy oils to H-rich transportation fuels. Batch and continuous experiments were conducted with an industrial microwave generator and a commercial microwave oven. A continuously circulating reactor was constructed for conducting experiments on flowing oils. Experiments on decomposition of scrap tires showed that microwave plasmas can be used to decompose scrap tires into potentially useful liquid products. In a batch experiment using a commercial microwave oven, about 20% of the tire was converted to liquid products in about 9 minutes. Methane was decomposed in a microwave plasma to yield a liquid products composed of various compound types; GC/MS analyses identified unsaturated compounds including benzene, toluene, ethyl benzene, methyl and ethyl naphthalene, small amounts of larger aromatic rings, and olefinic compounds. Experiments on a crude oil in a continuously flowing reactor showed that distillate materials are produced using H and CH plasmas. Also, the recycle oils had an overall carbon aromaticity lower than that of starting feed material, indicating that some hydrogenation and methanation had taken place in the recycle oils.

  9. ABB`s investigations into air toxic emissions from fossil fuel and MSW combustion

    SciTech Connect (OSTI)

    Wesnor, J.D.

    1994-12-31

    Since passage of the Clean Air Act, Asea Brown Boveri (ABB) has been actively developing a knowledge base on the Title 3 hazardous air pollutants, more commonly called air toxics. As ABB is a multinational company, US operating companies are able to call upon work performed by European counterparts, who have faced similar legislation several years ago. In addition to the design experience and database acquired in Europe, ABB Inc. has been pursuing several other avenues to expand its air toxics knowledge. ABB Combustion Engineering (ABB CE) is presently studying the formation of organic pollutants within the combustion furnace and partitioning of trace metals among the furnace outlet streams. ABB Environmental Systems (ABBES) has reviewed available and near-term control technologies and methods. Also, both ABB CE and ABBES have conducted source sampling and analysis at commercial installations for hazardous air pollutants to determine the emission rates and removal performance of various types of equipment. Several different plants hosted these activities, allowing for variation in fuel type and composition, boiler configuration, and air pollution control equipment. This paper discusses the results of these investigations.

  10. China: Emissions pattern of the world leader in CO2 emissions from fossil fuel consumption and cement production

    SciTech Connect (OSTI)

    Gregg, J; Andres, Robert Joseph; Marland, Gregg

    2008-01-01

    Release of carbon dioxide (CO2) from fossil fuel combustion and cement manufacture is the primary anthropogenic driver of climate change. Our best estimate is that China became the largest national source of CO2 emissions during 2006. Previously, the United States (US) had occupied that position. However, the annual emission rate in the US has remained relatively stable between 2001-2006 while the emission rate in China has more than doubled, apparently eclipsing that of the US in late 2006. Here we present the seasonal and spatial pattern of CO2 emissions in China, as well as the sectoral breakdown of emissions. Though our best point estimate places China in the lead position in terms of CO2 emissions, we qualify this statement in a discussion of the uncertainty in the underlying data (3-5% for the US; 15-20% for China). Finally, we comment briefly on the implications of China's new position with respect to international agreements to mitigate climate change.

  11. Technical Potential of Solar Water Heating to Reduce Fossil Fuel Use and Greenhouse Gas Emissions in the United States

    SciTech Connect (OSTI)

    Denholm, P.

    2007-03-01

    Use of solar water heating (SWH) in the United States grew significantly in the late 1970s and early 1980s, as a result of increasing energy prices and generous tax credits. Since 1985, however, expiration of federal tax credits and decreased energy prices have virtually eliminated the U.S. market for SWH. More recently, increases in energy prices, concerns regarding emissions of greenhouse gases, and improvements in SWH systems have created new interest in the potential of this technology. SWH, which uses the sun to heat water directly or via a heat-transfer fluid in a collector, may be particularly important in its ability to reduce natural gas use. Dependence on natural gas as an energy resource in the United States has significantly increased in the past decade, along with increased prices, price volatility, and concerns about sustainability and security of supply. One of the readily deployable technologies available to decrease use of natural gas is solar water heating. This report provides an overview of the technical potential of solar water heating to reduce fossil fuel consumption and associated greenhouse gas emissions in U.S. residential and commercial buildings.

  12. What to Expect When Readying to Move Spent Nuclear Fuel from...

    Energy Savers [EERE]

    What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power Plants What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power ...

  13. AN ANALYTICAL FRAMEWORK FOR ASSESSING RELIABLE NUCLEAR FUEL SERVICE APPROACHES: ECONOMIC AND NON-PROLIFERATION MERITS OF NUCLEAR FUEL LEASING

    SciTech Connect (OSTI)

    Kreyling, Sean J.; Brothers, Alan J.; Short, Steven M.; Phillips, Jon R.; Weimar, Mark R.

    2010-08-11

    The goal of international nuclear policy since the dawn of nuclear power has been the peaceful expansion of nuclear energy while controlling the spread of enrichment and reprocessing technology. Numerous initiatives undertaken in the intervening decades to develop international agreements on providing nuclear fuel supply assurances, or reliable nuclear fuel services (RNFS) attempted to control the spread of sensitive nuclear materials and technology. In order to inform the international debate and the development of government policy, PNNL has been developing an analytical framework to holistically evaluate the economics and non-proliferation merits of alternative approaches to managing the nuclear fuel cycle (i.e., cradle-to-grave). This paper provides an overview of the analytical framework and discusses preliminary results of an economic assessment of one RNFS approach: full-service nuclear fuel leasing. The specific focus of this paper is the metrics under development to systematically evaluate the non-proliferation merits of fuel-cycle management alternatives. Also discussed is the utility of an integrated assessment of the economics and non-proliferation merits of nuclear fuel leasing.

  14. Laser-Based Characterization of Nuclear Fuel Plates

    SciTech Connect (OSTI)

    James A. Smith; David L. Cottle; Barry H. Rabin

    2013-07-01

    Ensuring the integrity of fuel-clad and clad-clad bonding in nuclear fuels is important for safe reactor operation and assessment of fuel performance, yet the measurement of bond strengths in actual fuels has proved challenging. The laser shockwave technique (LST) originally developed to characterize structural adhesion in composites is being employed to characterize interface strength in a new type of plate fuel being developed at Idaho National Laboratory (INL). LST is a non-contact method that uses lasers for the generation and detection of large-amplitude acoustic waves and is well suited for application to both fresh and irradiated nuclear-fuel plates. This paper will report on initial characterization results obtained from fresh fuel plates manufactured by different processes, including hot isostatic pressing, friction stir welding, and hot rolling.

  15. Nuclear fuel alloys or mixtures and method of making thereof

    DOE Patents [OSTI]

    Mariani, Robert Dominick; Porter, Douglas Lloyd

    2016-04-05

    Nuclear fuel alloys or mixtures and methods of making nuclear fuel mixtures are provided. Pseudo-binary actinide-M fuel mixtures form alloys and exhibit: body-centered cubic solid phases at low temperatures; high solidus temperatures; and/or minimal or no reaction or inter-diffusion with steel and other cladding materials. Methods described herein through metallurgical and thermodynamics advancements guide the selection of amounts of fuel mixture components by use of phase diagrams. Weight percentages for components of a metallic additive to an actinide fuel are selected in a solid phase region of an isothermal phase diagram taken at a temperature below an upper temperature limit for the resulting fuel mixture in reactor use. Fuel mixtures include uranium-molybdenum-tungsten, uranium-molybdenum-tantalum, molybdenum-titanium-zirconium, and uranium-molybdenum-titanium systems.

  16. Pyroprocessing of fast flux test facility nuclear fuel

    SciTech Connect (OSTI)

    Westphal, B.R.; Wurth, L.A.; Fredrickson, G.L.; Galbreth, G.G.; Vaden, D.; Elliott, M.D.; Price, J.C.; Honeyfield, E.M.; Patterson, M.N.

    2013-07-01

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electro-refined uranium products exceeded 99%. (authors)

  17. Pyroprocessing of Fast Flux Test Facility Nuclear Fuel

    SciTech Connect (OSTI)

    B.R. Westphal; G.L. Fredrickson; G.G. Galbreth; D. Vaden; M.D. Elliott; J.C. Price; E.M. Honeyfield; M.N. Patterson; L. A. Wurth

    2013-10-01

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.

  18. Krakow clean fossil fuels and energy efficiency program. Phase 1 report

    SciTech Connect (OSTI)

    Butcher, T.; Pierce, B.

    1995-06-01

    Krakow is one of the largest and oldest cities in Poland. It is situated in the south of the country on the banks of the Vistula River. From the 11th until the 17th centuries, it was the capital of Poland. Today, Krakow is a city of 750,000 residents, one of the largest centers of higher education, an important industrial center, and is of particular importance because of the number and kinds of historic buildings and sites. For this reason, Krakow was included by the UNESCO in the list of the world`s cultural heritages. For about three decades, significant air pollution has been one of Krakow`s most serious problems. Because the city is situated in the Vistula River valley, it is poorly ventilated and experiences a high concentration of air pollutants. The quality of air in Krakow is affected mainly by industry (Sendzimir Steelworks, energy industry, chemical plants), influx from the Silesian industrial region (power plants, metallurgy), transboundary pollution (Ostrava - Czech Republic), and local sources of low pollution, i.e. more than 1,000 boiler houses using solid fuels and more than 100,000 coal-fired home stoves. These local sources, with low stacks and almost no pollution-control equipment, are responsible for about 35-40% of the air pollution. This report presents phase I results of a program to reduce pollution in krakow. Phase I was to gather information on emissions and costs, and to verify assumptions on existing heating methods and alternatives.

  19. Method of increasing the deterrent to proliferation of nuclear fuels

    DOE Patents [OSTI]

    Rampolla, Donald S.

    1982-01-01

    A process of recycling protactinium-231 to enhance the utilization of radioactively hot uranium-232 in nuclear fuel for the purpose of making both fresh and spent fuel more resistant to proliferation. The uranium-232 may be obtained by the irradiation of protactinium-231 which is normally found in the spent fuel rods of a thorium base nuclear reactor. The production of protactinium-231 and uranium-232 would be made possible by the use of the thorium uranium-233 fuel cycle in power reactors.

  20. A nuclear wind/solar oil-shale system for variable electricity and liquid fuels production

    SciTech Connect (OSTI)

    Forsberg, C.

