National Library of Energy BETA

Sample records for fuels nuclear electric

  1. 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.

  2. 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

  3. 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.

  4. Spent Nuclear Fuel

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

    Nuclear & Uranium Glossary FAQS Overview Data Status of U.S. nuclear outages (interactive) Nuclear power plants Uranium & nuclear fuel Spent nuclear fuel All nuclear data ...

  5. 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

  6. Alternative Fuels Data Center: Electricity Fuel Basics

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electricity Fuel Basics to someone by E-mail Share Alternative Fuels Data Center: Electricity Fuel Basics on Facebook Tweet about Alternative Fuels Data Center: Electricity Fuel Basics on Twitter Bookmark Alternative Fuels Data Center: Electricity Fuel Basics on Google Bookmark Alternative Fuels Data Center: Electricity Fuel Basics on Delicious Rank Alternative Fuels Data Center: Electricity Fuel Basics on Digg Find More places to share Alternative Fuels Data Center: Electricity Fuel Basics on

  7. Method and apparatus for steam mixing a nuclear fueled electricity generation system

    DOE Patents [OSTI]

    Tsiklauri, Georgi V.; Durst, Bruce M.

    1996-01-01

    A method and apparatus for improving the efficiency and performance of a nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs. Another benefit of the instant invention is the extension of plant life and the reduction of downtime due to refueling.

  8. Chapter 4: Advancing Clean Electric Power Technologies | Nuclear Fuel Cycles Technology Assessment

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

    Nuclear Fuel Cycles Chapter 4: Technology Assessments Introduction and Background The Nuclear Fuel Cycle (NFC) is defined as the total set of operations required to produce fission energy and manage the associated nuclear materials. It can have different attributes, including the extension of natural resources, or the minimization of waste disposal requirements. The NFC, as depicted in Figure 4.O.1, is comprised of a set of operations that include the extraction of uranium (U) resources from the

  9. Outline for a multi-cell nuclear thermionic fuel element that may be pretested with electric heat

    SciTech Connect (OSTI)

    Wilson, V.C.

    1997-01-01

    A nuclear thermionic converter electrical generating system is proposed in which the nuclear fuel is clad in tungsten (W) and transmits heat to a tungsten emitter by radiation. The tungsten clad is a single unit, containing a continuous fuel stack with an unfueled section extending through one end of the reactor. The emitters are electrically insulated from the heat source; therefore, several converters may be connected by short leads to produce more voltage per fuel element and to reduce the power losses in the leads. A fast reactor design was chosen; consequently, tungsten may be used for the fuel cladding and the emitters without a significant reactivity penalty due to neutron capture by tungsten epithermal resonances. The ability to use all-tungsten emitters may permit high emitter temperatures. Calculations indicate that at an emitter temperature of 2150 K and current density of 10A/cm{sup 2}, a 36 cm long thermionic fuel element (TFE) with 9 converters in series should produce 4500W{sub e} at 9.2 V and 15.7{percent} efficiency. One major advantage of this approach, relative to typical multicell designs is that the system can be tested by electrical heaters in the fuel cavity before loading fuel. {copyright} {ital 1997 American Institute of Physics.}

  10. Outline for a multi-cell nuclear thermionic fuel element that may be pretested with electric heat

    SciTech Connect (OSTI)

    Wilson, Volney C.

    1997-01-10

    A nuclear thermionic converter electrical generating system is proposed in which the nuclear fuel is clad in tungsten (W) and transmits heat to a tungsten emitter by radiation. The tungsten clad is a single unit, containing a continuous fuel stack with an unfueled section extending through one end of the reactor. The emitters are electrically insulated from the heat source; therefore, several converters may be connected by short leads to produce more voltage per fuel element and to reduce the power losses in the leads. A fast reactor design was chosen; consequently, tungsten may be used for the fuel cladding and the emitters without a significant reactivity penalty due to neutron capture by tungsten epithermal resonances. The ability to use all-tungsten emitters may permit high emitter temperatures. Calculations indicate that at an emitter temperature of 2150 K and current density of 10 A/cm{sup 2}, a 36 cm long thermionic fuel element (TFE) with 9 converters in series should produce 4500 W{sub e} at 9.2 V and 15.7% efficiency. One major advantage of this approach, relative to typical multicell designs is that the system can be tested by electrical heaters in the fuel cavity before loading fuel.

  11. 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.

  12. 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.

  13. Alternative Fuels Data Center: Electricity

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electricity Printable Version Share this resource Send a link to Alternative Fuels Data Center: Electricity to someone by E-mail Share Alternative Fuels Data Center: Electricity on Facebook Tweet about Alternative Fuels Data Center: Electricity on Twitter Bookmark Alternative Fuels Data Center: Electricity on Google Bookmark Alternative Fuels Data Center: Electricity on Delicious Rank Alternative Fuels Data Center: Electricity on Digg Find More places to share Alternative Fuels Data Center:

  14. Spent Nuclear Fuel

    Gasoline and Diesel Fuel Update (EIA)

    Spent Nuclear Fuel Release date: December 7, 2015 Next release date: Late 2018 Spent nuclear fuel data are collected by the U.S. Energy Information Administration (EIA) for the Department of Energy's Office of Standard Contract Management (Office of the General Counsel) on the Form GC-859, "Nuclear Fuel Data Survey." The data include detailed characteristics of spent nuclear fuel discharged from commercial U.S. nuclear power plants and currently stored at commercial sites in the United

  15. 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.

  16. 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.

  17. 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.

  18. Hydrogen Fueling for Current and Anticipated Fuel Cell Electric...

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

    Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs)" held on June 24, 2014. Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles ...

  19. Alternative Fuels Data Center: Fuel Cell Electric Vehicles

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Hydrogen Printable Version Share this resource Send a link to Alternative Fuels Data Center: Fuel Cell Electric Vehicles to someone by E-mail Share Alternative Fuels Data Center: Fuel Cell Electric Vehicles on Facebook Tweet about Alternative Fuels Data Center: Fuel Cell Electric Vehicles on Twitter Bookmark Alternative Fuels Data Center: Fuel Cell Electric Vehicles on Google Bookmark Alternative Fuels Data Center: Fuel Cell Electric Vehicles on Delicious Rank Alternative Fuels Data Center: Fuel

  20. 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.

  1. 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...

  2. 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.

  3. 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.

  4. Nuclear Fuel Cycle | Department of Energy

    Energy Savers [EERE]

    ... In a fuel fabrication plant great care is taken with the size and shape of processing ... Generation of electricity in a nuclear reactor is similar to a coal-fired steam station. The ...

  5. 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.

  6. Nuclear Fuel Cycle Options Catalog

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

    Hydrogen Production Market Transformation Fuel Cells Predictive Simulation of Engines ... Twitter Google + Vimeo Newsletter Signup SlideShare Nuclear Fuel Cycle Options Catalog ...

  7. 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.

  8. 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

  9. Alternative Fuels Data Center: Hybrid Electric Vehicles

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Hybrid Electric Vehicles to someone by E-mail Share Alternative Fuels Data Center: Hybrid Electric Vehicles on Facebook Tweet about Alternative Fuels Data Center: Hybrid Electric Vehicles on Twitter Bookmark Alternative Fuels Data Center: Hybrid Electric Vehicles on Google Bookmark Alternative Fuels Data Center: Hybrid Electric Vehicles on Delicious Rank Alternative Fuels Data Center: Hybrid Electric Vehicles on Digg Find More places to share Alternative Fuels Data Center: Hybrid Electric

  10. Alternative Fuels Data Center: Electricity Related Links

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electricity Printable Version Share this resource Send a link to Alternative Fuels Data Center: Electricity Related Links to someone by E-mail Share Alternative Fuels Data Center: Electricity Related Links on Facebook Tweet about Alternative Fuels Data Center: Electricity Related Links on Twitter Bookmark Alternative Fuels Data Center: Electricity Related Links on Google Bookmark Alternative Fuels Data Center: Electricity Related Links on Delicious Rank Alternative Fuels Data Center: Electricity

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. Alternative Fuels Data Center: Hydrogen Fuel Cell Vehicle Electric

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Availability Hydrogen Printable Version Share this resource Send a link to Alternative Fuels Data Center: Hydrogen Fuel Cell Vehicle Electric Availability to someone by E-mail Share Alternative Fuels Data Center: Hydrogen Fuel Cell Vehicle Electric Availability on Facebook Tweet about Alternative Fuels Data Center: Hydrogen Fuel Cell Vehicle Electric Availability on Twitter Bookmark Alternative Fuels Data Center: Hydrogen Fuel Cell Vehicle Electric Availability on Google Bookmark Alternative

  16. Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles

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

    (FCEVs) | Department of Energy for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs) Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs) Download presentation slides from the DOE Fuel Cell Technologies Office webinar "Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs)" held on June 24, 2014. Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs) Webinar Slides (3.28 MB) More Documents

  17. Nuclear reactor fuel element

    DOE Patents [OSTI]

    Johnson, Carl E.; Crouthamel, Carl E.

    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.

  18. The Birth of Nuclear-Generated Electricity

    DOE R&D Accomplishments [OSTI]

    1999-09-01

    The Experimental Breeder Reactor-I (EBR-I), built in Idaho in 1949, generated the first usable electricity from nuclear power on December 20, 1951. More importantly, the reactor was used to prove that it was possible to create more nuclear fuel in the reactor than it consumed during operation -- fuel breeding. The EBR-I facility is now a National Historic Landmark open to the public.

  19. 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)

  20. 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.

  1. Electricity Fuel Basics | Department of Energy

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

    Vehicles & Fuels » Fuels » Electricity Fuel Basics Electricity Fuel Basics August 19, 2013 - 5:44pm Addthis Electricity used to power vehicles is generally provided by the electricity grid and stored in the vehicle's batteries. Vehicles that run on electricity have no tailpipe emissions. Emissions that can be attributed to electric vehicles are generated during electricity production at the power plant. Charging plug-in electric vehicles at home is as simple as plugging them into an

  2. 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.

  3. 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.

  4. Nuclear Fuels | Department of Energy

    Energy Savers [EERE]

    A nuclear fuel assembly consists of hundreds of thousands of uranium pellets, stacked and ... scales from micro-structural level to individual pellets to entire rods and bundles. ...

  5. Greater fuel diversity needed to meet growing US electricity demand

    SciTech Connect (OSTI)

    Burt, B.; Mullins, S.

    2008-01-15

    Electricity demand is growing in the USA. One way to manage the uncertainty is to diversity fuel sources. Fuel sources include coal, natural gas, nuclear and renewable energy sources. Tables show actual and planned generation projects by fuel types. 1 fig., 2 tabs.

  6. Fuel cell electric power production

    DOE Patents [OSTI]

    Hwang, Herng-Shinn; Heck, Ronald M.; Yarrington, Robert M.

    1985-01-01

    A process for generating electricity from a fuel cell includes generating a hydrogen-rich gas as the fuel for the fuel cell by treating a hydrocarbon feed, which may be a normally liquid feed, in an autothermal reformer utilizing a first monolithic catalyst zone having palladium and platinum catalytic components therein and a second, platinum group metal steam reforming catalyst. Air is used as the oxidant in the hydrocarbon reforming zone and a low oxygen to carbon ratio is maintained to control the amount of dilution of the hydrogen-rich gas with nitrogen of the air without sustaining an insupportable amount of carbon deposition on the catalyst. Anode vent gas may be utilized as the fuel to preheat the inlet stream to the reformer. The fuel cell and the reformer are preferably operated at elevated pressures, up to about a pressure of 150 psia for the fuel cell.

  7. Webinar: Hydrogen Fueling for Current and Anticipated Fuel Cell Electric

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

    Vehicles (FCEVs) | Department of Energy Fueling for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs) Webinar: Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs) Below is the text version of the webinar titled "Hydrogen Fueling for Current and Anticipated Fuel Cell Electric Vehicles (FCEVs)," originally presented on June 24, 2014. In addition to this text version of the audio, you can access the presentation slides. Alli Aman: [Audio starts

  8. Electric Fuel Battery Corporation | Open Energy Information

    Open Energy Info (EERE)

    Fuel Battery Corporation Jump to: navigation, search Name: Electric Fuel Battery Corporation Place: Auburn, Alabama Zip: 36832 Product: Develops and manufactures BA-8180U high...

  9. 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 today’s implementation to revolutionary concepts that would require the development of advanced nuclear technologies.

  10. Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol

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

    DOE Webinar Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol U.S. DOE WEBINAR ON H2 FUELING PROTOCOLS: PARTICIPANTS Rob Burgess Moderator Jesse Schneider TIR J2601, ...