    2012-07-01

    The recoverable reserves of oil shale in the United States exceed the total quantity of oil produced to date worldwide. Oil shale contains no oil, rather it contains kerogen which when heated decomposes into oil, gases, and a carbon char. The energy required to heat the kerogen-containing rock to produce the oil is about a quarter of the energy value of the recovered products. If fossil fuels are burned to supply this energy, the greenhouse gas releases are large relative to producing gasoline and diesel from crude oil. The oil shale can be heated underground with steam from nuclear reactors leaving the carbon char underground - a form of carbon sequestration. Because the thermal conductivity of the oil shale is low, the heating process takes months to years. This process characteristic in a system where the reactor dominates the capital costs creates the option to operate the nuclear reactor at base load while providing variable electricity to meet peak electricity demand and heat for the shale oil at times of low electricity demand. This, in turn, may enable the large scale use of renewables such as wind and solar for electricity production because the base-load nuclear plants can provide lower-cost variable backup electricity. Nuclear shale oil may reduce the greenhouse gas releases from using gasoline and diesel in half relative to gasoline and diesel produced from conventional oil. The variable electricity replaces electricity that would have been produced by fossil plants. The carbon credits from replacing fossil fuels for variable electricity production, if assigned to shale oil production, results in a carbon footprint from burning gasoline or diesel from shale oil that may half that of conventional crude oil. The U.S. imports about 10 million barrels of oil per day at a cost of a billion dollars per day. It would require about 200 GW of high-temperature nuclear heat to recover this quantity of shale oil - about two-thirds the thermal output of existing nuclear reactors in the United States. With the added variable electricity production to enable renewables, additional nuclear capacity would be required. (authors)

  1. A Comparison Study of Various Nuclear Fuel Cycle Alternatives

    SciTech Connect (OSTI)

    Kwon, Eun-ha; Ko, Won-il

    2007-07-01

    As a nation develops its nuclear strategies, it must consider various aspects of nuclear energy such as sustainability, environmental-friendliness, proliferation-resistance, economics, technologies, and so on. Like all the policy decision, however, a nuclear fuel cycle option can not be superior in all aspects; the nation must identify its top priority and accordingly evaluate all the possible nuclear fuel cycle options. For such a purpose, this paper takes four different fuel cycle options that are likely adopted by the Korean government, considering the current status of nuclear power generation and the 3. Comprehensive Nuclear Energy Promotion Plan (CNEPP) - Once-through Cycle, DUPIC Recycle, Thermal Recycle and GEN-IV Recycle. The paper then evaluates each option in terms of resource utilization and waste generation. The analysis shows that the GEN-IV Recycle appears to be most competitive from these aspects. (authors)

  2. A Practical Approach to a Closed Nuclear Fuel Cycle and Sustained Nuclear

    Office of Scientific and Technical Information (OSTI)

    Energy (Conference) | SciTech Connect Conference: A Practical Approach to a Closed Nuclear Fuel Cycle and Sustained Nuclear Energy Citation Details In-Document Search Title: A Practical Approach to a Closed Nuclear Fuel Cycle and Sustained Nuclear Energy No abstract prepared. Authors: Collins, Emory D [1] ; Del Cul, Guillermo [1] ; Spencer, Barry B [1] ; Williams, Kent Alan [1] + Show Author Affiliations ORNL Publication Date: 2012-01-01 OSTI Identifier: 1042871 DOE Contract Number:

  3. Fabrication of high exposure nuclear fuel pellets

    DOE Patents [OSTI]

    Frederickson, James R.

    1987-01-01

    A method is disclosed for making a fuel pellet for a nuclear reactor. A mixture is prepared of PuO.sub.2 and UO.sub.2 powders, where the mixture contains at least about 30% PuO.sub.2, and where at least about 12% of the Pu is the Pu.sup.240 isotope. To this mixture is added about 0.3 to about 5% of a binder having a melting point of at least about 250.degree. F. The mixture is pressed to form a slug and the slug is granulated. Up to about 4.7% of a lubricant having a melting point of at least about 330.degree. F. is added to the granulated slug. Both the binder and the lubricant are selected from a group consisting of polyvinyl carboxylate, polyvinyl alcohol, naturally occurring high molecular weight cellulosic polymers, chemically modified high molecular weight cellulosic polymers, and mixtures thereof. The mixture is pressed to form a pellet and the pellet is sintered.

  4. Disposition of ORNL's Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Turner, D. W.; DeMonia, B. C.; Horton, L. L.

    2002-02-26

    This paper describes the process of retrieving, repackaging, and preparing Oak Ridge spent nuclear fuel (SNF) for off-site disposition. The objective of the Oak Ridge SNF Project is to safely, reliably, and efficiently manage SNF that is stored on the Oak Ridge Reservation until it can be shipped off-site. The project required development of several unique processes and the design and fabrication of special equipment to enable the successful retrieval, transfer, and repackaging of Oak Ridge SNF. SNF was retrieved and transferred to a hot cell for repackaging. After retrieval of SNF packages, the storage positions were decontaminated and stainless steel liners were installed to resolve the vulnerability of water infiltration. Each repackaged SNF canister has been transferred from the hot cell back to dry storage until off-site shipments can be made. Three shipments of aluminum-clad SNF were made to the Savannah River Site (SRS), and five shipments of non-aluminum-clad SNF are planned to the Idaho National Engineering and Environmental Laboratory (INEEL). Through the integrated cooperation of several organizations including the U.S. Department of Energy (DOE), Bechtel Jacobs Company LLC (BJC), Oak Ridge National Laboratory (ORNL), and various subcontractors, preparations for the disposition of SNF in Oak Ridge have been performed in a safe and successful manner.

  5. 105 K East and 105 K West fuel transfer bay crane use strategy for spent nuclear fuel path-forward

    SciTech Connect (OSTI)

    Ard, K.E.

    1996-04-02

    The purpose of this document is to outline the K Basins 30 ton crane qualification strategy for use in the Spent Nuclear Fuel Project fuel relocation campaign.

  6. Estimates of global, regional, and national annual CO{sub 2} emissions from fossil-fuel burning, hydraulic cement production, and gas flaring: 1950--1992

    SciTech Connect (OSTI)

    Boden, T.A.; Marland, G.; Andres, R.J.

    1995-12-01

    This document describes the compilation, content, and format of the most comprehensive C0{sub 2}-emissions database currently available. The database includes global, regional, and national annual estimates of C0{sub 2} emissions resulting from fossil-fuel burning, cement manufacturing, and gas flaring in oil fields for 1950--92 as well as the energy production, consumption, and trade data used for these estimates. The methods of Marland and Rotty (1983) are used to calculate these emission estimates. For the first time, the methods and data used to calculate CO, emissions from gas flaring are presented. This C0{sub 2}-emissions database is useful for carbon-cycle research, provides estimates of the rate at which fossil-fuel combustion has released C0{sub 2} to the atmosphere, and offers baseline estimates for those countries compiling 1990 C0{sub 2}-emissions inventories.

  7. Improved nuclear fuel assembly grid spacer

    DOE Patents [OSTI]

    Marshall, John; Kaplan, Samuel

    1977-01-01

    An improved fuel assembly grid spacer and method of retaining the basic fuel rod support elements in position within the fuel assembly containment channel. The improvement involves attachment of the grids to the hexagonal channel and of forming the basic fuel rod support element into a grid structure, which provides a design which is insensitive to potential channel distortion (ballooning) at high fluence levels. In addition the improved method eliminates problems associated with component fabrication and assembly.

  8. Energy Return on Investment from Recycling Nuclear Fuel

    SciTech Connect (OSTI)

    2011-08-17

    This report presents an evaluation of the Energy Return on Investment (EROI) from recycling an initial batch of 800 t/y of used nuclear fuel (UNF) through a Recycle Center under a number of different fuel cycle scenarios. The study assumed that apart from the original 800 t of UNF only depleted uranium was available as a feed. Therefore for each subsequent scenario only fuel that was derived from the previous fuel cycle scenario was considered. The scenarios represent a good cross section of the options available and the results contained in this paper and associated appendices will allow for other fuel cycle options to be considered.

  9. A review of nuclear fuel cycle options for developing nations

    SciTech Connect (OSTI)

    Harrison, R.K.; Scopatz, A.M.; Ernesti, M.

    2007-07-01

    A study of several nuclear reactor and fuel cycle options for developing nations was performed. All reactor choices were considered under a GNEP framework. Two advanced alternative reactor types, a nuclear battery-type reactor and a fuel reprocessing fast reactor were examined and compared with a conventional Generation III+ LWR reactor. The burn of nuclear fuel was simulated using ORIGEN 2.2 for each reactor type and the resulting information was used to compare the options in terms of waste produced, waste quality and repository impact. The ORIGEN data was also used to evaluate the economics of the fuel cycles using unit costs, discount rates and present value functions with the material balances. The comparison of the fuel cycles and reactors developed in this work provides a basis for the evaluation of subsidy programs and cost-benefit comparisons for various reactor parameters such as repository impact and proliferation risk versus economic considerations. (authors)

  10. Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Craft, Aaron E.; Wachs, Daniel M.; Okuniewski, Maria A.; Chichester, David L.; Williams, Walter J.; Papaioannou, Glen C.; Smolinski, Andrew T.

    2015-09-10

    Neutron radiography of irradiated nuclear fuel provides more comprehensive information about the internal condition of irradiated nuclear fuel than any other non-destructive technique to date. Idaho National Laboratory (INL) has multiple nuclear fuels research and development programs that routinely evaluate irradiated fuels using neutron radiography. The Neutron Radiography reactor (NRAD) sits beneath a shielded hot cell facility where neutron radiography and other evaluation techniques are performed on these highly radioactive objects. The NRAD currently uses the foil-film transfer technique for imaging fuel that is time consuming but provides high spatial resolution. This study describes the NRAD and hot cell facilities,more » the current neutron radiography capabilities available at INL, planned upgrades to the neutron imaging systems, and new facilities being brought online at INL related to neutron imaging.« less

  11. Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory

    SciTech Connect (OSTI)

    Craft, Aaron E.; Wachs, Daniel M.; Okuniewski, Maria A.; Chichester, David L.; Williams, Walter J.; Papaioannou, Glen C.; Smolinski, Andrew T.

    2015-09-10

    Neutron radiography of irradiated nuclear fuel provides more comprehensive information about the internal condition of irradiated nuclear fuel than any other non-destructive technique to date. Idaho National Laboratory (INL) has multiple nuclear fuels research and development programs that routinely evaluate irradiated fuels using neutron radiography. The Neutron Radiography reactor (NRAD) sits beneath a shielded hot cell facility where neutron radiography and other evaluation techniques are performed on these highly radioactive objects. The NRAD currently uses the foil-film transfer technique for imaging fuel that is time consuming but provides high spatial resolution. This study describes the NRAD and hot cell facilities, the current neutron radiography capabilities available at INL, planned upgrades to the neutron imaging systems, and new facilities being brought online at INL related to neutron imaging.