  11. Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol |

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

    Department of Energy Fuel Cell Electric Vehicle Hydrogen Fueling Protocol Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol Download the webinar slides from the U.S. Department of Energy Fuel Cell Technologies Office webinar, "Hydrogen Refueling Protocols," held February 22, 2013. Hydrogen Refueling Protocols Webinar Slides (3.49 MB) More Documents & Publications Introduction to SAE Hydrogen Fueling Standardization Developing SAE Safety Standards for Hydrogen and

  12. Fuel Cell Electric Vehicle (FCEV) Evaluation

    SciTech Connect (OSTI)

    Kurtz, Jennifer; Sprik, Sam; Ainscough, Chris; Saur, Genevieve

    2015-12-15

    Overview of NREL's fuel cell electric vehicle (FCEV) evaluation activities presented to the Interagency Working Group on December 15, 2015.

  13. 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)

  14. 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.

  15. 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.

  16. Spent Nuclear Fuel project, project management plan

    SciTech Connect (OSTI)

    Fuquay, B.J.

    1995-10-25

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

  17. Nuclear reactors and the nuclear fuel cycle

    SciTech Connect (OSTI)

    Pearlman, H

    1989-11-01

    According to the author, the first sustained nuclear fission chain reaction was not at the University of Chicago, but at the Oklo site in the African country of Gabon. Proof of this phenomenon is provided by mass spectrometric and analytical chemical measurements by French scientists. The U.S. experience in developing power-producing reactors and their related fuel and fuel cycles is discussed.

  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. 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.

  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. Cost and Quality of Fuels for Electric Utility Plants

    Gasoline and Diesel Fuel Update (EIA)

    1) Distribution Category UC-950 Cost and Quality of Fuels for Electric Utility Plants 2001 March 2004 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the

  2. 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.

  3. 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)

  4. FUEL ELEMENTS FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Blainey, A.; Lloyd, H.

    1961-07-11

    A method of sheathing a tubular fuel element for a nuclear reactor is described. A low melting metal core member is centered in a die, a layer of a powdered sheathing substance is placed on the bottom of the die, the tubular fuel element is inserted in the die, the space between the tubular fuel element and the die walls and core member is filled with the same powdered sheathing substance, a layer of the same substance is placed over the fissile material, and the charge within the die is subjected to pressure in the direction of the axis of the fuel element at the sintering temperature of the protective substance.

  5. 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.

  6. 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.

  7. Used Fuel Disposition Used Nuclear Fuel Storage and Transportation

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

    Used Nuclear Fuel Storage and Transportation Overview Steve Marschman Field Demonstration Lead Idaho National Laboratory NEET ASI Review Meeting September 17, 2014 Used Fuel ...

  8. 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)

  9. Electric Power Produced from Nuclear Reactor | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Electric Power Produced from Nuclear Reactor Electric Power Produced from Nuclear Reactor Arco, ID The Experimental Breeder Reactor No. 1 located at the National Reactor Testing ...

  10. NREL: Hydrogen and Fuel Cells Research - Fuel Cell Electric Vehicle

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

    Evaluations Fuel Cell Electric Vehicle Evaluations NREL's technology validation team analyzes hydrogen fuel cell electric vehicles (FCEVs) operating in a real-world setting to identify the current status of the technology, compare it to Department of Energy (DOE) performance and durability targets, and evaluate progress between multiple generations of technology, some of which will include commercial FCEVs for the first time. Current fuel cell electric vehicle evaluations build on the

  11. NMR data feature: 1995 world nuclear electricity production

    SciTech Connect (OSTI)

    1996-09-01

    World-wide nuclear electricity generation data is presented for 1995. Total nuclear power reactors in operation and under construction are listed for each country, along with MW(e) output totals and percentages of total electrical production. Detailed data is presented for the regions of Western Europe, Eastern Europe, and the Commonwealth of Independent States. This data includes electricity generation by source (fossil fuel, nuclear power, and hydro power and other), net electricity consumption, and percent changes since 1994. Very brief summaries of electricity production in Canada, the United States, and the Far East are also provided.

  12. NREL: Hydrogen and Fuel Cells Research - Fuel Cell Electric Bus...

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

    Fuel Cell Electric Bus Reliability Surpasses 2016 and Ultimate Technical Targets Project ... Applicable DOE Technical Target DOE and FTA have established performance, cost, and ...

  13. 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

  14. 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.

  15. Save Electricity and Fuel | Department of Energy

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

    use, purchase efficient products, save money on your electric bills, and buy or ... Learn about the following topics: Saving money on gas Buying and driving fuel efficient ...

  16. 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.

  17. Spent nuclear fuel reprocessing modeling

    SciTech Connect (OSTI)

    Tretyakova, S.; Shmidt, O.; Podymova, T.; Shadrin, A.; Tkachenko, V.; Makeyeva, I.; Tkachenko, V.; Verbitskaya, O.; Schultz, O.; Peshkichev, I.

    2013-07-01

    The long-term wide development of nuclear power requires new approaches towards the realization of nuclear fuel cycle, namely, closed nuclear fuel cycle (CNFC) with respect to fission materials. Plant nuclear fuel cycle (PNFC), which is in fact the reprocessing of spent nuclear fuel unloaded from the reactor and the production of new nuclear fuel (NF) at the same place together with reactor plant, can be one variant of CNFC. Developing and projecting of PNFC is a complicated high-technology innovative process that requires modern information support. One of the components of this information support is developed by the authors. This component is the programme conducting calculations for various variants of process flow sheets for reprocessing SNF and production of NF. Central in this programme is the blocks library, where the blocks contain mathematical description of separate processes and operations. The calculating programme itself has such a structure that one can configure the complex of blocks and correlations between blocks, appropriate for any given flow sheet. For the ready sequence of operations balance calculations are made of all flows, i.e. expenses, element and substance makeup, heat emission and radiation rate are determined. The programme is open and the block library can be updated. This means that more complicated and detailed models of technological processes will be added to the library basing on the results of testing processes using real equipment, in test operating mode. The development of the model for the realization of technical-economic analysis of various variants of technologic PNFC schemes and the organization of 'operator's advisor' is expected. (authors)

  18. 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)

  19. Fire resistant nuclear fuel cask

    DOE Patents [OSTI]

    Heckman, Richard C.; Moss, Marvin

    1979-01-01

    The disclosure is directed to a fire resistant nuclear fuel cask employing reversibly thermally expansible bands between adjacent cooling fins such that normal outward flow of heat is not interfered with, but abnormal inward flow of heat is impeded or blocked.

  20. 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.

  1. Pilot Application to Nuclear Fuel Cycle Options

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  2. 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)

  3. 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.

  4. 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.

  5. Alternative Fuels Data Center: Benefits and Considerations of Electricity

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    as a Vehicle Fuel Benefits and Considerations of Electricity as a Vehicle Fuel to someone by E-mail Share Alternative Fuels Data Center: Benefits and Considerations of Electricity as a Vehicle Fuel on Facebook Tweet about Alternative Fuels Data Center: Benefits and Considerations of Electricity as a Vehicle Fuel on Twitter Bookmark Alternative Fuels Data Center: Benefits and Considerations of Electricity as a Vehicle Fuel on Google Bookmark Alternative Fuels Data Center: Benefits and

  6. 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.

  7. Overview of Fuel Cell Electric Bus Development

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

    Overview of Fuel Cell Electric Bus Development Leslie Eudy, National Renewable Energy Laboratory September 12, 2013 2 Why Fuel Cells for Transit Buses? * Reduce transit bus emissions * Improve fuel efficiency * Improve vehicle performance * Consumer Acceptance * Transit industry is excellent test-bed for new technologies o Centrally fueled and maintained o Fixed routes with urban stop-go duty cycle o Professional operators and mechanics o Federal Capital Funding Support o High Visibility &

  8. Method for locating defective nuclear fuel elements

    SciTech Connect (OSTI)

    Lawrie, W.E.; White, N.W.; Womack, R.E.

    1982-02-02

    Defects in nuclear fuel elements are ascertained and located within an assembled fuel assembly by ultrasonic means. In a typical embodiment of the invention, an ultrasonic search unit is positioned within the fuel assembly opposite the lower plenum of the fuel element to be tested. An ultrasonic pulse is radially projected into the element. Defective fuel elements are ascertained by ultrasonic reflection measurements.

  9. 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.

  10. Method for producing nuclear fuel

    SciTech Connect (OSTI)

    Haas, P.A.

    1981-04-24

    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.

  11. 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.

  12. Proton Exchange Membrane Fuel Cells for Electrical Power Generation...

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

    Proton Exchange Membrane Fuel Cells for Electrical Power Generation On-Board Commercial Airplanes Proton Exchange Membrane Fuel Cells for Electrical Power Generation On-Board ...

  13. Hydrogen Fuel Cells and Electric Forklift Trucks | Department...

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

    Fuel Cells and Electric Forklift Trucks Hydrogen Fuel Cells and Electric Forklift Trucks Presentation for Dec. 17, 2008 hydrogen bimonthly informational call and meeting series for ...

  14. Alternative Fuels Data Center: Electric Vehicle Charging Stations

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

    Electric Vehicle Charging Stations to someone by E-mail Share Alternative Fuels Data Center: Electric Vehicle Charging Stations on Facebook Tweet about Alternative Fuels Data ...

  15. Curium concentration in spent nuclear fuel

    SciTech Connect (OSTI)

    Beddingfield, D. H.; Swinhoe, M. T.

    2004-01-01

    Neutron measurements are frequently used to characterize spent nuclear fuel. Curium is the primary neutron source from most spent nuclear fuel materials. Recent developments in nuclear safeguards measurements of spent nuclear fuel have increased the reliance upon curium assay for materials accounting on the back end of the fuel cycle. The curium assay is used to determine the fuel composition by the curium-ratio technique. The interpretation of these measurements is based upon the results of calculations using depletion codes. In this paper we will examine depletion code results to determine if there is reason for concern for the reliability of curium concentration from calculation.

  16. Fuel Savings from Hybrid Electric Vehicles

    SciTech Connect (OSTI)

    Bennion, K.; Thornton, M.

    2009-03-01

    NREL's study shows that hybrid electric vehicles can significantly reduce oil imports for use in light-duty vehicles, particularly if drivers switch to smaller, more fuel-efficient vehicles overall.

  17. 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. ...

  18. INFOGRAPHIC: The Fuel Cell Electric Vehicle | Department of Energy

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

    INFOGRAPHIC: The Fuel Cell Electric Vehicle INFOGRAPHIC: The Fuel Cell Electric Vehicle INFOGRAPHIC: The Fuel Cell Electric Vehicle This infographic shows how fuel cell electric vehicles (FCEVs) work and some of the benefits of FCEVs, such as how they reduce greenhouse gas emissions, emit only water, and operate efficiently. INFOGRAPHIC: The Fuel Cell Electric Vehicle (FCEV) (497.65 KB) More Documents & Publications Amped Up! Volume 1, No. 4: The Transportation Issue Fuel Cell Technologies

  19. FUEL ELEMENT FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Bassett, C.H.

    1961-07-11

    Nuclear reactor fuel elements of the type in which the flssionsble material is in ceramic form, such as uranium dioxide, are described. The fuel element is comprised of elongated inner and outer concentric spaced tubular members providing an annular space therebetween for receiving the fissionable material, the annular space being closed at both ends and the inner tube being open at both ends. The fuel is in the form of compressed pellets of ceramic fissionsble material having the configuration of split bushings formed with wedge surfaces and arranged in seriated inner and outer concentric groups which are urged against the respective tubes in response to relative axial movement of the pellets in the direction toward each other. The pairs of pellets are axially urged together by a resilient means also enclosed within the annulus. This arrangement-permits relative axial displacement of the pellets during use dial stresses on the inner and outer tube members and yet maintains the fuel pellets in good thermal conductive relationship therewith.

  20. Carbon pricing, nuclear power and electricity markets

    SciTech Connect (OSTI)

    Cameron, R.; Keppler, J. H.