  12. Nuclear reactor fuel element having improved heat transfer

    DOE Patents [OSTI]

    Garnier, J.E.; Begej, S.; Williford, R.E.; Christensen, J.A.

    1982-03-03

    A nuclear reactor fuel element having improved heat transfer between fuel material and cladding is described. The element consists of an outer cladding tube divided into an upper fuel section containing a central core of fissionable or mixed fissionable and fertile fuel material, slightly smaller in diameter than the inner surface of the cladding tube and a small lower accumulator section, the cladding tube being which is filled with a low molecular weight gas to transfer heat from fuel material to cladding during irradiation. A plurality of essentially vertical grooves in the fuel section extend downward and communicate with the accumulator section. The radial depth of the grooves is sufficient to provide a thermal gradient between the hot fuel surface and the relatively cooler cladding surface to allow thermal segregation to take place between the low molecular weight heat transfer gas and high molecular weight fission product gases produced by the fuel material during irradiation.

  13. EA-1977: Acceptance and Disposition of Spent Nuclear Fuel Containing...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany EA-1977: Acceptance and Disposition of Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched ...

  14. Discovery sheds light on nuclear reactor fuel behavior during...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Discovery sheds light on nuclear reactor fuel behavior during a severe event By Angela Hardin * November 20, 2014 Tweet EmailPrint A new discovery about the atomic structure of...

  15. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER FINAL RECHNICAL REPORT FOR THE PERIOD AUGUST 1, 1999 THROUGH SEPTEMBER 30, 2002 REV. 1

    SciTech Connect (OSTI)

    BROWN,LC; BESENBRUCH,GE; LENTSCH, RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

    2003-12-01

    OAK-B135 Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy [1-1,1-2]. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties [1-3,1-4]. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.''

  16. Coolant mass flow equalizer for nuclear fuel

    DOE Patents [OSTI]

    Betten, Paul R. (Windsor, CT)

    1978-01-01

    The coolant mass flow distribution in a liquid metal cooled reactor is enhanced by restricting flow in sub-channels defined in part by the peripheral fuel elements of a fuel assembly. This flow restriction, which results in more coolant flow in interior sub-channels, is achieved through the use of a corrugated liner positioned between the bundle of fuel elements and the inner wall of the fuel assembly coolant duct. The corrugated liner is expandable to accommodate irradiation induced growth of fuel assembly components.

  17. Means for supporting fuel elements in a nuclear reactor

    DOE Patents [OSTI]

    Andrews, Harry N.; Keller, Herbert W.

    1980-01-01

    A grid structure for a nuclear reactor fuel assembly comprising a plurality of connecting members forming at least one longitudinally extending opening peripheral and inner fuel element openings through each of which openings at least one nuclear fuel element extends, said connecting members forming wall means surrounding said each peripheral and inner fuel element opening, a pair of rigid projections longitudinally spaced from one another extending from a portion of said wall means into said each peripheral and inner opening for rigidly engaging said each fuel element, respectively, yet permit individual longitudinal slippage thereof, and resilient means formed integrally on and from said wall means and positioned in said each peripheral and inner opening in opposed relationship with said projections and located to engage said fuel element to bias the latter into engagement with said rigid projections, respectively

  18. NUCLEAR HYDROGEN AND CAPTURED CARBON DIOXIDE FOR ALTERNATIVE LIQUID FUELS.

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Journal Article: NUCLEAR HYDROGEN AND CAPTURED CARBON DIOXIDE FOR ALTERNATIVE LIQUID FUELS. Citation Details In-Document Search Title: NUCLEAR HYDROGEN AND CAPTURED CARBON DIOXIDE FOR ALTERNATIVE LIQUID FUELS. Abstract not provided. Authors: Middleton, Bobby ; Kazimi, Mujid ; Leung, MinWah Publication Date: 2008-03-01 OSTI Identifier: 1145909 Report Number(s): SAND2008-1979J 518805 DOE Contract Number: DE-AC04-94AL85000 Resource Type: Journal Article

  19. Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear

    Office of Scientific and Technical Information (OSTI)

    Research Reactors (Technical Report) | SciTech Connect Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors Citation Details In-Document Search Title: Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit

  20. Nuclear Hydrogen and Captured Carbon Dioxide for Alternative Liquid Fuels.

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Conference: Nuclear Hydrogen and Captured Carbon Dioxide for Alternative Liquid Fuels. Citation Details In-Document Search Title: Nuclear Hydrogen and Captured Carbon Dioxide for Alternative Liquid Fuels. Abstract not provided. Authors: Middleton, Bobby ; Kazimi, Mujid Publication Date: 2007-06-01 OSTI Identifier: 1147847 Report Number(s): SAND2007-3553C 522735 DOE Contract Number: DE-AC04-94AL85000 Resource Type: Conference Resource Relation: Conference: ANS

  1. Sustainable thorium nuclear fuel cycles: A comparison of intermediate and

    Office of Scientific and Technical Information (OSTI)

    fast neutron spectrum systems (Journal Article) | DOE PAGES Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems This content will become publicly available on May 20, 2017 « Prev Next » Title: Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems Authors: Brown, N. R. ; Powers, J. J. ; Feng, B. ; Heidet, F. ; Stauff, N. E. ; Zhang, G. ; Todosow, M. ; Worrall, A. ; Gehin, J. C. ; Kim, T. K.

  2. Sustainable thorium nuclear fuel cycles: A comparison of intermediate and

    Office of Scientific and Technical Information (OSTI)

    fast neutron spectrum systems (Journal Article) | SciTech Connect Journal Article: Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems Citation Details In-Document Search This content will become publicly available on May 20, 2017 Title: Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems Authors: Brown, N. R. ; Powers, J. J. ; Feng, B. ; Heidet, F. ; Stauff, N. E. ; Zhang, G. ; Todosow,

  3. Metallic Fast Reactor Fuel Fabrication for Global Nuclear Energy Partnership

    SciTech Connect (OSTI)

    Douglas E. Burkes; Randall S. Fielding; Douglas L. Porter

    2009-07-01

    Fast reactors are once again being considered for nuclear power generation, in addition to transmutation of long-lived fission products resident in spent nuclear fuels. This re-consideration follows with intense developmental programs for both fuel and reactor design. One of the two leading candidates for next generation fast reactor fuel is metal alloys, resulting primarily from the successes achieved in the 1960s to early 1990s with both the experimental breeding reactor-II and the fast flux test facility. The goal of the current program is to develop and qualify a nuclear fuel system that performs all of the functions of a conventional, fast-spectrum nuclear fuel while destroying recycled actinides, thereby closing the nuclear fuel cycle. In order to meet this goal, the program must develop efficient and safe fuel fabrication processes designed for remote operation. This paper provides an overview of advanced casting processes investigated in the past, and the development of a gaseous diffusion calculation that demonstrates how straightforward process parameter modification can mitigate the loss of volatile minor actinides in the metal alloy melt.

  4. Utilization of Used Nuclear Fuel (UNF) in a Potential Future U.S. Fuel

    Office of Scientific and Technical Information (OSTI)

    Cycle Scenario (Conference) | SciTech Connect Utilization of Used Nuclear Fuel (UNF) in a Potential Future U.S. Fuel Cycle Scenario Citation Details In-Document Search Title: Utilization of Used Nuclear Fuel (UNF) in a Potential Future U.S. Fuel Cycle Scenario Authors: Worrall, Andrew [1] + Show Author Affiliations ORNL [ORNL Publication Date: 2013-01-01 OSTI Identifier: 1087026 DOE Contract Number: DE-AC05-00OR22725 Resource Type: Conference Resource Relation: Conference: WM2013 Symposium,

  5. A Practical Approach to a Closed Nuclear Fuel Cycle and Sustained...

    Office of Scientific and Technical Information (OSTI)

    Conference: A Practical Approach to a Closed Nuclear Fuel Cycle and Sustained Nuclear Energy Citation Details In-Document Search Title: A Practical Approach to a Closed Nuclear ...

  6. Advanced nuclear fuel cycles - Main challenges and strategic choices

    SciTech Connect (OSTI)

    Le Biez, V.; Machiels, A.; Sowder, A.

    2013-07-01

    A graphical conceptual model of the uranium fuel cycles has been developed to capture the present, anticipated, and potential (future) nuclear fuel cycle elements. The once-through cycle and plutonium recycle in fast reactors represent two basic approaches that bound classical options for nuclear fuel cycles. Chief among these other options are mono-recycling of plutonium in thermal reactors and recycling of minor actinides in fast reactors. Mono-recycling of plutonium in thermal reactors offers modest savings in natural uranium, provides an alternative approach for present-day interim management of used fuel, and offers a potential bridging technology to development and deployment of future fuel cycles. In addition to breeder reactors' obvious fuel sustainability advantages, recycling of minor actinides in fast reactors offers an attractive concept for long-term management of the wastes, but its ultimate value is uncertain in view of the added complexity in doing so,. Ultimately, there are no simple choices for nuclear fuel cycle options, as the selection of a fuel cycle option must reflect strategic criteria and priorities that vary with national policy and market perspectives. For example, fuel cycle decision-making driven primarily by national strategic interests will likely favor energy security or proliferation resistance issues, whereas decisions driven primarily by commercial or market influences will focus on economic competitiveness.

  7. Mox fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, Mark L.; Rosenstein, Richard G.

    2001-05-15

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion. characteristics of the assembly.

  8. MOX fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, Mark L.; Rosenstein, Richard G.

    1998-01-01

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

  9. MOX fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, Mark L.; Rosenstein, Richard G.

    2001-07-17

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

  10. MOX fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, M.L.; Rosenstein, R.G.

    1998-10-13

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly. 38 figs.

  11. Technical bases for interim storage of spent nuclear fuel

    SciTech Connect (OSTI)

    Johnson, A.B. Jr.

    1981-06-01

    The experience base for water storage of spent nuclear fuel has evolved since 1943. The technology base includes licensing documentation, standards, technology studies, pool operator experience, and documentation from public hearings. That base reflects a technology which is largely successful and mundane. It projects probable satisfactory water storage of spent water reactor fuel for several decades. Interim dry storage of spent water reactor fuel is not yet licensed in the US, but a data base and documentation have developed. There do not appear to be technological barriers to interim dry storage, based on demonstrations with irradiated fuel. Water storage will continue to be a part of spent fuel management at reactors. Whether dry storage becomes a prominent interim fuel management option depends on licensing and economic considerations. National policies will strongly influence how long the spent fuel remains in interim storage and what its final disposition will be.