    2012-07-01

    In 2010, the NEA in conjunction with the International Energy Agency produced an analysis of the Projected Costs of Electricity for almost 200 power plants, covering nuclear, fossil fuel and renewable electricity generation. That analysis used lifetime costs to consider the merits of each technology. However, the lifetime cost analysis is less applicable in liberalised markets and does not look specifically at the viewpoint of the private investor. A follow-up NEA assessment of the competitiveness of nuclear energy against coal- and gas-fired generation under carbon pricing has considered just this question. The economic competition in electricity markets is today between nuclear energy and gas-fired power generation, with coal-fired power generation not being competitive as soon as even modest carbon pricing is introduced. Whether nuclear energy or natural gas comes out ahead in their competition depends on a number of assumptions, which, while all entirely reasonable, yield very different outcomes. The analysis in this study has been developed on the basis of daily data from European power markets over the last five-year period. Three different methodologies, a Profit Analysis looking at historic returns over the past five years, an Investment Analysis projecting the conditions of the past five years over the lifetime of plants and a Carbon Tax Analysis (differentiating the Investment Analysis for different carbon prices) look at the issue of competitiveness from different angles. They show that the competitiveness of nuclear energy depends on a number of variables which in different configurations determine whether electricity produced from nuclear power or from CCGTs generates higher profits for its investors. These are overnight costs, financing costs, gas prices, carbon prices, profit margins (or mark-ups), the amount of coal with carbon capture and electricity prices. This paper will present the outcomes of the analysis in the context of a liberalised

  1. 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.

  2. Infographic: The Fuel Cell Electric Vehicle (FCEV)

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

    The Fuel Cell Electric Vehicle (FCEV) FCEVs are available now in southern California and coming soon to a neighborhood near you. as fuel cells can be added to the stack to increase power Scales Up Easily Gasoline H₂ from natural gas H₂ from Wind even at highway speeds, since there are no mechanical gears or combustion Runs Quietly from the tailpipe Emits Only Water * natural gas * water (electrolysis) * biomass * waste products Uses Domestic Fuel Reduces Greenhouse Gas Emissions 50% 90%

  3. Hydrogen Fuel Cells and Electric Forklift Trucks

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

    Fuel Cells and Electric Forklift Trucks Steve Medwin The Raymond Corporation December 10, 2008 Value Proposition and Fuel Cell Tax Credit * Federal fuel cell tax credit increased in "Bailout Bill" - $3000/kW or 30% of unit price whichever is less * Tax credits extended to 2016 * Has a significant impact on financial viability Sample Financial Analysis * Illustrate impact of key factors on value proposition - Tax credit - Labor rate - Battery change time - Productivity improvement *

  4. Alternative Fuels Data Center: Plug-In Hybrid Electric Vehicles

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Plug-In Hybrid Electric Vehicles to someone by E-mail Share Alternative Fuels Data Center: Plug-In Hybrid Electric Vehicles on Facebook Tweet about Alternative Fuels Data Center: Plug-In Hybrid Electric Vehicles on Twitter Bookmark Alternative Fuels Data Center: Plug-In Hybrid Electric Vehicles on Google Bookmark Alternative Fuels Data Center: Plug-In Hybrid Electric Vehicles on Delicious Rank Alternative Fuels Data Center: Plug-In Hybrid Electric Vehicles on Digg Find More places to share

  5. Alternative Fuels Data Center: Electric Vehicle Charging Station Locations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electric Vehicle Charging Station Locations to someone by E-mail Share Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Facebook Tweet about Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Twitter Bookmark Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Google Bookmark Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Delicious Rank Alternative Fuels Data Center: Electric Vehicle

  6. Alternative Fuels Data Center: Electricity Research and Development

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electricity Research and Development to someone by E-mail Share Alternative Fuels Data Center: Electricity Research and Development on Facebook Tweet about Alternative Fuels Data Center: Electricity Research and Development on Twitter Bookmark Alternative Fuels Data Center: Electricity Research and Development on Google Bookmark Alternative Fuels Data Center: Electricity Research and Development on Delicious Rank Alternative Fuels Data Center: Electricity Research and Development on Digg Find

  7. Alternative Fuels Data Center: Rental Cars Go Electric in Florida

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Rental Cars Go Electric in Florida to someone by E-mail Share Alternative Fuels Data Center: Rental Cars Go Electric in Florida on Facebook Tweet about Alternative Fuels Data Center: Rental Cars Go Electric in Florida on Twitter Bookmark Alternative Fuels Data Center: Rental Cars Go Electric in Florida on Google Bookmark Alternative Fuels Data Center: Rental Cars Go Electric in Florida on Delicious Rank Alternative Fuels Data Center: Rental Cars Go Electric in Florida on Digg Find More places to

  8. Model documentation: Electricity Market Module, Electricity Fuel Dispatch Submodule

    SciTech Connect (OSTI)

    Not Available

    1994-04-08

    This report documents the objectives, analytical approach and development of the National Energy Modeling System Electricity Fuel Dispatch Submodule (EFD), a submodule of the Electricity Market Module (EMM). The report catalogues and describes the model assumptions, computational methodology, parameter estimation techniques, model source code, and forecast results generated through the synthesis and scenario development based on these components.

  9. Nuclear Fuel Cycle | Department of Energy

    Office of Environmental Management (EM)

    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. ...

  10. Fuel Cell and Battery Electric Vehicles Compared | Department of Energy

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

    and Battery Electric Vehicles Compared Fuel Cell and Battery Electric Vehicles Compared Presented by Sandy Thomas at the National Hydrogen Assocation Conference and Hydrogen Expo thomas_fcev_vs_battery_evs.pdf (281 KB) More Documents & Publications An Energy Evolution:Alternative Fueled Vehicle Comparisons Fuel Cell and Battery Electric Vehicles Compared INFOGRAPHIC: The Fuel Cell Electric Vehicle Asia/ITS

  11. 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.

  12. Used Fuel Disposition Used Nuclear Fuel Storage and Transportation

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

    Used Nuclear Fuel 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. Tennessee 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","3,401",15.9,"27,739",33.7 "Coal","8,805",41.1,"43,670",53.0 "Hydro and Pumped

  11. Texas 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","4,966",4.6,"41,335",10.0 "Coal","22,335",20.6,"150,173",36.5 "Hydro and Pumped Storage",689,0.6,"1,262",0.3

  12. Alternative Fuels Data Center: Federal Laws and Incentives for Electricity

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electricity Printable Version Share this resource Send a link to Alternative Fuels Data Center: Federal Laws and Incentives for Electricity to someone by E-mail Share Alternative Fuels Data Center: Federal Laws and Incentives for Electricity on Facebook Tweet about Alternative Fuels Data Center: Federal Laws and Incentives for Electricity on Twitter Bookmark Alternative Fuels Data Center: Federal Laws and Incentives for Electricity on Google Bookmark Alternative Fuels Data Center: Federal Laws

  13. Alternative Fuels Data Center: Sacramento Powers up with Electric Vehicles

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Sacramento Powers up with Electric Vehicles to someone by E-mail Share Alternative Fuels Data Center: Sacramento Powers up with Electric Vehicles on Facebook Tweet about Alternative Fuels Data Center: Sacramento Powers up with Electric Vehicles on Twitter Bookmark Alternative Fuels Data Center: Sacramento Powers up with Electric Vehicles on Google Bookmark Alternative Fuels Data Center: Sacramento Powers up with Electric Vehicles on Delicious Rank Alternative Fuels Data Center: Sacramento Powers

  14. NREL: Hydrogen and Fuel Cells Research - Hydrogen Fuel Cell Electric

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

    Vehicle Learning Demonstration Fuel Cell Electric Vehicle Learning Demonstration Delve deeper into real-world performance data with our Interactive Composite Data Product demo Graphical thumbnail of the Interactive Composite Data Product demo map. Learn More Subscribe to the biannual Fuel Cell and Hydrogen Technology Validation newsletter, which highlights recent technology validation activities at NREL. Initiated in 2004, DOE's Controlled Hydrogen Fleet and Infrastructure Demonstration and

  15. 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.

  16. Fuel Cell and Battery Electric Vehicles Compared

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

    Level PHEVs Fuel Cell and Battery Electric Vehicles Compared By C. E. (Sandy) Thomas, Ph.D., President H 2 Gen Innovations, Inc. Alexandria, Virginia Thomas@h2gen.com 1.0 Introduction Detailed computer simulations demonstrate that all-electric vehicles will be required to meet our energy security and climate change reduction goals 1 . As shown in Figure 1, hybrid electric vehicles (HEV's) and plug-in hybrid electric vehicles (PHEV's) both reduce greenhouse gas (GHG) emissions, but neither of

  17. 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)

  18. 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.

  19. Cost and Quality of Fuels for Electric Utility Plants 1997

    Gasoline and Diesel Fuel Update (EIA)

    7 Tables May 1998 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. Energy Information Administration/Cost

  20. Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister

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

    System - Energy Innovation Portal Storage Energy Storage Electricity Transmission Electricity Transmission Advanced Materials Advanced Materials Find More Like This Return to Search Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister System Oak Ridge National Laboratory Contact ORNL About This Technology Publications: PDF Document Publication 11-G00239_ID2603 (2).pdf (847 KB) Technology Marketing Summary Researchers at ORNL have developed an integrated system that

  1. 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.

  2. 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

  3. Alternative Fuels Data Center: Hybrid Electric Horsepower for Kentucky

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Schools Hybrid Electric Horsepower for Kentucky Schools to someone by E-mail Share Alternative Fuels Data Center: Hybrid Electric Horsepower for Kentucky Schools on Facebook Tweet about Alternative Fuels Data Center: Hybrid Electric Horsepower for Kentucky Schools on Twitter Bookmark Alternative Fuels Data Center: Hybrid Electric Horsepower for Kentucky Schools on Google Bookmark Alternative Fuels Data Center: Hybrid Electric Horsepower for Kentucky Schools on Delicious Rank Alternative

  4. Alternative Fuels Data Center: New York Broadens Network for Electric

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Vehicle Charging New York Broadens Network for Electric Vehicle Charging to someone by E-mail Share Alternative Fuels Data Center: New York Broadens Network for Electric Vehicle Charging on Facebook Tweet about Alternative Fuels Data Center: New York Broadens Network for Electric Vehicle Charging on Twitter Bookmark Alternative Fuels Data Center: New York Broadens Network for Electric Vehicle Charging on Google Bookmark Alternative Fuels Data Center: New York Broadens Network for Electric

  5. Alternative Fuels Data Center: Oregon Celebrates 200 Miles of Electric

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Highways Oregon Celebrates 200 Miles of Electric Highways to someone by E-mail Share Alternative Fuels Data Center: Oregon Celebrates 200 Miles of Electric Highways on Facebook Tweet about Alternative Fuels Data Center: Oregon Celebrates 200 Miles of Electric Highways on Twitter Bookmark Alternative Fuels Data Center: Oregon Celebrates 200 Miles of Electric Highways on Google Bookmark Alternative Fuels Data Center: Oregon Celebrates 200 Miles of Electric Highways on Delicious Rank

  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. 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...

  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. 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 ...

  11. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown...

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

    Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites Prepared for U.S. ... Evaluation of Removing Used Nuclear Fuel from Shutdown Sites October 1, 2014 iii ...

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

    Office of Scientific and Technical Information (OSTI)

    Fundamental aspects of nuclear reactor fuel elements: solutions to problems Citation Details In-Document Search Title: Fundamental aspects of nuclear reactor fuel elements: ...

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

    Office of Scientific and Technical Information (OSTI)

    Fundamental aspects of nuclear reactor fuel elements Citation Details In-Document Search Title: Fundamental aspects of nuclear reactor fuel elements You are accessing a document ...

  14. EIS-0279: Spent Nuclear Fuel Management, Aiken, South Carolina...

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

    79: Spent Nuclear Fuel Management, Aiken, South Carolina EIS-0279: Spent Nuclear Fuel ... Carolina, including placing these materials in forms suitable for ultimate disposition. ...

  15. 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)...

  16. 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 ...

  17. Economic Impacts Associated With Commercializing Fuel Cell Electric...

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

    with commercializing fuel cell electric vehicles (FCEVs) in California. Successful implementation of the California Road Map for the introduction of hydrogen fueling stations to ...

  18. Highlighting Hydrogen: Hawaii's Success with Fuel Cell Electric...

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

    Highlighting Hydrogen: Hawaii's Success with Fuel Cell Electric Vehicles Offers Opportunity Nationwide ... so innovative ways of building cost-effective hydrogen fueling stations ...

  19. Webinar: BNL's Low-Platinum Electrocatalysts for Fuel Cell Electric...

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

    Webinar: BNL's Low-Platinum Electrocatalysts for Fuel Cell Electric Vehicles (FCEVs) Above is the video recording for the webinar, "BNL's Low-Platinum Electrocatalysts for Fuel ...

  20. New Nuclear Fuel Disposition Opportunities in a Changed World

    SciTech Connect (OSTI)

    Barrett, L.H.

    2006-07-01

    The world's economic, security, environmental, and technological situation has changed significantly in the last several years and these changes bring new opportunities for substantial policy improvements and redirections in the used nuclear fuel management arena. The passage of new energy legislation; the need for more US nuclear energy; growing state, national and international momentum for carbon emission and other air pollutant reductions; post September 11. Homeland Security threat reduction improvements; desires to improve global nuclear security; rapidly emerging needs for clean electricity supplies in developing countries; and the technological advancements in advanced fuel cycle technologies provide a substantial foundation for future enhancements and improvements in current used nuclear fuel management programs. Past progress, lessons learned, and new used fuel/waste management technological innovations coupled with current and future economic, security, and environmental issues can create new approaches that can help the Federal government meet its obligations while simultaneously addressing many of the difficult regional/state issues that have historically hindered progress. This paper will examine and integrate the synergy of these issues to explore options and discuss possible new opportunities in the vitally important area of spent fuel management and the entire back end of the nuclear fuel cycle. (authors)

  1. Hydrogen Fuel Cell Electric Vehicles (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-02-01

    As nations around the world pursue a variety of sustainable transportation solutions, the hydrogen fuel cell electric vehicle (FCEV) presents a promising opportunity for American consumers and automakers. FCEVs offer a sustainable transportation option, provide a cost-competitive alternative for drivers, reduce dependence on imported oil, and enable global economic leadership and job growth.

  2. 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.

  3. CONSTRUCTION OF NUCLEAR FUEL ELEMENTS

    DOE Patents [OSTI]

    Weems, S.J.

    1963-09-24

    >A rib arrangement and an end construction for nuclearfuel elements laid end to end in a coolant tube are described. The rib arrangement is such that each fuel element, when separated from other fuel elements, fits loosely in the coolant tube and so can easily be inserted or withdrawn from the tube. The end construction of the fuel elements is such that the fuel elements when assembled end to end are keyed against relative rotation, and the ribs of each fuel element cooperate with the ribs of the adjacent fuel elements to give the assembled fuel elements a tight fit with the coolant tube. (AEC)

  4. Spent Nuclear Fuel (SNF) Removal Campaign Plan

    SciTech Connect (OSTI)

    PAJUNEN, A.L.

    2000-08-07

    The overall operation of the Spent Nuclear Fuel Project will include fuel removal, sludge removal, debris removal, and deactivation transition activities. Figure 1-1 provides an overview of the current baseline operating schedule for project sub-systems, indicating that a majority of fuel removal activities are performed over an approximately three-and-one-half year time period. The purpose of this document is to describe the strategy for operating the fuel removal process systems. The campaign plan scope includes: (1) identifying a fuel selection sequence during fuel removal activities, (2) identifying MCOs that are subjected to extra testing (process validation) and monitoring, and (3) discussion of initial MCO loading and monitoring in the Canister Storage Building (CSB). The campaign plan is intended to integrate fuel selection requirements for handling special groups of fuel within the basin (e.g., single pass reactor fuel), process validation activities identified for process systems, and monitoring activities during storage.

  5. 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.

  6. 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.

  7. 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;...

  8. LWR nuclear fuel bundle data for use in fuel bundle handling...

    Office of Scientific and Technical Information (OSTI)

    LWR nuclear fuel bundle data for use in fuel bundle handling Citation Details In-Document Search Title: LWR nuclear fuel bundle data for use in fuel bundle handling You are ...

  9. 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.

  10. 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.

  11. National Fuel Cell Electric Vehicle Learning Demonstration Final...

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

    Electric Vehicle Learning Demonstration Final Report National Fuel Cell Electric Vehicle Learning Demonstration Final Report This report discusses key analysis results based on ...

  12. Nuclear Fuels Storage & Transportation Planning Project Documents |

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

    Department of Energy Fuel Cycle Technologies » Nuclear Fuels Storage & Transportation Planning Project » Nuclear Fuels Storage & Transportation Planning Project Documents Nuclear Fuels Storage & Transportation Planning Project Documents October 1, 2014 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

  13. First Commercially Available Fuel Cell Electric Vehicles Hit the Street |

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

    Department of Energy First Commercially Available Fuel Cell Electric Vehicles Hit the Street First Commercially Available Fuel Cell Electric Vehicles Hit the Street December 10, 2014 - 12:25pm Addthis A fuel cell electric vehicle (FCEV) at a fueling station in California. New Energy Department reports signal rapid growth in America’s fuel cell and hydrogen industry as FCEVs are introduced to the market. | Energy Department photo A fuel cell electric vehicle (FCEV) at a fueling station

  14. 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.

  15. 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

  16. 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.

  17. 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.

  18. 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

  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. Composite construction for nuclear fuel containers

    DOE Patents [OSTI]

    Cheng, Bo-Ching [Fremont, CA; Rosenbaum, Herman S [Fremont, CA; Armijo, Joseph S [Saratoga, CA

    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.

  1. 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.

  2. 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.

  3. Spent Nuclear Fuel Project Technical Databook

    SciTech Connect (OSTI)

    Reilly, M.A.

    1998-10-23

    The Spent Nuclear Fuel (SNF) Project Technical Databook is developed for use as a common authoritative source of fuel behavior and material parameters in support of the Hanford SNF Project. The Technical Databook will be revised as necessary to add parameters as their Databook submittals become available.

  4. 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.

  5. 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.

  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. Emissions of greenhouse gases from the use of transportation fuels and electricity

    SciTech Connect (OSTI)

    DeLuchi, M.A. )

    1991-11-01

    This report presents estimates of full fuel-cycle emissions of greenhouse gases from using transportation fuels and electricity. The data cover emissions of carbon dioxide (CO{sub 2}), methane, carbon monoxide, nitrous oxide, nitrogen oxides, and nonmethane organic compounds resulting from the end use of fuels, compression or liquefaction of gaseous transportation fuels, fuel distribution, fuel production, feedstock transport, feedstock recovery, manufacture of motor vehicles, maintenance of transportation systems, manufacture of materials used in major energy facilities, and changes in land use that result from using biomass-derived fuels. The results for electricity use are in grams of CO{sub 2}-equivalent emissions per kilowatt-hour of electricity delivered to end users and cover generating plants powered by coal, oil, natural gas, methanol, biomass, and nuclear energy. The transportation analysis compares CO{sub 2}-equivalent emissions, in grams per mile, from base-case gasoline and diesel fuel cycles with emissions from these alternative- fuel cycles: methanol from coal, natural gas, or wood; compressed or liquefied natural gas; synthetic natural gas from wood; ethanol from corn or wood; liquefied petroleum gas from oil or natural gas; hydrogen from nuclear or solar power; electricity from coal, uranium, oil, natural gas, biomass, or solar energy, used in battery-powered electric vehicles; and hydrogen and methanol used in fuel-cell vehicles.

  8. Emissions of greenhouse gases from the use of transportation fuels and electricity. Volume 1, Main text

    SciTech Connect (OSTI)

    DeLuchi, M.A.

    1991-11-01

    This report presents estimates of full fuel-cycle emissions of greenhouse gases from using transportation fuels and electricity. The data cover emissions of carbon dioxide (CO{sub 2}), methane, carbon monoxide, nitrous oxide, nitrogen oxides, and nonmethane organic compounds resulting from the end use of fuels, compression or liquefaction of gaseous transportation fuels, fuel distribution, fuel production, feedstock transport, feedstock recovery, manufacture of motor vehicles, maintenance of transportation systems, manufacture of materials used in major energy facilities, and changes in land use that result from using biomass-derived fuels. The results for electricity use are in grams of CO{sub 2}-equivalent emissions per kilowatt-hour of electricity delivered to end users and cover generating plants powered by coal, oil, natural gas, methanol, biomass, and nuclear energy. The transportation analysis compares CO{sub 2}-equivalent emissions, in grams per mile, from base-case gasoline and diesel fuel cycles with emissions from these alternative- fuel cycles: methanol from coal, natural gas, or wood; compressed or liquefied natural gas; synthetic natural gas from wood; ethanol from corn or wood; liquefied petroleum gas from oil or natural gas; hydrogen from nuclear or solar power; electricity from coal, uranium, oil, natural gas, biomass, or solar energy, used in battery-powered electric vehicles; and hydrogen and methanol used in fuel-cell vehicles.

  9. FUEL ELEMENT FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Dickson, J.J.

    1963-09-24

    A method is described whereby fuel tubes or pins are cut, loaded with fuel pellets and a heat transfer medium, sealed at each end with slotted fittings, and assembled into a rectangular tube bundle to form a fuel element. The tubes comprising the fuel element are laterally connected between their ends by clips and tabs to form a linear group of spaced parallel tubes, which receive their vertical support by resting on a grid. The advantages of this method are that it permits elimination of structural material (e.g., fuel-element cans) within the reactor core, and removal of at least one fuel pin from an element and replacement thereof so that a burnable poison may be utilized during the core lifetime. (AEC)

  10. Major Fuels","Electricity","Natural Gas","Fuel Oil","District...

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

    (million square feet)","Total of Major Fuels","Electricity","Natural Gas","Fuel Oil","District Heat" "All Buildings ...",4657,67338,81552,66424,10...

  11. "Characteristic(a)","Electricity","Fuel Oil","Fuel Oil(b)","Natural...

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

    " Unit: Percents." " ",," "," ",," "," " "Economic",,"Residual","Distillate",,"LPG and" "Characteristic(a)","Electricity","Fuel Oil","Fuel Oil(b)","Natural Gas(c)","NGL(d)","Coal

  12. "Economic","Electricity","Fuel Oil","Fuel Oil(b)","Natural Gas...

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

    "," ",," "," " ,,"Residual","Distillate",,"LPG and" "Economic","Electricity","Fuel Oil","Fuel Oil(b)","Natural Gas(c)","NGL(d)","Coal" "Characteristic(a)","(kWh)","(gallons)","...

  13. Major Fuels","Electricity",,"Natural Gas","Fuel Oil","District

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

    of Buildings (thousand)","Floorspace (million square feet)","Sum of Major Fuels","Electricity",,"Natural Gas","Fuel Oil","District Heat" ,,,,"Primary","Site" "All Buildings...

  14. Vermont Nuclear Profile - All Fuels

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

    components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable." "- No data reported." "Notes: Totals may not equal sum of ...

  15. Kansas Nuclear Profile - All Fuels

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

    components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable." "* Absolute percentage less than 0.05." "Notes: Totals may not ...

  16. Washington Nuclear Profile - All Fuels

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

    components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable." "* Absolute percentage less than 0.05." "- No data reported." ...

  17. Virginia Nuclear Profile - All Fuels

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

    components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable." "* Absolute percentage less than 0.05." "- No data reported." ...

  18. Iowa Nuclear Profile - All Fuels

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

    components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable." "Notes: Totals may not equal sum of components due to independent ...

  19. Wisconsin Nuclear Profile - All Fuels

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

    components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable." "Notes: Totals may not equal sum of components due to independent ...

  20. 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.

  1. fuel | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    fuel Cheaper catalyst may lower fuel costs for hydrogen-powered cars Sandia National Laboratories post-doctoral fellow Stan Chou demonstrates the reaction of more efficiently catalyzing hydrogen. In this simulation, the color is from dye excited by light and generating electrons for the catalyst molybdenum disulfide to evolve hydrogen. ALBUQUERQUE, N.M. -Sandia

  2. 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.

  3. 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.

  4. 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.

  5. Highlighting Hydrogen: Hawaii's Success with Fuel Cell Electric Vehicles

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

    Offers Opportunity Nationwide | Department of Energy Highlighting Hydrogen: Hawaii's Success with Fuel Cell Electric Vehicles Offers Opportunity Nationwide Highlighting Hydrogen: Hawaii's Success with Fuel Cell Electric Vehicles Offers Opportunity Nationwide September 11, 2014 - 2:38pm Addthis A fuel cell electric vehicle (FCEV) in Hawaii. Engineers from Idaho National Laboratory and National Renewable Energy Laboratory identified a new way to launch economically viable hydrogen fueling

  6. 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 Energy Defense Waste Management Programs

  7. 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.

  8. 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.

  9. Nuclear Fuel Cycle Options Catalog

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

    Nuclear Security Administration | (NNSA) Nuclear Facility Risk Reduction project moves forward at Y-12 December 02, 2011 OAK RIDGE, Tenn. - The Y-12 National Security Complex has received final approval for a $76 million project that aims to maintain decades-old equipment - some dating to World War II - until the site constructs a new facility to ensure that the nation has essential uranium processing capability long-term. The Nuclear Facility Risk Reduction (NFRR) project includes two Y-12

  10. Interdisciplinary Engineer (Electrical/Electronics/Nuclear/Computer)

    Broader source: Energy.gov [DOE]

    THIS IS AN INTERDISCIPLINARY POSITION AND MAY BE FILLED WITH ANY OF THE FOLLOWING OCCUPATIONS: Electrical Engineer, GS-0850-13 Electronics Engineer, GS-0855-13 Nuclear Engineer, GS-0840-13 Computer...