  12. International nuclear fuel cycle fact book. Revision 4

    SciTech Connect (OSTI)

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

    1984-03-01

    This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

  13. International Nuclear Fuel Cycle Fact Book. Revision 5

    SciTech Connect (OSTI)

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

    1985-01-01

    This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

  14. Multidimensional Multiphysics Simulation of Nuclear Fuel Behavior

    SciTech Connect (OSTI)

    R. L. Williamson; J. D. Hales; S. R. Novascone; M. R. Tonks; D. R. Gaston; C. J. Permann; D. Andrs; R. C. Martineau

    2012-04-01

    Important aspects of fuel rod behavior, for example pellet-clad mechanical interaction (PCMI), fuel fracture, oxide formation, non- axisymmetric cooling, and response to fuel manufacturing defects, are inherently multidimensional in addition to being complicated multiphysics problems. Many current modeling tools are strictly 2D axisymmetric or even 1.5D. This paper outlines the capabilities of a new fuel modeling tool able to analyze either 2D axisymmetric or fully 3D models. These capabilities include temperature-dependent thermal conductivity of fuel; swelling and densification; fuel creep; pellet fracture; fission gas release; cladding creep; irradiation growth; and gap mechanics (contact and gap heat transfer). The need for multiphysics, multidimensional modeling is then demonstrated through a discussion of results for a set of example problems. The first, a 10-pellet rodlet, demonstrates the viability of the solution method employed. This example highlights the effect of our smeared cracking model and also shows the multidimensional nature of discrete fuel pellet modeling. The second example relies on our multidimensional, multiphysics approach to analyze a missing pellet surface problem. The next example is the analysis of cesium diffusion in a TRISO fuel particle with defects. As a final example, we show a lower-length-scale simulation coupled to a continuum-scale simulation.

  15. Spent nuclear fuel discharges from US reactors 1992

    SciTech Connect (OSTI)

    Not Available

    1994-05-05

    This report provides current statistical data on every fuel assembly irradiated in commercial nuclear reactors operating in the United States. It also provides data on the current inventories and storage capacities of those reactors to a wide audience, including Congress, Federal and State agencies, the nuclear and electric industries and the general public. It uses data from the mandatory, ``Nuclear Fuel Data`` survey, Form RW-859 for 1992 and historical data collected by the Energy Information Administration (EIA) on previous Form RW-859 surveys. The report was prepared by the EIA under a Memorandum of Understanding with the Office of Civilian Radioactive Waste Management.

  16. High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001

    SciTech Connect (OSTI)

    Brown, L.C.

    2002-11-01

    OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

  17. The Prospective Role of JAEA Nuclear Fuel Cycle Engineering Laboratories

    SciTech Connect (OSTI)

    Ojima, Hisao; Dojiri, Shigeru; Tanaka, Kazuhiko; Takeda, Seiichiro; Nomura, Shigeo

    2007-07-01

    JAEA Nuclear Fuel Cycle Engineering Laboratories was established in 2005 to take over the activities of the JNC Tokai Works. Many kinds of development activities have been carried out since 1959. Among these, the results on the centrifuge for U enrichment, LWR spent fuel reprocessing and MOX fuel fabrication have already provided the foundation of the fuel cycle industry in Japan. R and D on the treatment and disposal of high-level waste and FBR fuel reprocessing has also been carried out. Through such activities, radioactive material release to the environment has been appropriately controlled and all nuclear materials have been placed under IAEA safeguards. The Laboratories has sufficient experience and ability to establish the next generation closed cycle and strives to become a world-class Center Of Excellence (COE). (authors)

  18. Depleted uranium as a backfill for nuclear fuel waste package

    DOE Patents [OSTI]

    Forsberg, C.W.

    1998-11-03

    A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

  19. Depleted uranium as a backfill for nuclear fuel waste package

    DOE Patents [OSTI]

    Forsberg, Charles W.

    1998-01-01

    A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

  20. Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

    SciTech Connect (OSTI)

    Brent W. Dixon; Steven J. Piet

    2004-10-01

    The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository (63,000 MTiHM commercial, 7,000 MT non-commercial). There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel management options in the context of a full range of possible nuclear energy futures. The analysis indicates the best option to implement varies depending on the nuclear energy future selected. The first step in understanding the need for different spent fuel management approaches is to understand the size of potential spent fuel inventories. A full range of potential futures for domestic commercial nuclear energy is considered. These energy futures are as follows: 1. Existing License Completion - Based on existing spent fuel inventories plus extrapolation of future plant-by-plant discharges until the end of each operating license, including known license extensions. 2. Extended License Completion - Based on existing spent fuel inventories plus a plant-by-plant extrapolation of future discharges assuming on all operating plants having one 20-year extension. 3. Continuing Level Energy Generation - Based on extension of the current ~100 GWe installed commercial base and average spent fuel discharge of 2100 MT/yr through the year 2100. 4. Continuing Market Share Generation Based on a 1.8% compounded growth of the electricity market through the year 2100, matched by growing nuclear capacity and associated spent fuel discharge. 5. Growing Market Share Generation - Extension of current nuclear capacity and associated spent fuel discharge through 2100 with 3.2% growth representing 1.5% market growth (all energy, not just electricity) and 1.7% share growth. Share growth results in tripling market share by 2100 from the current 8.4% to 25%, equivalent to continuing the average market growth of last 50 years for an additional 100 years. Five primary spent fuel management strategies are assessed against each of the energy futures to determine the number of geological repositories needed and how the first repository would be used. The geological repository site at Yucca Mountain, Nevada, has the physical potential to accommodate all the spent fuel that will be generated by the current fleet of domestic commercial nuclear reactors, even with license extensions. If new nuclear plants are built in the future as replacements or additions, the United States will need to adopt spent fuel treatment to extend the life of the repository. Should a significant number of new nuclear plants be built, advanced fuel recycling will be needed to fully manage the spent fuel within a single repository. The analysis also considers the timeframe for most efficient implementation of new spent fuel management strategies. The mix of unprocessed spent fuel and processed high level waste in Yucca Mountain varies with each future and strategy. Either recycling must start before there is too much unprocessed waste emplaced or unprocessed waste will have to be retrieved later with corresponding costs. For each case, the latest date to implement reprocessing without subsequent retrieval is determined.

  1. Porous nuclear fuel element for high-temperature gas-cooled nuclear reactors

    DOE Patents [OSTI]

    Youchison, Dennis L.; Williams, Brian E.; Benander, Robert E.

    2011-03-01

    Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

  2. Methods for manufacturing porous nuclear fuel elements for high-temperature gas-cooled nuclear reactors

    DOE Patents [OSTI]

    Youchison, Dennis L.; Williams, Brian E.; Benander, Robert E.

    2010-02-23

    Methods for manufacturing porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's). Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, a thin coating of nuclear fuel may be deposited inside of a highly porous skeletal structure made, for example, of reticulated vitreous carbon foam.

  3. Porous nuclear fuel element with internal skeleton for high-temperature gas-cooled nuclear reactors

    DOE Patents [OSTI]

    Youchison, Dennis L.; Williams, Brian E.; Benander, Robert E.

    2013-09-03

    Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

  4. An evaluation of the nuclear fuel performance code BISON

    SciTech Connect (OSTI)

    Perez, D. M.; Williamson, R. L.; Novascone, S. R.; Larson, T. K.; Hales, J. D.; Spencer, B. W.; Pastore, G.

    2013-07-01

    BISON is a modern finite-element based nuclear fuel performance code that has been under development at the Idaho National Laboratory (USA) since 2009. The code is applicable to both steady and transient fuel behavior and is used to analyze either 2D axisymmetric or 3D geometries. BISON has been applied to a variety of fuel forms including LWR fuel rods, TRISO-coated fuel particles, and metallic fuel in both rod and plate geometries. Code validation is currently in progress, principally by comparison to instrumented LWR fuel rods and other well known fuel performance codes. Results from several assessment cases are reported, with emphasis on fuel centerline temperatures at various stages of fuel life, fission gas release, and clad deformation during pellet clad mechanical interaction (PCMI). BISON comparisons to fuel centerline temperature measurements are very good at beginning of life and reasonable at high burnup. Although limited to date, fission gas release comparisons are very good. Comparisons of rod diameter following significant power ramping are also good and demonstrate BISON's unique ability to model discrete pellet behavior and accurately predict clad ridging from PCMI. (authors)

  5. Fuel cycle cost uncertainty from nuclear fuel cycle comparison

    SciTech Connect (OSTI)

    Li, J.; McNelis, D.; Yim, M.S.

    2013-07-01

    This paper examined the uncertainty in fuel cycle cost (FCC) calculation by considering both model and parameter uncertainty. Four different fuel cycle options were compared in the analysis including the once-through cycle (OT), the DUPIC cycle, the MOX cycle and a closed fuel cycle with fast reactors (FR). The model uncertainty was addressed by using three different FCC modeling approaches with and without the time value of money consideration. The relative ratios of FCC in comparison to OT did not change much by using different modeling approaches. This observation was consistent with the results of the sensitivity study for the discount rate. Two different sets of data with uncertainty range of unit costs were used to address the parameter uncertainty of the FCC calculation. The sensitivity study showed that the dominating contributor to the total variance of FCC is the uranium price. In general, the FCC of OT was found to be the lowest followed by FR, MOX, and DUPIC. But depending on the uranium price, the FR cycle was found to have lower FCC over OT. The reprocessing cost was also found to have a major impact on FCC.

  6. Temperature measuring analysis of the nuclear reactor fuel assembly

    SciTech Connect (OSTI)

    Urban, F. E-mail: zdenko.zavodny@stuba.sk; Kučák, L. E-mail: zdenko.zavodny@stuba.sk; Bereznai, J. E-mail: zdenko.zavodny@stuba.sk; Závodný, Z. E-mail: zdenko.zavodny@stuba.sk; Muškát, P. E-mail: zdenko.zavodny@stuba.sk

    2014-08-06

    Study was based on rapid changes of measured temperature values from the thermocouple in the VVER 440 nuclear reactor fuel assembly. Task was to determine origin of fluctuations of the temperature values by experiments on physical model of the fuel assembly. During an experiment, heated water was circulating in the system and cold water inlet through central tube to record sensitivity of the temperature sensor. Two positions of the sensor was used. First, just above the central tube in the physical model fuel assembly axis and second at the position of the thermocouple in the VVER 440 nuclear reactor fuel assembly. Dependency of the temperature values on time are presented in the diagram form in the paper.

  7. International nuclear fuel cycle fact book. [Contains glossary

    SciTech Connect (OSTI)

    Leigh, I.W.; Lakey, L.T.; Schneider, K.J.; Silviera, D.J.

    1987-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

  8. International Nuclear Fuel Cycle Fact Book. Revision 12

    SciTech Connect (OSTI)

    Leigh, I.W.

    1992-05-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

  9. International nuclear fuel cycle fact book: Revision 9

    SciTech Connect (OSTI)

    Leigh, I.W.

    1989-01-01

    The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. The Fact Book contains: national summaries in which a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; and international agencies in which a section for each of the international agencies which has significant fuel cycle involvement, and a listing of nuclear societies. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter is presented from the perspective of the Fact Book user in the United States.

  10. Effects of aqueous effluents from in situ fossil fuel processing technologies on aquatic systems. Annual progress report, January 1-December 31, 1979

    SciTech Connect (OSTI)

    Bergman, H.L.

    1980-01-04

    This is the third annual progress report for a continuing EPA-DOE jointly funded project to evaluate the effects of aqueous effluents from in situ fossil-fuel processing technologies on aquatic biota. The project is organized into four project tasks: (1) literature review; (2) process water screening; (3) methods development; and (4) recommendations. Our Bibliography of aquatic ecosystem effects, analytical methods and treatment technologies for organic compounds in advanced fossil-fuel processing effluents was submitted to the EPA for publication. The bibliography contains 1314 citations indexed by chemicals, keywords, taxa and authors. We estimate that the second bibliography volume will contain approximately 1500 citations and be completed in February. We compiled results from several laboratories of inorganic characterizations of 19 process waters: 55 simulated in situ oil-shale retort waters; and Hanna-3, Hanna-4B 01W and Lawrence Livermore Hoe Creek underground coal gasification condenser waters. These process waters were then compared to a published summary of the analyses from 18 simulated in situ oil-shale retort waters. We completed this year 96-h flow-through toxicity bioassays with fathead minnows and rainbow trout and 48-h flow-through bioassays with Daphnia pulicaria exposed to 5 oil-shale process waters, 1 tar-sand process water, 2 underground coal gasification condenser waters, 1 post-gasification backflood condenser water, as well as 2 bioassays with fossil-fuel process water constituents. The LC/sub 50/ toxicity values for these respective species when exposed to these waters are given in detail. (LTN)

  11. Double-clad nuclear-fuel safety rod

    DOE Patents [OSTI]

    McCarthy, W.H.; Atcheson, D.B.

    1981-12-30

    A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

  12. Apparatus for injection casting metallic nuclear energy fuel rods

    DOE Patents [OSTI]

    Seidel, Bobby R.; Tracy, Donald B.; Griffiths, Vernon

    1991-01-01

    Molds for making metallic nuclear fuel rods are provided which present reduced risks to the environment by reducing radioactive waste. In one embodiment, the mold is consumable with the fuel rod, and in another embodiment, part of the mold can be re-used. Several molds can be arranged together in a cascaded manner, if desired, or several long cavities can be integrated in a monolithic multiple cavity re-usable mold.

  13. FUEL ELEMENTS FOR THERMAL-FISSION NUCLEAR REACTORS

    DOE Patents [OSTI]

    Flint, O.

    1961-01-10

    Fuel elements for thermal-fission nuclear reactors are described. The fuel element is comprised of a core of alumina, a film of a metal of the class consisting of copper, silver, and nickel on the outer face of the core, and a coating of an oxide of a metal isotope of the class consisting of Un/sup 235/, U/ sup 233/, and Pu/sup 239/ on the metal f ilm.

  14. Fossil Energy RSS Feeds | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Fossil Energy RSS Feeds Fossil Energy RSS Feeds RSS, sometimes known as Really Simple Syndication, is a popular means of sharing content (such as news headlines) without requiring readers to constantly visit a Web site to see what's new. RSS feeds contain headlines and hyperlinks to longer articles or Web pages. RSS feeds from the Office of Fossil Energy provide updates of specific interest to the fossil fuel community. Fossil Energy RSS feeds are free of charge. RSS content can be read using

  15. Technology Insights and Perspectives for Nuclear Fuel Cycle Concepts

    SciTech Connect (OSTI)

    S. Bays; S. Piet; N. Soelberg; M. Lineberry; B. Dixon

    2010-09-01

    The following report provides a rich resource of information for exploring fuel cycle characteristics. The most noteworthy trends can be traced back to the utilization efficiency of natural uranium resources. By definition, complete uranium utilization occurs only when all of the natural uranium resource can be introduced into the nuclear reactor long enough for all of it to undergo fission. Achieving near complete uranium utilization requires technologies that can achieve full recycle or at least nearly full recycle of the initial natural uranium consumed from the Earth. Greater than 99% of all natural uranium is fertile, and thus is not conducive to fission. This fact requires the fuel cycle to convert large quantities of non-fissile material into fissile transuranics. Step increases in waste benefits are closely related to the step increase in uranium utilization going from non-breeding fuel cycles to breeding fuel cycles. The amount of mass requiring a disposal path is tightly coupled to the quantity of actinides in the waste stream. Complete uranium utilization by definition means that zero (practically, near zero) actinide mass is present in the waste stream. Therefore, fuel cycles with complete (uranium and transuranic) recycle discharge predominately fission products with some actinide process losses. Fuel cycles without complete recycle discharge a much more massive waste stream because only a fraction of the initial actinide mass is burned prior to disposal. In a nuclear growth scenario, the relevant acceptable frequency for core damage events in nuclear reactors is inversely proportional to the number of reactors deployed in a fuel cycle. For ten times the reactors in a fleet, it should be expected that the fleet-average core damage frequency be decreased by a factor of ten. The relevant proliferation resistance of a fuel cycle system is enhanced with: decreasing reliance on domestic fuel cycle services, decreasing adaptability for technology misuse, enablement of material accountability, and decreasing material attractiveness.

  16. Railroad transportation of spent nuclear fuel

    SciTech Connect (OSTI)

    Wooden, D.G.

    1986-03-01

    This report documents a detailed analysis of rail operations that are important for assessing the risk of transporting high-level nuclear waste. The major emphasis of the discussion is towards ''general freight'' shipments of radioactive material. The purpose of this document is to provide a basis for selecting models and parameters that are appropriate for assessing the risk of rail transportation of nuclear waste.

  17. Preparation of nuclear fuel spheres by flotation-internal gelation

    DOE Patents [OSTI]

    Haas, P.A.; Fowler, V.L.; Lloyd, M.H.

    1984-12-21

    A simplified internal gelation process is claimed for the preparation of gel spheres of nuclear fuels. The process utilizes perchloroethylene as a gelation medium. Gelation is accomplished by directing droplets of a nuclear fuel broth into a moving volume of hot perchloroethylene (about 85/sup 0/C) in a trough. Gelation takes place as the droplets float on the surface of the perchloroethylene and the resultant gel spheres are carried directly into an ager column which is attached to the trough. The aged spheres are disengaged from the perchloroethylene on a moving screen and are deposited in an aqueous wash column. 3 figs.

  18. Next-generation nuclear fuel withstands high-temperature accident

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    conditions U.S. DEPARTMENT OF ENERGY IDAHO FALLS, IDAHO, 83403 For Immediate Release: Sept. 25, 2013 Media Contacts: Teri Ehresman, 208-526-7785 teri.ehresman@inl.gov Bill Cabage (ORNL), 865-574-4399, cabagewh@ornl.gov Next-generation nuclear fuel withstands high-temperature accident conditions IDAHO FALLS - A safer and more efficient nuclear fuel is on the horizon. A team of researchers at the U.S. Department of Energy's Idaho National Laboratory (INL) and Oak Ridge National Laboratory

  19. Preparation of nuclear fuel spheres by flotation-internal gelation

    DOE Patents [OSTI]

    Haas, Paul A.; Fowler, Victor L.; Lloyd, Milton H.

    1987-01-01

    A simplified internal gelation process for the preparation of gel spheres of nuclear fuels. The process utilizes perchloroethylene as a gelation medium. Gelation is accomplished by directing droplets of a nuclear fuel broth into a moving volume of hot perchloroethylene (about 85.degree. C.) in a trough. Gelation takes place as the droplets float on the surface of the perchloroethylene and the resultant gel spheres are carried directly into an ager column which is attached to the trough. The aged spheres are disengaged from the perchloroethylene on a moving screen and are deposited in an aqueous wash column.

  20. Quantitative assessment of proposals on assurance of nuclear fuel supply

    SciTech Connect (OSTI)

    Tanaka, T.; Kuno, Y.; Tanaka, S.

    2013-07-01

    The assurance of nuclear fuel supply has the potential to contribute to balancing peaceful use of nuclear power and nuclear nonproliferation. 5 proposals which provide the backup supply of the enrichment service in case of supply disruption, are investigated in this study. We investigated the 20 NPT countries which are non-nuclear-weapon states and possess operable commercial LWRs in October 2012 as potential participants for each proposal. As a result of literature researching, we have extracted factors that can be considered as important for a country to participate or not participate in the assurance of nuclear fuel supply. Then we have computed incentive and disincentive parameters for each country. The results show that the participation expectancy decreases in the order of IAEA Fuel Bank proposal, Russian LEU Reserve proposal, AFS proposal, WNA proposal and 6-Country proposal. The 'IAEA fuel bank proposal' would be triggered in case of the supply disruption which cannot be solved by the market mechanism and bilateral agreements.

  1. Manufacture of bonded-particle nuclear fuel composites

    DOE Patents [OSTI]

    Stradley, J.G.; Sease, J.D.

    1973-10-01

    A preselected volume of nuclear fuel particles are placed in a cylindrical mold cavity followed by a solid pellet of resin--carbon matrix material of preselected volume. The mold is heated to liquefy the pellet and the liquefied matrix forced throughout the interstices of the fuel particles by advancing a piston into the mold cavity. Excess matrix is permitted to escape through a vent hole in the end of the mold opposite to that end where the pellet was originally disposed. After the matrix is resolidified by cooling, the resultant fuel composite is removed from the mold and the resin component of the matrix carbonized. (Official Gazette)

  2. Nuclear waste actinides as fissile fuel in hybrid blankets

    SciTech Connect (OSTI)

    Sahin, S.; Al-Kusayer, T.A.