  11. Interdisciplinary Engineer (Electrical/Electronics/Nuclear/Computer)

    Broader source: Energy.gov [DOE]

    THIS IS AN INTERDISCIPLINARY POSITION AND MAY BE FILLED WITH ANY OF THE FOLLOWING OCCUPATIONS: Electrical Engineer, GS-0850-12 Electronics Engineer, GS-0855-12 Nuclear Engineer, GS-0840-12 Computer...

  12. Advanced LWR Nuclear Fuel Development

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

    ... through LWRS program funding and industry cost-sharing. * Coordinate project development among research organizations associated with the U.S commercial nuclear industry, to the ...

  13. 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.

  14. 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.

  15. Cost and Quality of Fuels for Electric Utility Plants 2000 Tables

    Gasoline and Diesel Fuel Update (EIA)

    0) Distribution Category UC-950 Cost and Quality of Fuels for Electric Utility Plants 2000 Tables August 2001 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position

  16. Electric and Gasoline Vehicle Fuel Efficiency Analysis

    Energy Science and Technology Software Center (OSTI)

    1995-05-24

    EAGLES1.1 is PC-based interactive software for analyzing performance (e.g., maximum range) of electric vehicles (EVs) or fuel economy (e.g., miles/gallon) of gasoline vehicles (GVs). The EV model provides a second by second simulation of battery voltage and current for any specified vehicle velocity/time or power/time profile. It takes into account the effects of battery depth-of-discharge (DOD) and regenerative braking. The GV fuel economy model which relates fuel economy, vehicle parameters, and driving cycle characteristics, canmore » be used to investigate the effects of changes in vehicle parameters and driving patterns on fuel economy. For both types of vehicles, effects of heating/cooling loads on vehicle performance can be studied. Alternatively, the software can be used to determine the size of battery needed to satisfy given vehicle mission requirements (e.g., maximum range and driving patterns). Options are available to estimate the time necessary for a vehicle to reach a certain speed with the application of a specified constant power and to compute the fraction of time and/or distance in a drivng cycle for speeds exceeding a given value.« less

  17. 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.

  18. 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.

  19. 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.

  20. 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

  1. Spent nuclear fuel project integrated schedule plan

    SciTech Connect (OSTI)

    Squires, K.G.

    1995-03-06

    The Spent Nuclear Fuel Integrated Schedule Plan establishes the organizational responsibilities, rules for developing, maintain and status of the SNF integrated schedule, and an implementation plan for the integrated schedule. The mission of the SNFP on the Hanford site is to provide safe, economic, environmentally sound management of Hanford SNF in a manner which stages it to final disposition. This particularly involves K Basin fuel.

  2. 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.

  3. 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.

  4. Arizona Nuclear Profile - All Fuels

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

    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 ...

  5. Maryland Nuclear Profile - All Fuels

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

    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 ...

  6. Mississippi Nuclear Profile - All Fuels

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

    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 ...

  7. Pennsylvania Nuclear Profile - All Fuels

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

    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 ...

  8. Connecticut Nuclear Profile - All Fuels

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

    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 ...

  9. Illinois Nuclear Profile - All Fuels

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

    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 ...

  10. Iowa Nuclear Profile - All Fuels

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

    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 ...

  11. Louisiana Nuclear Profile - All Fuels

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

    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 ...

  12. Michigan Nuclear Profile - All Fuels

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

    total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,947",13.2,"29,625",26.6 "Coal","11,531",38.7,"65,604",58.8 "Hydro and Pumped ...

  13. Missouri Nuclear Profile - All Fuels

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

    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 ...

  14. Ohio Nuclear Profile - All Fuels

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

    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 ...

  15. Vermont Nuclear Profile - All Fuels

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

    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 ...

  16. Wisconsin Nuclear Profile - All Fuels

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

    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 ...

  17. Arkansas Nuclear Profile - All Fuels

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

    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 ...

  18. Minnesota Nuclear Profile - All Fuels

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

    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 ...

  19. Florida Nuclear Profile - All Fuels

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

    total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,924",6.6,"23,936",10.4 "Coal","9,975",16.9,"59,897",26.1 "Hydro and Pumped ...

  20. 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 ...

  1. Virginia Nuclear Profile - All Fuels

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

    total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,501",14.5,"26,572",36.4 "Coal","5,868",24.3,"25,459",34.9 "Hydro and Pumped ...

  2. Massachusetts Nuclear Profile - All Fuels

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

    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 ...

  3. 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 ...

  4. Washington Nuclear Profile - All Fuels

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

    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 ...

  5. Nebraska Nuclear Profile - All Fuels

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

    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 ...

  6. Georgia Nuclear Profile - All Fuels

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

    total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,061",11.1,"33,512",24.4 "Coal","13,230",36.1,"73,298",53.3 "Hydro and Pumped ...

  7. California Nuclear Profile - All Fuels

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

    total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,390",6.5,"32,201",15.8 "Coal",374,0.6,"2,100",1.0 "Hydro and Pumped ...

  8. Kansas Nuclear Profile - All Fuels

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

    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 ...

  9. Alabama Nuclear Profile - All Fuels

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

    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 ...

  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. 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.

  13. Nuclear Fuels Storage and Transportation Planning Project (NFST...

    Office of Environmental Management (EM)

    Fuels Storage and Transportation Planning Project (NFST) Program Status Nuclear Fuels Storage and Transportation Planning Project (NFST) Program Status Presentation made by Jeff ...

  14. RAIL ROUTING - CURRENT PRACTICES FOR SPENT NUCLEAR FUEL AND HIGH...

    Office of Environmental Management (EM)

    Two types of highly radioactive materials are spent nuclear fuel and high-level radioactive waste that resulted from reprocessing spent fuel. Transportation of these radioactive ...

  15. 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)

  16. 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.

  17. OECD/NEA Ongoing activities related to the nuclear fuel cycle

    SciTech Connect (OSTI)

    Cornet, S.M.; McCarthy, K.; Chauvin, N.

    2013-07-01

    As part of its role in encouraging international collaboration, the OECD Nuclear Energy Agency is coordinating a series of projects related to the Nuclear Fuel Cycle. The Nuclear Science Committee (NSC) Working Party on Scientific Issues of the Nuclear Fuel Cycle (WPFC) comprises five different expert groups covering all aspects of the fuel cycle from front to back-end. Activities related to fuels, materials, physics, separation chemistry, and fuel cycles scenarios are being undertaken. By publishing state-of-the-art reports and organizing workshops, the groups are able to disseminate recent research advancements to the international community. Current activities mainly focus on advanced nuclear systems, and experts are working on analyzing results and establishing challenges associated to the adoption of new materials and fuels. By comparing different codes, the Expert Group on Advanced Fuel Cycle Scenarios is aiming at gaining further understanding of the scientific issues and specific national needs associated with the implementation of advanced fuel cycles. At the back end of the fuel cycle, separation technologies (aqueous and pyrochemical processing) are being assessed. Current and future activities comprise studies on minor actinides separation and post Fukushima studies. Regular workshops are also organized to discuss recent developments on Partitioning and Transmutation. In addition, the Nuclear Development Committee (NDC) focuses on the analysis of the economics of nuclear power across the fuel cycle in the context of changes of electricity markets, social acceptance and technological advances and assesses the availability of the nuclear fuel and infrastructure required for the deployment of existing and future nuclear power. The Expert Group on the Economics of the Back End of the Nuclear Fuel Cycle (EBENFC), in particular, is looking at assessing economic and financial issues related to the long term management of spent nuclear fuel. (authors)

  18. Webinar: BNL's Low-Platinum Electrocatalysts for Fuel Cell Electric

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

    Vehicles (FCEVs) | Department of Energy BNL's Low-Platinum Electrocatalysts for Fuel Cell Electric Vehicles (FCEVs) Webinar: BNL's Low-Platinum Electrocatalysts for Fuel Cell Electric Vehicles (FCEVs) Above is the video recording for the webinar, "BNL's Low-Platinum Electrocatalysts for Fuel Cell Electric Vehicles (FCEVs)," originally held on June 19, 2012. In addition to this recording, you can access the presentation slides. A text version of this recording will be available soon

  19. Hyundai Tucson Fuel Cell Electric Vehicle visits Department of Energy |

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

    Department of Energy Hyundai Tucson Fuel Cell Electric Vehicle visits Department of Energy Hyundai Tucson Fuel Cell Electric Vehicle visits Department of Energy September 26, 2014 - 3:34pm Addthis Deputy Secretary Daniel Poneman test drove the Hyundai Tucson Fuel Cell vehicle when the car made an appearance at the Department of Energy headquarters in Washington, D.C. Deputy Secretary Daniel Poneman test drove the Hyundai Tucson Fuel Cell vehicle when the car made an appearance at the

  20. Proton Exchange Membrane Fuel Cells for Electrical Power Generation

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

    On-Board Commercial Airplanes | Department of Energy Proton Exchange Membrane Fuel Cells for Electrical Power Generation On-Board Commercial Airplanes Proton Exchange Membrane Fuel Cells for Electrical Power Generation On-Board Commercial Airplanes This report, prepared by Sandia National Laboratories, is an initial investigation of the use of proton exchange membrane (PEM) fuel cells on-board commercial aircraft. The report examines whether on-board airplane fuel cell systems are

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

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

    in Support of a Comprehensive National Nuclear Fuel Cycle Strategy Categorization of Used Nuclear ... of research, development, demonstration, and national security interests. ...

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

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

    waste from civilian nuclear power generation, defense, national security and other activities. Strategy for the Management and Disposal of Used Nuclear Fuel and High ...

  3. Activities Related to Storage of Spent Nuclear Fuel | Department...

    Office of Environmental Management (EM)

    Related to Storage of Spent Nuclear Fuel More Documents & Publications Nuclear Regulatory Commission Fifth National Report for the Joint Convention on the Safety of Spent...

  4. Comparison of spent nuclear fuel management alternatives

    SciTech Connect (OSTI)

    Beebe, C.L.; Caldwell, M.A,

    1996-09-01

    This paper reports the process an results of a trade study of spent nuclear fuel (SNF)management alternatives. The purpose of the trade study was to provide: (1) a summary of various SNF management alternatives, (2) an objective comparison of the various alternatives to facilitate the decision making process, and (3) documentation of trade study rational and the basis for decisions.

  5. 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

  6. 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.

  7. 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)

  8. Cost and Quality of Fuels for Electric Plants - Energy Information...

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

    and the environment All electricity data reports Analysis & Projections Major Topics Most popular Capacity and generation Costs, revenue and expense Demand Environment Fuel use...

  9. Fuel Cell Electric Vehicles: Paving the Way to Commercial Success...

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

    Powered by a fuel cell system with light-weight, high-pressure hydrogen tanks, an electric motor, a ... Automakers have made steady progress reducing the cost and ...

  10. Fuel Cell Electric Vehicles Make Rapid Progress in Range, Durability...

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

    project to demonstrate and evaluate hydrogen fuel cell electric vehicles (FCEVs) and hydrogen ... and help the industry bring these technologies into the marketplace at lower cost. ...

  11. SERA Scenarios of Early Market Fuel Cell Electric Vehicle Introduction...

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

    SERA Scenarios of Early Market Fuel Cell Electric Vehicle ... NREL Transportation & Hydrogen Systems Center NREL... of tools for studying the cost implications of regional ...

  12. An Assessment of Heating Fuels And Electricity Markets During...

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

    PDF icon An Assessment of Heating Fuels And Electricity Markets During the Winters of 2013... Before the House Subcommittee on Energy and Power - Committee on Energy and Commerce

  13. Alternative Fuels Data Center: San Diego Prepares for Electric...

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    ... Electric Ice Resurfacers Improve Air Quality in Minnesota Sept. 14, 2013 Photo ... Fuels Dec. 25, 2010 Tennessee Reduces Pollution With Propane Hybrid Trolleys Dec. 11, ...

  14. 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.

  15. 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.

  16. Next-generation nuclear fuel withstands high-temperature accident...

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

    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 ...

  17. Behavior of Spent Nuclear Fuel in Water Pool Storage

    Office of Scientific and Technical Information (OSTI)

    Behavior of Spent Nuclear Fuel in Water Pool Storage A. 0; Johnson, jr. , I ..: . Prepared ... I . , I BEHAVIOR OF SPENT NUCLEAR FUEL I N WATER POOL STORAGE by A. B. Johnson, J r . ...

  18. Behavior of spent nuclear fuel in water pool storage (Technical...

    Office of Scientific and Technical Information (OSTI)

    Behavior of spent nuclear fuel in water pool storage Citation Details In-Document Search Title: Behavior of spent nuclear fuel in water pool storage You are accessing a document ...

  19. Cost and quality of fuels for electric plants 1993

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    The Cost and Quality of Fuels for Electric Utility Plants (C&Q) presents an annual summary of statistics at the national, Census division, State, electric utility, and plant levels regarding the quantity, quality, and cost of fossil fuels used to produce electricity. The purpose of this publication is to provide energy decision-makers with accurate and timely information that may be used in forming various perspectives on issues regarding electric power.

  20. 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.

  1. Tubular screen electrical connection support for solid oxide fuel cells

    DOE Patents [OSTI]

    Tomlins, Gregory W.; Jaszcar, Michael P.

    2002-01-01

    A solid oxide fuel assembly is made of fuel cells (16, 16', 18, 24, 24', 26), each having an outer interconnection layer (36) and an outer electrode (28), which are disposed next to each other with rolled, porous, hollow, electrically conducting metal mesh conductors (20, 20') between the fuel cells, connecting the fuel cells at least in series along columns (15, 15') and where there are no metal felt connections between any fuel cells.

  2. Nuclear Fuel Storage and Transportation Planning Project Overview |

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

    Department of Energy Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project Overview (956.77 KB) More Documents & Publications Section 180(c) Ad Hoc Working Group DOE Office of Nuclear Energy Transportation Plan Ad Hoc Working Group

  3. EIA model documentation: Electricity market module - electricity fuel dispatch

    SciTech Connect (OSTI)

    1997-01-01

    This report documents the National Energy Modeling System Electricity Fuel Dispatch Submodule (EFD), a submodule of the Electricity Market Module (EMM) as it was used for EIA`s Annual Energy Outlook 1997. It replaces previous documentation dated March 1994 and subsequent yearly update revisions. The report catalogues and describes the model assumptions, computational methodology, parameter estimation techniques, model source code, and forecast results generated through the synthesis and scenario development based on these components. This document serves four purposes. First, it is a reference document providing a detailed description of the model for reviewers and potential users of the EFD including energy experts at the Energy Information Administration (EIA), other Federal agencies, state energy agencies, private firms such as utilities and consulting firms, and non-profit groups such as consumer and environmental groups. Second, this report meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its statistical and forecast reports. Third, it facilitates continuity in model development by providing documentation which details model enhancements that were undertaken for AE097 and since the previous documentation. Last, because the major use of the EFD is to develop forecasts, this documentation explains the calculations, major inputs and assumptions which were used to generate the AE097.

  4. 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.

  5. 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.

  6. U.S. Nuclear Generation of Electricity

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

    U.S. Nuclear Generation and Generating Capacity Data Released: August 25, 2016 Data for: June 2016 Next Release: September 2016 Year Capacity and Generation by State and Reactor 2016 P XLS 2015 P XLS 2014 P XLS 2013 XLS 2012 XLS 2011 XLS 2010 XLS 2009 XLS 2008 XLS 2007 XLS 2006 XLS 2005 XLS 2004 XLS 2003 XLS P = Preliminary U.S. Nuclear Generation: 1957 to latest available EIA final data information in the Annual Energy Review, table 9.2. U. S. Nuclear power plants projected electricity

  7. 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.

  8. 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.

  9. 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.

  10. Alternative Fuels Data Center: Research and Development of Electricity as a

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Vehicle Fuel Research and Development of Electricity as a Vehicle Fuel to someone by E-mail Share Alternative Fuels Data Center: Research and Development of Electricity as a Vehicle Fuel on Facebook Tweet about Alternative Fuels Data Center: Research and Development of Electricity as a Vehicle Fuel on Twitter Bookmark Alternative Fuels Data Center: Research and Development of Electricity as a Vehicle Fuel on Google Bookmark Alternative Fuels Data Center: Research and Development of

  11. ,"for Electricity(a)","Fuel Oil","Diesel Fuel(b)","(billion"...

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

    Unit: Percents." ,,,"Distillate",,,"Coal" ,,,"Fuel Oil",,,"(excluding Coal" ,"Net Demand","Residual","and","Natural Gas(c)","LPG and","Coke and Breeze)" ,"for Electricity(a)","Fuel ...

  12. Fuel Cell Electric Vehicles and Hydrogen Infrastructure: Deployment and

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

    Issues | Department of Energy Electric Vehicles and Hydrogen Infrastructure: Deployment and Issues Fuel Cell Electric Vehicles and Hydrogen Infrastructure: Deployment and Issues This presentation by Bill Elrick of the California Fuel Cell Partnership was given at the DOE Hydrogen Compression, Storage, and Dispensing Workshop on March 19, 2013. csd_workshop_2_elrick.pdf (1004.25 KB) More Documents & Publications FCEVs and Hydrogen in California Vision for Rollout of Fuel Cell Vehicles and

  13. Washington Auto Show Spotlight: How Fuel Cell Electric Vehicles Work |

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

    Department of Energy Washington Auto Show Spotlight: How Fuel Cell Electric Vehicles Work Washington Auto Show Spotlight: How Fuel Cell Electric Vehicles Work January 27, 2015 - 12:57pm Addthis The Hyundai Tucson FCEV is currently available for lease in Southern California for less than $500 per month, including free hydrogen fuel. Hydrogen for FCEVs can be produced from a variety of resources all providing emission reductions. Hydrogen derived from natural gas reduces emissions by half and

  14. 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.

  15. Current Comparison of Advanced Nuclear Fuel Cycles

    SciTech Connect (OSTI)

    Steven Piet; Trond Bjornard; Brent Dixon; Robert Hill; Gretchen Matthern; David Shropshire

    2007-04-01

    This paper compares potential nuclear fuel cycle strategies – once-through, recycling in thermal reactors, sustained recycle with a mix of thermal and fast reactors, and sustained recycle with fast reactors. Initiation of recycle starts the draw-down of weapons-usable material and starts accruing improvements for geologic repositories and energy sustainability. It reduces the motivation to search for potential second geologic repository sites. Recycle in thermal-spectru

  16. 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.

  17. 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.

  18. Nuclear Fuels Storage & Transportation Planning Project | Department of

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

    Energy Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel assemblies [412.3 metric ton heavy metal (MTHM)] and 3 canisters of greater-than-class-C (GTCC) low-level radioactive waste. Photo courtesy of Connecticut

  19. Levelized Costs for Nuclear, Gas and Coal for Electricity, under...

    Office of Scientific and Technical Information (OSTI)

    Conference: Levelized Costs for Nuclear, Gas and Coal for Electricity, under the Mexican Scenario Citation Details In-Document Search Title: Levelized Costs for Nuclear, Gas and ...

  20. Major Fuels","Site Electricity","Natural Gas","Fuel Oil","District...

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

    C1. Total Energy Consumption by Major Fuel, 1999" ,"All Buildings",,"Total Energy Consumption (trillion Btu)",,,,,"Primary Electricity (trillion Btu)" ,"Number of Buildings...

  1. Electrical Generation for More-Electric Aircraft using Solid Oxide Fuel Cells

    Office of Energy Efficiency and Renewable Energy (EERE)

    This study, completed by Pacific Northwest National Laboratory, examines approaches to providing electrical power on board commercial aircraft using solid oxide fuel (SOFC) technology.

  2. 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.

  3. Cost and quality of fuels for electric utility plants, 1992

    SciTech Connect (OSTI)

    Not Available

    1993-08-02

    This publication presents an annual summary of statistics at the national, Census division, State, electric utility, and plant levels regarding the quantity, quality, and cost of fossil fuels used to produce electricity. The purpose of this publication is to provide energy decision-makers with accurate and timely information that may be used in forming various perspectives on issues regarding electric power.

  4. Cost and quality of fuels for electric utility plants, 1994

    SciTech Connect (OSTI)

    1995-07-14

    This document presents an annual summary of statistics at the national, Census division, State, electric utility, and plant levels regarding the quantity, quality, and cost of fossil fuels used to produce electricity. Purpose of this publication is to provide energy decision-makers with accurate, timely information that may be used in forming various perspectives on issues regarding electric power.

  5. Nuclear power generation and fuel cycle report 1997

    SciTech Connect (OSTI)

    1997-09-01

    Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

  6. Transportation capabilities study of DOE-owned spent nuclear fuel

    SciTech Connect (OSTI)

    Clark, G.L.; Johnson, R.A.; Smith, R.W.; Abbott, D.G.; Tyacke, M.J.

    1994-10-01

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

  7. 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.

  8. 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.

  9. 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.

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

    Energy Savers [EERE]

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

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol...

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

    Download the webinar slides from the U.S. Department of Energy Fuel Cell Technologies Office webinar, "Hydrogen Refueling Protocols," held February 22, 2013. Hydrogen Refueling ...

  16. 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

  17. 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.

  18. 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  20. 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...

  1. 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

  2. NREL: Transportation Research - NREL to Offer Fuel Cell Electric...

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

    to Offer Fuel Cell Electric Vehicle Ride and Drive at Sustainable Smart Home Opening on July 9 July 7, 2016 The National Renewable Energy Laboratory (NREL) will showcase several ...

  3. York Electric Cooperative- Dual Fuel Heat Pump Rebate Program

    Broader source: Energy.gov [DOE]

    York Electric Cooperative, Inc. (YEC) offers a $200 rebate to members who install a dual fuel heat pump in homes or businesses. The rebates are for primary residences, commercial, and industrial...

  4. 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.

  5. Synergistic Smart Fuel For In-pile Nuclear Reactor Measurements

    SciTech Connect (OSTI)

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

    2013-10-01

    In March 2011, an earthquake of magnitude 9.0 on the Richter scale struck Japan with its epicenter on the northeast coast, near the Tohoku region. In addition to the immense physical destruction and casualties across the country, several nuclear power plants (NPP) were affected. It was the Fukushima Daiichi NPP that experienced the most severe and irreversible damage. The earthquake brought the reactors at Fukushima to an automatic shutdown and because the power transmission lines were damaged, emergency diesel generators (EDGs) were activated to ensure that there was continued cooling of the reactors and spent fuel pools. The situation was being successfully managed until the tsunami hit about forty-five minutes later with a maximum wave height of approximately 15 m. The influx of water submerged the EDGs, the electrical switchgear, and dc batteries, resulting in the total loss of power to the reactors.2 At this point, the situation became critical. There was a loss of the sensors and instrumentation within the reactor that could have provided valuable information to guide the operators to make informed decisions and avoid the unfortunate events that followed. In the light of these events, we have developed and tested a potential self-powered thermoacoustic system, which will have the ability to serve as a temperature sensor and can transmit data independently of electronic networks. Such a device is synergistic with the harsh environment of the nuclear reactor as it utilizes the heat from the nuclear fuel to provide the input power.

  6. Models Help Pinpoint Material for Better Nuclear Fuel Recycling

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

    Models Help Pinpoint Material for Better Nuclear Fuel Recycling Models Help Pinpoint Material for Better Nuclear Fuel Recycling Sifting 125,000 Candidates Yields Ideal Candidate for Xenon, Krypton Recovery June 13, 2016 Contact: Jon Bashor, jbashor@lbl.gov, +1 510.486.5849 SBMOF-1 illlustration A new material, dubbed SBMOF-1 illustrated here, could be used to separate xenon and krypton gases from the waste produced in recycling spent nuclear fuels using less energy than conventional methods. The

  7. Economic Impacts Associated With Commercializing Fuel Cell Electric

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

    Vehicles in California: An Analysis of the California Road Map Using the JOBS H2 Model | Department of Energy Impacts Associated With Commercializing Fuel Cell Electric Vehicles in California: An Analysis of the California Road Map Using the JOBS H2 Model Economic Impacts Associated With Commercializing Fuel Cell Electric Vehicles in California: An Analysis of the California Road Map Using the JOBS H2 Model This report by Argonne National Laboratory summarizes an analysis of the economic

  8. 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.

  9. Models Help Pinpoint Material for Better Nuclear Fuel Recycling

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

    Researchers are investigating a new material that might help in nuclear fuel recycling and waste reduction by capturing certain gases released during reprocessing. Conventional ...

  10. 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.

  11. Office of Used Nuclear Fuel Disposition International Program...

    Office of Environmental Management (EM)

    strategy that combines safe storage of spent nuclear fuel with expeditious progress toward siting ... involves information exchanges, expert panels, reviews, and training and education. ...

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

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

    Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering Laboratory ...

  13. Electrical contact structures for solid oxide electrolyte fuel cell

    DOE Patents [OSTI]

    Isenberg, Arnold O.