    1983-12-01

    The widespread use of the present LWRs produces substantial quantities of nuclear waste materials. Among those, actinide nuclear waste poses a serious problem of stockage because the associated half life times for actinides is measured in terms of geological time periods (several millions of years) so that no waste disposal guarantee over such time intervals can be given, except for space disposal. On the other hand, these nuclear waste actinides are very good fissionable materials for high energetic (D,T) fusion neutrons. It is therefore worthwhile to investigate their quality as potential nuclear fuel in hybrid blankets. The present study investigates the neutronic performance of hybrid blankets containing Np/sup 237/ and Cm/sup 244/ as fissile materials. The isotopic composition of Americium has been adjusted to the spent fuel isotope composition of a LWR. The geometrical design has been made, according to the AYMAN fussion-fission (hybrid) experimental facility, now in the very early phase of planning.

  3. Assessment of Nuclear Fuels using Radiographic Thickness Measurement Method

    SciTech Connect (OSTI)

    Muhammad Abir; Fahima Islam; Hyoung Koo Lee; Daniel Wachs

    2014-11-01

    The Convert branch of the National Nuclear Security Administration (NNSA) Global Threat Reduction Initiative (GTRI) focuses on the development of high uranium density fuels for research and test reactors for nonproliferation. This fuel is aimed to convert low density high enriched uranium (HEU) based fuel to high density low enriched uranium (LEU) based fuel for high performance research reactors (HPRR). There are five U.S. reactors that fall under the HPRR category, including: the Massachusetts Institute of Technology Reactor (MITR), the National Bureau of Standards Reactor (NBSR), the Missouri University Research Reactor (UMRR), the Advanced Test Reactor (ATR), and the High Flux Isotope Reactor (HFIR). U-Mo alloy fuel phase in the form of either monolithic or dispersion foil type fuels, such as ATR Full-size In center flux trap Position (AFIP) and Reduced Enrichment for Research and Test Reactor (RERTR), are being designed for this purpose. The fabrication process1 of RERTR is susceptible to introducing a variety of fuel defects. A dependable quality control method is required during fabrication of RERTR miniplates to maintain the allowable design tolerances, therefore evaluating and analytically verifying the fabricated miniplates for maintaining quality standards as well as safety. The purpose of this work is to analyze the thickness of the fabricated RERTR-12 miniplates using non-destructive technique to meet the fuel plate specification for RERTR fuel to be used in the ATR.

  4. Sensitivity analysis and optimization of the nuclear fuel cycle

    SciTech Connect (OSTI)

    Passerini, S.; Kazimi, M. S.; Shwageraus, E.

    2012-07-01

    A sensitivity study has been conducted to assess the robustness of the conclusions presented in the MIT Fuel Cycle Study. The Once Through Cycle (OTC) is considered as the base-line case, while advanced technologies with fuel recycling characterize the alternative fuel cycles. The options include limited recycling in LWRs and full recycling in fast reactors and in high conversion LWRs. Fast reactor technologies studied include both oxide and metal fueled reactors. The analysis allowed optimization of the fast reactor conversion ratio with respect to desired fuel cycle performance characteristics. The following parameters were found to significantly affect the performance of recycling technologies and their penetration over time: Capacity Factors of the fuel cycle facilities, Spent Fuel Cooling Time, Thermal Reprocessing Introduction Date, and in core and Out-of-core TRU Inventory Requirements for recycling technology. An optimization scheme of the nuclear fuel cycle is proposed. Optimization criteria and metrics of interest for different stakeholders in the fuel cycle (economics, waste management, environmental impact, etc.) are utilized for two different optimization techniques (linear and stochastic). Preliminary results covering single and multi-variable and single and multi-objective optimization demonstrate the viability of the optimization scheme. (authors)

  5. Nuclear fuel elements and method of making same

    DOE Patents [OSTI]

    Schweitzer, Donald G.

    1992-01-01

    A nuclear fuel element for a high temperature gas nuclear reactor that has an average operating temperature in excess of 2000.degree. C., and a method of making such a fuel element. The fuel element is characterized by having fissionable fuel material localized and stabilized within pores of a carbon or graphite member by melting the fissionable material to cause it to chemically react with the carbon walls of the pores. The fissionable fuel material is further stabilized and localized within the pores of the graphite member by providing one or more coatings of pyrolytic carbon or diamond surrounding the porous graphite member so that each layer defines a successive barrier against migration of the fissionable fuel from the pores, and so that the outermost layer of pyrolytic carbon or diamond forms a barrier between the fissionable material and the moderating gases used in an associated high temperature gas reactor. The method of the invention provides for making such new elements either as generally spherically elements, or as flexible filaments, or as other relatively small-sized fuel elements that are particularly suited for use in high temperature gas reactors.

  6. EIS-0218: Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel

    Broader source: Energy.gov [DOE]

    This study analyzes the potential environmental impacts of adopting a policy to manage foreign research reactor spent nuclear fuel containing uranium enriched in the United States. In particular, the study examines the comparative impacts of several alternative approaches to managing the spent fuel.

  7. Fossil-Fired Boilers

    Energy Science and Technology Software Center (OSTI)

    1993-09-23

    Boiler Performance Model (BPM 3.0S) is a set of computer programs developed to analyze the performance of fossil-fired utility boilers. The programs can model a wide variety of boiler designs, and can model coal, oil, or natural gas firing. The programs are intended for use by engineers performing analyses of alternative fuels, alternative operating modes, or boiler modifications.

  8. Nuclear Fuel Cycle Reasoner: PNNL FY13 Report

    SciTech Connect (OSTI)

    Hohimer, Ryan E.; Strasburg, Jana D.

    2013-09-30

    In Fiscal Year 2012 (FY12) PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In Fiscal Year 2013 (FY13) the SNAP demonstration was enhanced with respect to query and navigation usability issues.

  9. Webinar: Fuzzy Mud and the Future of Alternative Fuels | Argonne National

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Laboratory Webinar: Fuzzy Mud and the Future of Alternative Fuels Share Browse By - Any - Energy -Energy efficiency --Vehicles ---Alternative fuels ---Automotive engineering ---Diesel ---Electric drive technology ---Hybrid & electric vehicles ---Hydrogen & fuel cells ---Internal combustion ---Powertrain research --Building design ---Construction --Manufacturing -Energy sources --Renewable energy ---Bioenergy ---Solar energy --Fossil fuels ---Natural Gas --Nuclear energy ---Nuclear

  10. Air Shipment of Spent Nuclear Fuel from Romania to Russia

    SciTech Connect (OSTI)

    Igor Bolshinsky; Ken Allen; Lucian Biro; Alexander Buchelnikov

    2010-10-01

    Romania successfully completed the worlds first air shipment of spent nuclear fuel transported in Type B(U) casks under existing international laws and without shipment license special exceptions when the last Romanian highly enriched uranium (HEU) spent nuclear fuel was transported to the Russian Federation in June 2009. This air shipment required the design, fabrication, and licensing of special 20 foot freight containers and cask tiedown supports to transport the eighteen TUK 19 shipping casks on a Russian commercial cargo aircraft. The new equipment was certified for transport by road, rail, water, and air to provide multi modal transport capabilities for shipping research reactor spent fuel. The equipment design, safety analyses, and fabrication were performed in the Russian Federation and transport licenses were issued by both the Russian and Romanian regulatory authorities. The spent fuel was transported by truck from the VVR S research reactor to the Bucharest airport, flown by commercial cargo aircraft to the airport at Yekaterinburg, Russia, and then transported by truck to the final destination in a secure nuclear facility at Chelyabinsk, Russia. This shipment of 23.7 kg of HEU was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), as part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in close cooperation with the Rosatom State Atomic Energy Corporation and the International Atomic Energy Agency, and was managed in Romania by the National Commission for Nuclear Activities Control (CNCAN). This paper describes the planning, shipment preparations, equipment design, and license approvals that resulted in the safe and secure air shipment of this spent nuclear fuel.

  11. Systems for the Intermodal Routing of Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Peterson, Steven K; Liu, Cheng

    2015-01-01

    The safe and secure movement of spent nuclear fuel from shutdown and active reactor facilities to intermediate or long term storage sites may, in some instances, require the use of several modes of transportation to accomplish the move. To that end, a fully operable multi-modal routing system is being developed within Oak Ridge National Laboratory s (ORNL) WebTRAGIS (Transportation Routing Analysis Geographic Information System). This study aims to provide an overview of multi-modal routing, the existing state of the TRAGIS networks, the source data needs, and the requirements for developing structural relationships between various modes to create a suitable system for modeling the transport of spent nuclear fuel via a multimodal network. Modern transportation systems are comprised of interconnected, yet separate, modal networks. Efficient transportation networks rely upon the smooth transfer of cargoes at junction points that serve as connectors between modes. A key logistical impediment to the shipment of spent nuclear fuel is the absence of identified or designated transfer locations between transport modes. Understanding the potential network impacts on intermodal transportation of spent nuclear fuel is vital for planning transportation routes from origin to destination. By identifying key locations where modes intersect, routing decisions can be made to prioritize cost savings, optimize transport times and minimize potential risks to the population and environment. In order to facilitate such a process, ORNL began the development of a base intermodal network and associated routing code. The network was developed using previous intermodal networks and information from publicly available data sources to construct a database of potential intermodal transfer locations with likely capability to handle spent nuclear fuel casks. The coding development focused on modifying the existing WebTRAGIS routing code to accommodate intermodal transfers and the selection of prioritization constraints and modifiers to determine route selection. The limitations of the current model and future directions for development are discussed, including the current state of information on possible intermodal transfer locations for spent fuel.

  12. Zone approaches to international safeguards of a nuclear fuel cycle

    SciTech Connect (OSTI)

    Fishbone, L.G.; Higinbotham, W.A.

    1986-01-01

    At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a state are derived by combining the results of safeguards verifications for the individual facilities within it. We have examined safeguards approaches for a state nuclear fuel cycle that take into account the existence of all of the nuclear facilities in the state. We have focussed on the fresh-fuel zone of an advanced nuclear fuel cycle, the several facilities of which use or process low-enriched uranium. At one extreme, flows and inventories would be verified at each material balance area. At the other extreme, the flows into and out of the zone and the inventory of the whole zone would be verified. The intention is to develop an approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the zone approach and for some reasonable intermediate safeguards approaches. Technical effectiveness, in these cases, means an estimate of the assurance that all nuclear material has been accounted for.

  13. Modeling Deep Burn TRISO Particle Nuclear Fuel

    SciTech Connect (OSTI)

    Besmann, Theodore M [ORNL; Stoller, Roger E [ORNL; Samolyuk, German D [ORNL; Schuck, Paul C [ORNL; Rudin, Sven [Los Alamos National Laboratory (LANL); Wills, John [Los Alamos National Laboratory (LANL); Wirth, Brian D. [University of California, Berkeley; Kim, Sungtae [University of Wisconsin, Madison; Morgan, Dane [University of Wisconsin, Madison; Szlufarska, Izabela [University of Wisconsin, Madison

    2012-01-01

    Under the DOE Deep Burn program TRISO fuel is being investigated as a fuel form for consuming plutonium and minor actinides, and for greater efficiency in uranium utilization. The result will thus be to drive TRISO particulate fuel to very high burn-ups. In the current effort the various phenomena in the TRISO particle are being modeled using a variety of techniques. The chemical behavior is being treated utilizing thermochemical analysis to identify phase formation/transformation and chemical activities in the particle, including kernel migration. First principles calculations are being used to investigate the critical issue of fission product palladium attack on the SiC coating layer. Density functional theory is being used to understand fission product diffusion within the plutonia oxide kernel. Kinetic Monte Carlo techniques are shedding light on transport of fission products, most notably silver, through the carbon and SiC coating layers. The diffusion of fission products through an alternative coating layer, ZrC, is being assessed via DFT methods. Finally, a multiscale approach is being used to understand thermal transport, including the effect of radiation damage induced defects, in a model SiC material.

  14. Interim report spent nuclear fuel retrieval system fuel handling development testing

    SciTech Connect (OSTI)

    Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

    1997-06-01

    Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

  15. METHOD OF FORMING A FUEL ELEMENT FOR A NUCLEAR REACTOR

    DOE Patents [OSTI]

    Layer, E.H. Jr.; Peet, C.S.

    1962-01-23

    A method is given for preparing a fuel element for a nuclear reactor. The method includes the steps of sandblasting a body of uranium dioxide to roughen the surface thereof, depositing a thin layer of carbon thereon by thermal decomposition of methane, and cladding the uranium dioxide body with zirconium by gas pressure bonding. (AEC)

  16. Methods and apparatuses for the development of microstructured nuclear fuels

    DOE Patents [OSTI]

    Jarvinen, Gordon D.; Carroll, David W.; Devlin, David J.

    2009-04-21

    Microstructured nuclear fuel adapted for nuclear power system use includes fissile material structures of micrometer-scale dimension dispersed in a matrix material. In one method of production, fissile material particles are processed in a chemical vapor deposition (CVD) fluidized-bed reactor including a gas inlet for providing controlled gas flow into a particle coating chamber, a lower bed hot zone region to contain powder, and an upper bed region to enable powder expansion. At least one pneumatic or electric vibrator is operationally coupled to the particle coating chamber for causing vibration of the particle coater to promote uniform powder coating within the particle coater during fuel processing. An exhaust associated with the particle coating chamber and can provide a port for placement and removal of particles and powder. During use of the fuel in a nuclear power reactor, fission products escape from the fissile material structures and come to rest in the matrix material. After a period of use in a nuclear power reactor and subsequent cooling, separation of the fissile material from the matrix containing the embedded fission products will provide an efficient partitioning of the bulk of the fissile material from the fission products. The fissile material can be reused by incorporating it into new microstructured fuel. The fission products and matrix material can be incorporated into a waste form for disposal or processed to separate valuable components from the fission products mixture.

  17. Method of controlling crystallite size in nuclear-reactor fuels

    DOE Patents [OSTI]

    Lloyd, Milton H.; Collins, Jack L.; Shell, Sam E.

    1985-01-01

    Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.

  18. Method of controlling crystallite size in nuclear-reactor fuels

    DOE Patents [OSTI]

    Lloyd, M.H.; Collins, J.L.; Shell, S.E.

    Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.

  19. METHOD OF PREPARING A FUEL ELEMENT FOR A NUCLEAR REACTOR

    DOE Patents [OSTI]

    Hauth, J.J.; Anicetti, R.J.

    1962-12-01

    A method is described for preparing a fuel element for a nuclear reactor. According to the patent uranium dioxide is compacted in a metal tabe by directlng intense sound waves at the tabe prior to tamp packing or vibration compaction of the powder. (AEC)

  20. U.S. Spent Nuclear Fuel Data as of December 31,2002 Table 3

    U.S. Energy Information Administration (EIA) Indexed Site

    equal sum of components because of independent rounding. Source: Energy Information Administration, Form RW-859, "Nuclear Fuel Data" (2002). Table 1 | Table 2 NuclearUranium Data...

  1. U.S. Spent Nuclear Fuel Data as of December 31, 2002

    U.S. Energy Information Administration (EIA) Indexed Site

    Latest spent nuclear data Release Date: October 1, 2004 Spent nuclear fuel data is collected by the Energy Information Administration (EIA) for the Office of Civilian Radioactive...

  2. Nuclear Fuel Cycle Reasoner: PNNL FY12 Report

    SciTech Connect (OSTI)

    Hohimer, Ryan E.; Pomiak, Yekaterina G.; Neorr, Peter A.; Gastelum, Zoe N.; Strasburg, Jana D.

    2013-05-03

    Building on previous internal investments and leveraging ongoing advancements in semantic technologies, PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In developing this proof of concept prototype, the utility and relevancy of semantic technologies to the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D) has been better understood.

  3. Spallator and APEX nuclear fuel cycle: a new option for nuclear power

    SciTech Connect (OSTI)

    Steinberg, M.

    1982-01-01

    A new nuclear fuel cycle is described which provides a long term supply of nuclear fuel for the thermal LWR nuclear power reactors and eliminates the need for long-term storage of radioactive waste. Fissile fuel is produced by the Spallator which depends on the production of spallation neutrons by the interaction of high-energy (1 to 2 GeV) protons on a heavy-metal target. The neutrons are absorbed in a surrounding natural-uranium or thorium blanket in which fissile Pu-239 to U-233 is produced. Advances in linear accelerator technology makes it possible to design and construct a high-beam-current continuous-wave proton linac for production purposes. The target is similar to a sub-critical reactor and produces heat which is converted to electricity for supplying the linac. The Spallator is a self-sufficient fuel producer, which can compete with the fast breeder. The APEX fuel cycle depends on recycling the transuranics and long-lived fission products while extracting the stable and short-lived fission products when reprocessing the fuel. Transmutation and decay within the fuel cycle and decay of short-lived fission products external to the fuel cycle eliminates the need for long-term geological age shortage of fission-product waste.

  4. The Spallator and APEX nuclear fuel cycle: a new option for nuclear power

    SciTech Connect (OSTI)

    Steinberg, M.

    1983-02-01

    A new nuclear fuel cycle is described which provides a long term supply of nuclear fuel for the thermal LWR nuclear power reactors and eliminates the need for long-term storage of radioactive waste. Fissile fuel is produced by the Spallator which depends on the production of spallation neutrons by the interaction of high energy (1 to 2 GeV) protons on a heavy metal target. The neutrons are absorbed in a surrounding natural uranium or thorium blanket in which fissile Pu-239 or U-233 is produced. Advances in linear accelerator technology makes it possible to design and construct a high beam current continuous wave proton linac for production purposes. The target is similar to a sub-critical reactor and produces heat which is converted to electricity for supplying the linac. The Spallator is a selfsufficient fuel producer, which can compete with the fast breeder. The APEX fuel cycle depends on recycling the transuranics and long-lived fission products while extracting the stable and short-lived fission products when reprocessing the fuel. Transmutation and decay within the fuel cycle and decay of the short-lived fission products external to the fuel cycle eliminates the need for long-term geological age storage of fission product waste.

  5. Enduring Nuclear Fuel Cycle, Proceedings of a panel discussion

    SciTech Connect (OSTI)

    Walter, C. E., LLNL

    1997-11-18

    The panel reviewed the complete nuclear fuel cycle in the context of alternate energy resources, energy need projections, effects on the environment, susceptibility of nuclear materials to theft, diversion, and weapon proliferation. We also looked at ethical considerations of energy use, as well as waste, and its effects. The scope of the review extended to the end of the next century with due regard for world populations beyond that period. The intent was to take a long- range view and to project, not forecast, the future based on ethical rationales, and to avoid, as often happens, long-range discussions that quickly zoom in on only the next few decades. A specific nuclear fuel cycle technology that could satisfy these considerations was described and can be applied globally.

  6. Exploratory Design of a Reactor/Fuel Cycle Using Spent Nuclear Fuel Without Conventional Reprocessing - 13579

    SciTech Connect (OSTI)

    Bertch, Timothy C.; Schleicher, Robert W.; Rawls, John D.

    2013-07-01

    General Atomics has started design of a waste to energy nuclear reactor (EM2) that can use light water reactor (LWR) spent nuclear fuel (SNF). This effort addresses two problems: using an advanced small reactor with long core life to reduce nuclear energy overnight cost and providing a disposal path for LWR SNF. LWR SNF is re-fabricated into new EM2 fuel using a dry voloxidation process modeled on AIROX/ OREOX processes which remove some of the fission products but no heavy metals. By not removing all of the fission products the fuel remains self-protecting. By not separating heavy metals, the process remains proliferation resistant. Implementation of Energy Multiplier Module (EM2) fuel cycle will provide low cost nuclear energy while providing a long term LWR SNF disposition path which is important for LWR waste confidence. With LWR waste confidence recent impacts on reactor licensing, an alternate disposition path is highly relevant. Centered on a reactor operating at 250 MWe, the compact electricity generating system design maximizes site flexibility with truck transport of all system components and available dry cooling features that removes the need to be located near a body of water. A high temperature system using helium coolant, electricity is efficiently produced using an asynchronous high-speed gas turbine while the LWR SNF is converted to fission products. Reactor design features such as vented fuel and silicon carbide cladding support reactor operation for decades between refueling, with improved fuel utilization. Beyond the reactor, the fuel cycle is designed so that subsequent generations of EM2 reactor fuel will use the previous EM2 discharge, providing its own waste confidence plus eliminating the need for enrichment after the first generation. Additional LWR SNF is added at each re-fabrication to replace the removed fission products. The fuel cycle uses a dry voloxidation process for both the initial LWR SNF re-fabrication and later for EM2 discharge reuse. The EM2 waste disposal profile is effectively only fission products, which reduces the mass (about 3% vs LWR), average half life, heat and long term radio-toxicity of the disposal. Widespread implementation of EM2 fuel cycle is highly significant as it would increase world energy reserves; the remaining energy in U.S. LWR SNF alone exceeds that in the U.S. natural gas reserves. Unlike many LWR SNF disposition concepts, the EM2 fuel cycle conversion of SNF produces energy and associated revenue such that the overall project is cost effective. By providing conversion of SNF to fission products the fuel cycle is closed and a non-repository LWR SNF disposition path is created and overall repository requirements are significantly reduced. (authors)

  7. Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine

    Energy Savers [EERE]

    Nuclear Fuel Qualification Program | Department of Energy Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine Nuclear Fuel Qualification Program Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine Nuclear Fuel Qualification Program April 9, 2010 - 12:11pm Addthis KYIV, UKRAINE - Officials from the U.S. Department of Energy's (DOE) Office of Nuclear Energy today (April 8, 2010) participated in a ceremony in Ukraine to mark the insertion of

  8. Laser shockwave technique for characterization of nuclear fuel plate interfaces

    SciTech Connect (OSTI)

    Perton, M.; Levesque, D.; Monchalin, J.-P.; Lord, M.; Smith, J. A.; Rabin, B. H.