    1984-01-01

    An improved electrical output connection means is provided for a high temperature solid oxide electrolyte type fuel cell generator. The electrical connection of the fuel cell electrodes to the electrical output bus, which is brought through the generator housing to be connected to an electrical load line maintains a highly uniform temperature distribution. The electrical connection means includes an electrode bus which is spaced parallel to the output bus with a plurality of symmetrically spaced transversely extending conductors extending between the electrode bus and the output bus, with thermal insulation means provided about the transverse conductors between the spaced apart buses. Single or plural stages of the insulated transversely extending conductors can be provided within the high temperatures regions of the fuel cell generator to provide highly homogeneous temperature distribution over the contacting surfaces.

  14. Fuel Cell Electric Vehicle Evaluation; NREL (National Renewable Energy Laboratory)

    SciTech Connect (OSTI)

    Kurtz, Jennifer; Sprik, Sam; Ainscough, Chris; Saur, Genevieve

    2015-06-10

    This presentation provides a summary of NREL's FY15 fuel cell electric vehicle evaluation project activities and accomplishments. It was presented at the U.S. Department of Energy Hydrogen and Fuel Cells Program 2015 Annual Merit Review and Peer Evaluation Meeting on June 10, 2015, in Arlington, Virginia.

  15. Material Handling Fuel Cells for Building Electric Peak Shaving Applications

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

    Material Handling Fuel Cells for Building Electric Peak Shaving Applications U.S. Department of Energy Fuel Cell Technologies Office August 11, 2015 Presenter: Michael Penev of NREL DOE Host: Pete Devlin 2 Question and Answer * Please type your question into the question box hydrogenandfuelcells.energy.gov 3 Acknowledgments Fuel Cell Technologies Office, DOE EERE For providing funding for this project and for supporting sustainable hydrogen technology development through analysis, demonstration,

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

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electricity Printable Version Share this resource Send a link to Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicles to someone by E-mail Share Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicles on Facebook Tweet about Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicles on Twitter Bookmark Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicles on Google Bookmark Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicles on

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

    Energy Savers [EERE]

    This spent nuclear fuel is composed of kernels containing thorium and U.S.-origin highly enriched uranium (HEU) embedded in small graphite spheres that were irradiated in nuclear ...

  18. CHARACTERIZATION OF HYDROGEN CONTENT IN ZIRCALOY-4 NUCLEAR FUEL CLADDING

    SciTech Connect (OSTI)

    Pfeif, E. A.; Mishra, B.; Olson, D. L.; Lasseigne, A. N.; Krzywosz, K.; Mader, E. V.

    2010-02-22

    Assessment of hydrogen uptake of underwater nuclear fuel clad and component materials will enable improved monitoring of fuel health. Zirconium alloys are used in nuclear reactors as fuel cladding, fuel channels, guide tubes and spacer grids, and are available for inspection in spent fuel pools. With increasing reactor exposure zirconium alloys experience hydrogen ingress due to neutron interactions and water-side corrosion that is not easily quantified without destructive hot cell examination. Contact and non-contact nondestructive techniques, using Seebeck coefficient measurements and low frequency impedance spectroscopy, to assess the hydrogen content and hydride formation within zircaloy 4 material that are submerged to simulate spent fuel pools are presented.

  19. 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.

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. Overview of the United States spent nuclear fuel program

    SciTech Connect (OSTI)

    Hurt, W.L.

    1997-12-01

    As a result of the end of the Cold War, the mission of the US Department of Energy (DOE) has shifted from an emphasis on nuclear weapons development and production to an emphasis on the safe management and disposal of excess nuclear materials including spent nuclear fuel from both production and research reactors. Within the US, there are two groups managing spent nuclear fuel. Commercial nuclear power plants are managing their spent nuclear fuel at the individual reactor sites until the planned repository is opened. All other spent nuclear fuel, including research reactors, university reactors, naval reactors, and legacy material from the Cold War is managed by DOE. DOE`s mission is to safely and efficiently manage its spent nuclear fuel and prepare it for disposal. This mission involves correcting existing vulnerabilities in spent fuel storage; moving spent fuel from wet basins to dry storage; processing at-risk spent fuel; and preparing spent fuel in road-ready condition for repository disposal. Most of DOE`s spent nuclear fuel is stored in underwater basins (wet storage). Many of these basins are outdated, and spent fuel is to be removed and transferred to more modern basins or to new dry storage facilities. In 1995, DOE completed a complex-wide environmental impact analysis that resulted in spent fuel being sent to one of three principal DOE sites for interim storage (up to 40 years) prior to shipment to a repository. This regionalization by fuel type will allow for economies of scale yet minimize unnecessary transportation. This paper discusses the national SNF program, ultimate disposition of SNF, and the technical challenges that have yet to be resolved, namely, release rate testing, non-destructive assay, alternative treatments, drying, and chemical reactivity.

  7. U.S. Fuel Cell Electric Vehicle Demonstration Project 2010 Status Update (Presentation)

    SciTech Connect (OSTI)

    Wipke, K.; Sprik, S.; Kurtz, J.; Ramsden, T.

    2010-10-21

    This presentation summarizes U.S. Fuel Cell Electric Vehicle Demonstration Project 2010 Status Update.

  8. Spent nuclear fuel project quality assurance program plan

    SciTech Connect (OSTI)

    Lacey, R.E.

    1997-05-09

    This main body of this document describes how the requirements of 10 CFR 830.120 are met by the Spent Nuclear Fuel Project through implementation of WHC-SP-1131. Appendix A describes how the requirements of DOE/RW-0333P are met by the Spent Nuclear Fuel Project through implementation of specific policies, manuals, and procedures.

  9. Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites

    Broader source: Energy.gov [DOE]

    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.

  10. 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.

  11. 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)

  12. 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.

  13. Spent nuclear fuel project technical databook

    SciTech Connect (OSTI)

    Reilly, M.A.

    1998-07-22

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

  14. 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).

  15. Alternative Fuels Data Center: Charging Plug-In Electric Vehicles in Public

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    in Public to someone by E-mail Share Alternative Fuels Data Center: Charging Plug-In Electric Vehicles in Public on Facebook Tweet about Alternative Fuels Data Center: Charging Plug-In Electric Vehicles in Public on Twitter Bookmark Alternative Fuels Data Center: Charging Plug-In Electric Vehicles in Public on Google Bookmark Alternative Fuels Data Center: Charging Plug-In Electric Vehicles in Public on Delicious Rank Alternative Fuels Data Center: Charging Plug-In Electric Vehicles in Public on

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. Utilization of Used Nuclear Fuel in a Potential Future US Fuel Cycle Scenario - 13499

    SciTech Connect (OSTI)

    Worrall, Andrew

    2013-07-01

    To date, the US reactor fleet has generated approximately 68,000 MTHM of used nuclear fuel (UNF) and even with no new nuclear build in the US, this stockpile will continue to grow at approximately 2,000 MTHM per year for several more decades. In the absence of reprocessing and recycle, this UNF is a liability and needs to be dealt with accordingly. However, with the development of future fuel cycle and reactor technologies in the decades ahead, there is potential for UNF to be used effectively and efficiently within a future US nuclear reactor fleet. Based on the detailed expected operating lifetimes, the future UNF discharges from the existing reactor fleet have been calculated on a yearly basis. Assuming a given electricity demand growth in the US and a corresponding growth demand for nuclear energy via new nuclear build, the future discharges of UNF have also been calculated on a yearly basis. Using realistic assumptions about reprocessing technologies and timescales and which future fuels are likely to be reprocessed, the amount of plutonium that could be separated and stored for future reactor technologies has been determined. With fast reactors (FRs) unlikely to be commercially available until 2050, any new nuclear build prior to then is assumed to be a light water reactor (LWR). If the decision is made for the US to proceed with reprocessing by 2030, the analysis shows that the UNF from future fuels discharged from 2025 onwards from the new and existing fleet of LWRs is sufficient to fuel a realistic future demand from FRs. The UNF arising from the existing LWR fleet prior to 2025 can be disposed of directly with no adverse effect on the potential to deploy a FR fleet from 2050 onwards. Furthermore, only a proportion of the UNF is required to be reprocessed from the existing fleet after 2025. All of the analyses and conclusions are based on realistic deployment timescales for reprocessing and reactor deployment. The impact of the delay in recycling the UNF

  2. 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

  3. Overview of the International R&D Recycling Activities of the Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Patricia Paviet-Hartmann

    2012-10-01

    Nuclear power has demonstrated over the last 30 years its capacity to produce base-load electricity at a low, predictable and stable cost due to the very low economic dependence on the price of uranium. However the management of used nuclear fuel remains the “Achilles’ Heel” of this energy source since the storage of used nuclear fuel is increasing as evidenced by the following number with 2,000 tons of UNF produced each year by the 104 US nuclear reactor units which equates to a total of 62,000 spent fuel assemblies stored in dry cask and 88,000 stored in pools. Two options adopted by several countries will be presented. The first one adopted by Europe, Japan and Russia consists of recycling the used nuclear fuel after irradiation in a nuclear reactor. Ninety six percent of uranium and plutonium contained in the spent fuel could be reused to produce electricity and are worth recycling. The separation of uranium and plutonium from the wastes is realized through the industrial PUREX process so that they can be recycled for re-use in a nuclear reactor as a mixed oxide (MOX) fuel. The second option undertaken by Finland, Sweden and the United States implies the direct disposal of used nuclear fuel into a geologic formation. One has to remind that only 30% of the worldwide used nuclear fuel are currently recycled, the larger part being stored (90% in pool) waiting for scientific or political decisions. A third option is emerging with a closed fuel cycle which will improve the global sustainability of nuclear energy. This option will not only decrease the volume amount of nuclear waste but also the long-term radiotoxicity of the final waste, as well as improving the long-term safety and the heat-loading of the final repository. At the present time, numerous countries are focusing on the R&D recycling activities of the ultimate waste composed of fission products and minor actinides (americium and curium). Several new chemical extraction processes, such as TRUSPEAK

  4. Fuel rod retention device for a nuclear reactor

    DOE Patents [OSTI]

    Hylton, Charles L.

    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.

  5. The Economics of Reprocessing Versus Direct Disposal of Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Bunn, Matthew; Holdren, John P.; Fetter, Steve; Zwaan, Bob van der

    2005-06-15

    We assess the economics of reprocessing versus direct disposal of spent fuel. The uranium price at which reprocessing spent fuel from light water reactors (LWRs) and recycling the resulting plutonium and uranium in LWRs would become economic is estimated for a range of reprocessing prices and other fuel cycle costs. The contribution of both fuel cycle options to the cost of electricity is also estimated. A similar analysis is performed to compare fast neutron reactors (FRs) with LWRs. We review available information about various fuel cycle costs, as well as the quantities of uranium likely to be recoverable at a range of future prices. We conclude that the once-through LWR fuel cycle is likely to remain significantly cheaper than recycling in either LWRs or FRs for at least the next 50 yr, even with substantial growth in nuclear power.

  6. 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.

  7. 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.

  8. Capacity utilization and fuel consumption in the electric power industry, 1970-1981

    SciTech Connect (OSTI)

    Lewis, E.W.

    1982-07-01

    This report updates the 1980 Energy Information Administration (EIA) publication entitled Trends in the Capacity Utilization and Fuel Consumption of Electric Utility Powerplants, 1970-1978, DOE/EIA-184/32. The analysis covers the period from 1970 through 1981, and examines trends during the period prior to the 1973 Arab oil embargo (1970-1973), after the embargo (1974-1977), and during the immediate past (1978-1981). The report also addresses other factors affecting the electric utility industry since the oil embargo: the reduction in foreign oil supplies as a result of the 1979 Iranian crisis, the 1977 drought in the western United States, the 1978 coal strike by the United Mine Workers Union, and the shutdown of nuclear plants in response to the accident at Three Mile Island. Annual data on electric utility generating capacity, net generation, and fuel consumption are provided to identify changes in patterns of power plant capacity utilization and dispatching.

  9. 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.

  10. 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.

  11. Dry, portable calorimeter for nondestructive measurement of the activity of nuclear fuel

    DOE Patents [OSTI]

    Beyer, Norman S.; Lewis, Robert N.; Perry, Ronald B.

    1976-01-01

    The activity of a quantity of heat-producing nuclear fuel is measured rapidly, accurately and nondestructively by a portable dry calorimeter comprising a preheater, an array of temperature-controlled structures comprising a thermally guarded temperature-controlled oven, and a calculation and control unit. The difference between the amounts of electric power required to maintain the oven temperature with and without nuclear fuel in the oven is measured to determine the power produced by radioactive disintegration and hence the activity of the fuel. A portion of the electronic control system is designed to terminate a continuing sequence of measurements when the standard deviation of the variations of the amount of electric power required to maintain oven temperature is within a predetermined value.