    2013-01-25

    The US National Nuclear Security Agency is tasked with minimizing the worldwide use of high-enriched uranium. One aspect of that effort is the conversion of research reactors to monolithic fuel plates of low-enriched uranium. The manufacturing process includes hot isostatic press bonding of an aluminum cladding to the fuel foil. The Laser Shockwave Technique (LST) is here evaluated for characterizing the interface strength of fuel plates using depleted Uranium/Mo foils. LST is a non-contact method that uses lasers for the generation and detection of large amplitude acoustic waves and is therefore well adapted to the quality assurance of this process. Preliminary results show a clear signature of well-bonded and debonded interfaces and the method is able to classify/rank the bond strength of fuel plates prepared under different HIP conditions.

  9. Laser Shockwave Technique For Characterization Of Nuclear Fuel Plate Interfaces

    SciTech Connect (OSTI)

    James A. Smith; Barry H. Rabin; Mathieu Perton; Daniel Lévesque; Jean-Pierre Monchalin; Martin Lord

    2012-07-01

    The US National Nuclear Security Agency is tasked with minimizing the worldwide use of high-enriched uranium. One aspect of that effort is the conversion of research reactors to monolithic fuel plates of low-enriched uranium. The manufacturing process includes hot isostatic press bonding of an aluminum cladding to the fuel foil. The Laser Shockwave Technique (LST) is here evaluated for characterizing the interface strength of fuel plates using depleted Uranium/Mo foils. LST is a non-contact method that uses lasers for the generation and detection of large amplitude acoustic waves and is therefore well adapted to the quality assurance of this process. Preliminary results show a clear signature of well-bonded and debonded interfaces and the method is able to classify/rank the bond strength of fuel plates prepared under different HIP conditions.

  10. Retrievable fuel pin end member for a nuclear reactor

    DOE Patents [OSTI]

    Rosa, Jerry M.

    1982-01-01

    A bottom end member (17b) on a retrievable fuel pin (13b) secures the pin (13b) within a nuclear reactor (12) by engaging on a transverse attachment rail (18) with a spring clip type of action. Removal and reinstallation if facilitated as only axial movement of the fuel pin (13b) is required for either operation. A pair of resilient axially extending blades (31) are spaced apart to define a slot (24) having a seat region (34) which receives the rail (18) and having a land region (37), closer to the tips (39) of the blades (31) which is normally of less width than the rail (18). Thus an axially directed force sufficient to wedge the resilient blades (31) apart is required to emplace or release the fuel pin (13b) such force being greater than the axial forces on the fuel pins (13b) which occur during operation of the reactor (12).

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

    SciTech Connect (OSTI)

    none,

    2011-09-01

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

  12. New York Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","5,271",13.4,"41,870",30.6 "Coal","2,781",7.1,"13,583",9.9 "Hydro and Pumped

  13. North Carolina Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,958",17.9,"40,740",31.7 "Coal","12,766",46.1,"71,951",55.9 "Hydro and Pumped

  14. South Carolina Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","6,486",27.0,"51,988",49.9 "Coal","7,230",30.1,"37,671",36.2 "Hydro and Pumped

  15. New Hampshire Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,247",29.8,"10,910",49.2 "Coal",546,13.1,"3,083",13.9 "Hydro and Pumped Storage",489,11.7,"1,478",6.7 "Natural

  16. New Jersey Nuclear Profile - All Fuels

    U.S. Energy Information Administration (EIA) Indexed Site

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,108",22.3,"32,771",49.9 "Coal","2,036",11.1,"6,418",9.8 "Hydro and Pumped Storage",404,2.2,-176,-0.3 "Natural

  17. Fuel cycle analysis of once-through nuclear systems.

    SciTech Connect (OSTI)

    Kim, T. K.; Taiwo, T. A.; Nuclear Engineering Division

    2010-08-10

    Once-through fuel cycle systems are commercially used for the generation of nuclear power, with little exception. The bulk of these once-through systems have been water-cooled reactors (light-water and heavy water reactors, LWRs and HWRs). Some gas-cooled reactors are used in the United Kingdom. The commercial power systems that are exceptions use limited recycle (currently one recycle) of transuranic elements, primarily plutonium, as done in Europe and nearing deployment in Japan. For most of these once-through fuel cycles, the ultimate storage of the used (spent) nuclear fuel (UNF, SNF) will be in a geologic repository. Besides the commercial nuclear plants, new once-through concepts are being proposed for various objectives under international advanced nuclear fuel cycle studies and by industrial and venture capital groups. Some of the objectives for these systems include: (1) Long life core for remote use or foreign export and to support proliferation risk reduction goals - In these systems the intent is to achieve very long core-life with no refueling and limited or no access to the fuel. Most of these systems are fast spectrum systems and have been designed with the intent to improve plant economics, minimize nuclear waste, enhance system safety, and reduce proliferation risk. Some of these designs are being developed under Generation IV International Forum activities and have generally not used fuel blankets and have limited the fissile content of the fuel to less than 20% for the purpose on meeting international nonproliferation objectives. In general, the systems attempt to use transuranic elements (TRU) produced in current commercial nuclear power plants as this is seen as a way to minimize the amount of the problematic radio-nuclides that have to be stored in a repository. In this case, however, the reprocessing of the commercial LWR UNF to produce the initial fuel will be necessary. For this reason, some of the systems plan to use low enriched uranium (LEU) fuels. Examples of systems in this class include the small modular reactors being considered internationally; e.g. 4S [Tsuboi 2009], Hyperion Power Module [Deal 2010], ARC-100 [Wade 2010], and SSTAR [Smith 2008]. (2) Systems for Resource Utilization - In recent years, interest has developed in the use of advanced nuclear designs for the effective utilization of fuel resources. Systems under this class have generally utilized the breed and burn concept in which fissile material is bred and used in situ in the reactor core. Due to the favorable breeding that is possible with fast neutrons, these systems have tended to be fast spectrum systems. In the once-through concepts (as opposed to the traditional multirecycle approach typically considered for fast reactors), an ignition (or starter) zone contains driver fuel which is fissile material. This zone is designed to last a long time period to allow the breeding of sufficient fissile material in the adjoining blanket zone. The blanket zone is initially made of fertile depleted uranium fuel. This zone could also be made of fertile thorium fuel or recovered uranium from fuel reprocessing or natural uranium. However, given the bulk of depleted uranium and the potentially large inventory of recovered uranium, it is unlikely that the use of thorium is required in the near term in the U.S. Following the breeding of plutonium or fissile U-233 in the blanket, this zone or assembly then carries a larger fraction of the power generation in the reactor. These systems tend to also have a long cycle length (or core life) and they could be with or without fuel shuffling. When fuel is shuffled, the incoming fuel is generally depleted uranium (or thorium) fuel. In any case, fuel is burned once and then discharged. Examples of systems in this class include the CANDLE concept [Sekimoto 2001], the traveling wave reactor (TWR) concept of TerraPower [Ellis 2010], the ultra-long life fast reactor (ULFR) by ANL [Kim 2010], and the BNL fast mixed spectrum reactor (FMSR) concept [Fisher 1979]. (3) Thermal systems for resource extension - These systems were primarily considered during the INFCE/NASAP evaluations [NASAP 1979] and include various LWR designs for increasing resource utilization (both uranium and thorium). This class would include the Radkowsky seed-blanket concept. Also included in this class are the thermal reactor systems being considered for deployment as small modular reactors, such as IRIS [Carelli 2004], mPower [mPower], and NuScale [NuScale] that are all water cooled reactors. The purpose of this work is to provide relevant systems and fuel cycle information for some of these once-through fuel cycle systems. In this report, the intent is on providing information on most of the systems from open sources and from scoping studies recently done within the program. As there is insufficient fuel cycle information on the first class of systems, they are not discussed in this report.

  18. Waste management plan for Hanford spent nuclear fuel characterization activities

    SciTech Connect (OSTI)

    Chastain, S.A. [Westinghouse Hanford Co., Richland, WA (United States); Spinks, R.L. [Pacific Northwest Lab., Richland, WA (United States)

    1994-10-17

    A joint project was initiated between Westinghouse Hanford Company (WHC) and Pacific Northwest Laboratory (PNL) to address critical issues associated with the Spent Nuclear Fuel (SNF) stored at the Hanford Site. Recently, particular attention has been given to remediation of the SNF stored in the K Basins. A waste management plan (WMP) acceptable to both parties is required prior to the movement of selected material to the PNL facilities for examination. N Reactor and Single Pass Reactor (SPR) fuel has been stored for an extended period of time in the N Reactor, PUREX, K-East, and K-West Basins. Characterization plans call for transport of fuel material form the K Basins to the 327 Building Postirradiation Testing Laboratory (PTL) in the 300 Area for examination. However, PNL received a directive stating that no examination work will be started in PNL hot cell laboratories without an approved disposal route for all waste generated related to the activity. Thus, as part of the Characterization Program Management Plan for Hanford Spent Nuclear Fuel, a waste management plan which will ensure that wastes generated as a result of characterization activities conducted at PNL will be accepted by WHC for disposition is required. This document contains the details of the waste handling plan that utilizes, to the greatest extent possible, established waste handling and disposal practices at Hanford between PNL and WHC. Standard practices are sufficient to provides for disposal of most of the waste materials, however, special consideration must be given to the remnants of spent nuclear fuel elements following examination. Fuel element remnants will be repackaged in an acceptable container such as the single element canister and returned to the K Basins for storage.

  19. Synthetic Fuel

    ScienceCinema (OSTI)

    Idaho National Laboratory - Steve Herring, Jim O'Brien, Carl Stoots

    2010-01-08

    Two global energy priorities today are finding environmentally friendly alternatives to fossil fuels, and reducing greenhouse gass Two global energy priorities today are finding environmentally friendly alternatives to fossil fuels, and reducing greenhous

  20. Nuclear reactor vessel fuel thermal insulating barrier

    DOE Patents [OSTI]

    Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.

    2013-03-19

    The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.