  12. An Assessment of Heating Fuels And Electricity Markets During the

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

    An Assessment of Heating Fuels And Electricity Markets During the Winters of 2013-2014 and 2014-2015 October 2015 This page intentionally blank For Further Information This report was prepared under the auspices of the Energy Infrastructure Modeling and Analysis (EIMA) division of the Office of Electricity Delivery and Energy Reliability (OE). OE's vision is a U.S. energy delivery system that is reliable in the face of all hazards and resilient to disruptions, supports U.S. economic

  13. Bioconversion of animal manure into electricity and a liquid fuel

    SciTech Connect (OSTI)

    Fischer, J.R.; Iannotti, E.L.; Stahl, T.; Garcia, A. III; Harris, F.D.

    1983-01-01

    The integrated farm energy system operating at Columbia, Missouri converted animal manure into thermal and electrical energy and a liquid fuel. An anaerobic digester converted 510 kg of volatile solids into 285 m/sup 3/ of biogas consisting of 55% methane. An internal combustion engine coupled to an electrical generator produced 408 kWh/day of electricity and 3 GJ/day of thermal energy. An ethanol production plant converted thermal and electrical energy into 85 liters of ethanol. Subtracting the thermal and electrical demands of the digester and ethanol plant, the system produced a net energy of 277 kWh of electricity, 750 MJ of thermal energy and 85 liters of ethanol. 9 references, 6 figures, 2 tables.

  14. 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.

  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)

    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%.

  17. 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)

  18. Laser-based characterization of nuclear fuel plates

    SciTech Connect (OSTI)

    Smith, James A.; Cottle, Dave L.; Rabin, Barry H.

    2014-02-18

    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.

  19. 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.

  20. 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.

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

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

    Nuclear Power Plants | Department of Energy 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 Plants What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power Plants (397.39 KB) More Documents & Publications Nuclear Fuel Storage and Transportation Planning Project Overview Indiana Department of Homeland Security - NNPP Exercise

  2. Evaluation of Waste Arising from Future Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Jubin, Robert Thomas; Taiwo, Temitope; Wigeland, Roald

    2015-01-01

    A comprehensive study was recently completed at the request of the US Department of Energy Office of Nuclear Energy (DOE-NE) to evaluate and screen nuclear fuel cycles. The final report was issued in October 2014. Uranium- and thorium-based fuel cycles were evaluated using both fast and thermal spectrum reactors. Once-through, limited-recycle, and continuous-recycle cases were considered. This study used nine evaluation criteria to identify promising fuel cycles. Nuclear waste management was one of the nine evaluation criteria. The waste generation criterion from this study is discussed herein.

  3. Alternative Fuels Data Center: Electric Vehicles Take Center Stage in North

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Texas Electric Vehicles Take Center Stage in North Texas to someone by E-mail Share Alternative Fuels Data Center: Electric Vehicles Take Center Stage in North Texas on Facebook Tweet about Alternative Fuels Data Center: Electric Vehicles Take Center Stage in North Texas on Twitter Bookmark Alternative Fuels Data Center: Electric Vehicles Take Center Stage in North Texas on Google Bookmark Alternative Fuels Data Center: Electric Vehicles Take Center Stage in North Texas on Delicious Rank

  4. Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicle

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Conversions Hybrid and Plug-In Electric Vehicle Conversions to someone by E-mail Share Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicle Conversions on Facebook Tweet about Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicle Conversions on Twitter Bookmark Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicle Conversions on Google Bookmark Alternative Fuels Data Center: Hybrid and Plug-In Electric Vehicle Conversions on Delicious Rank Alternative

  5. Alternative Fuels Data Center: Electric Vehicle Charging for Multi-Unit

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Dwellings Electricity Printable Version Share this resource Send a link to Alternative Fuels Data Center: Electric Vehicle Charging for Multi-Unit Dwellings to someone by E-mail Share Alternative Fuels Data Center: Electric Vehicle Charging for Multi-Unit Dwellings on Facebook Tweet about Alternative Fuels Data Center: Electric Vehicle Charging for Multi-Unit Dwellings on Twitter Bookmark Alternative Fuels Data Center: Electric Vehicle Charging for Multi-Unit Dwellings on Google Bookmark

  6. How to Fill Up Your Fuel Cell Electric Vehicle | Department of Energy

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

    How to Fill Up Your Fuel Cell Electric Vehicle How to Fill Up Your Fuel Cell Electric Vehicle Addthis Description Below is the text version for the "How to Fill Up Your Fuel Cell Electric Vehicle" video. How to fill up your fuel cell electric vehicle. The video includes music and text to illustrate how to fill up a fuel cell electric vehicle. Step 1: Pay: Use the controls to pay for the fuel. Step 2: Pop: Push the H2 button inside the vehicle to open the fuel tank. Step 3: Lift: Pick

  7. 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)

  8. 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.

  9. 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.

  10. RESCHEDULED: Webinar on Material Handling Fuel Cells for Building Electric Peak Shaving Applications

    Broader source: Energy.gov [DOE]

    The Fuel Cell Technologies Office will present a live webinar entitled "Material Handling Fuel Cells for Building Electric Peak Shaving Applications".

  11. Evaluation of dry versus wet unloading of spent nuclear fuel shipping casks

    SciTech Connect (OSTI)

    Allen, Jr., G. C.; Lambert, R. W.; Larkin, D. J.

    1980-01-01

    The Transportation Technology Center at Sandia National Laboratories completed an evaluation of unloading methods for spent fuel by sponsoring technical programs at Exxon Nuclear Company, Inc., and General Electric Corporation. These programs provided a comprehensive assessment of the relative merits, capabilities, and limitations of dry and wet unloading methods. The results of this evaluation, when continued, are expected to impact the development of future spent fuel and waste transportation systems. In addition, final conclusions of the evaluation will provide input to designers of future receiving and shipping interfaces at away-from-reactor spent fuel storage facilities and geologic nuclear waste repositories in the United States. The results presented here apply to the case where uncanistered spent fuel from light water reactors is to be handled. The conclusions may be different if uncontaminated canistered waste forms are considered in the future.

  12. 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.

  13. National Fuel Cell Electric Vehicle Learning Demonstration Final Report

    Office of Energy Efficiency and Renewable Energy (EERE)

    This report discusses key analysis results based on data from early 2005 through September 2011 from the US DOE’s Controlled Hydrogen Fleet and Infrastructure Validation and Demonstration Project, also referred to as the National Fuel Cell Electric Vehicle (FCEV) Learning Demonstration.

  14. 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.

  15. THE ECONOMICS OF REPROCESSING vs DIRECT DISPOSAL OF SPENT NUCLEAR FUEL

    SciTech Connect (OSTI)

    Matthew Bunn; Steve Fetter; John P. Holdren; Bob van der Zwaan

    2003-07-01

    This report assesses the economics of reprocessing versus direct disposal of spent nuclear fuel. The breakeven uranium price at which reprocessing spent nuclear fuel from existing light-water reactors (LWRs) and recycling the resulting plutonium and uranium in LWRs would become economic is assessed, using central estimates of the costs of different elements of the nuclear fuel cycle (and other fuel cycle input parameters), for a wide range of range of potential reprocessing prices. Sensitivity analysis is performed, showing that the conclusions reached are robust across a wide range of input parameters. The contribution of direct disposal or reprocessing and recycling to electricity cost is also assessed. The choice of particular central estimates and ranges for the input parameters of the fuel cycle model is justified through a review of the relevant literature. The impact of different fuel cycle approaches on the volume needed for geologic repositories is briefly discussed, as are the issues surrounding the possibility of performing separations and transmutation on spent nuclear fuel to reduce the need for additional repositories. A similar analysis is then performed of the breakeven uranium price at which deploying fast neutron breeder reactors would become competitive compared with a once-through fuel cycle in LWRs, for a range of possible differences in capital cost between LWRs and fast neutron reactors. Sensitivity analysis is again provided, as are an analysis of the contribution to electricity cost, and a justification of the choices of central estimates and ranges for the input parameters. The equations used in the economic model are derived and explained in an appendix. Another appendix assesses the quantities of uranium likely to be recoverable worldwide in the future at a range of different possible future prices.

  16. 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.

  17. 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)

  18. 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

  19. 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.

  20. 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...

  1. 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.

  2. Coolant mass flow equalizer for nuclear fuel

    DOE Patents [OSTI]

    Betten, Paul R.

    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.

  3. 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

  4. 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.

  5. Support grid for fuel elements in a nuclear reactor

    DOE Patents [OSTI]

    Finch, Lester M.

    1977-01-01

    A support grid is provided for holding nuclear fuel rods in a rectangular array. Intersecting sheet metal strips are interconnected using opposing slots in the strips to form a rectangular cellular grid structure for engaging the sides of a multiplicity of fuel rods. Spring and dimple supports for engaging fuel and guide rods extending through each cell in the support grid are formed in the metal strips with the springs thus formed being characterized by nonlinear spring rates.

  6. 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.

  7. 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.

  8. Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF)

    Broader source: Energy.gov [DOE]

    GC-52 provides legal advice to DOE regarding the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). SNF is nuclear fuel that has been used as fuel in a reactor...

  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, 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.

  11. 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.

  12. 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.

  13. Fuels

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

    Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing ... Heavy Duty Fuels DISI Combustion HCCISCCI Fundamentals Spray Combustion Modeling ...

  14. Fuel Cell Electric Vehicle (FCEV) Performance Composite Data Products: Fall 2015

    SciTech Connect (OSTI)

    Kurtz, Jennifer; Sprik, Sam; Ainscough, Chris; Saur, Genevieve; Peters, Mike

    2015-11-01

    This publication includes 53 composite data products (CDPs) produced in Fall 2015 for fuel cell electric vehicle performance.

  15. NREL: Hydrogen and Fuel Cells Research - NREL to Offer Fuel Cell Electric

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

    Vehicle Ride and Drive at Sustainable Smart Home Opening on July 9 to Offer Fuel Cell Electric Vehicle Ride and Drive at Sustainable Smart Home Opening on July 9 July 7, 2016 The National Renewable Energy Laboratory (NREL) will showcase several fuel cell electric vehicles (FCEVs) at a ride and drive event at the Sustainable Smart Home Living Learning Center Grand Opening in Superior, Colorado, on July 9. Ride and drive participants can get behind the wheel or ride along in one of NREL's

  16. Diesel Fuel Price Pass-through

    Gasoline and Diesel Fuel Update (EIA)

    1000 Independence Avenue, SW Washington, DC 20585 Home | Petroleum | Gasoline | Diesel | Propane | Natural Gas | Electricity | Coal | Nuclear Renewables | Alternative Fuels |...

  17. Electrochemical fluorination for processing of used nuclear fuel

    DOE Patents [OSTI]

    Garcia-Diaz, Brenda L.; Martinez-Rodriguez, Michael J.; Gray, Joshua R.; Olson, Luke C.

    2016-07-05

    A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO.sub.2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.

  18. South Carolina Nuclear Profile - All Fuels

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

    solid waste, batteries, chemicals, hydrogen, pitch, purchased steam, sulfur, tire-derived fuel, and miscellaneous technologies." "Other Renewable: Wood, black liquor, other wood ...

  19. National Fuel Cell Electric Vehicle Learning Demonstration Final Report

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

    Fuel Cell Electric Vehicle Learning Demonstration Final Report K. Wipke, S. Sprik, J. Kurtz, T. Ramsden, C. Ainscough, and G. Saur Technical Report NREL/TP-5600-54860 July 2012 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 National Fuel

  20. Fuel Cell Electric Vehicle Powered by Renewable Hydrogen

    SciTech Connect (OSTI)

    2011-01-01

    The National Renewable Energy Laboratory (NREL) recently received a Borrego fuel cell electric vehicle (FCEV) on loan from Kia for display at a variety of summer events. The Borrego is fueled using renewable hydrogen that is produced and dispensed at NREL's National Wind Technology Center near Boulder, Colorado. The hydrogen dispensed at the station is produced via renewable electrolysis as part of the wind-to-hydrogen project, which uses wind turbines and photovoltaic arrays to power electrolyzer stacks that split water into hydrogen and oxygen. The FCEV features state-of-the-art technology with zero harmful emissions.

  1. National Fuel Cell Electric Vehicle Learning Demonstration Final Report

    SciTech Connect (OSTI)

    Wipke, K.; Sprik, S.; Kurtz, J.; Ramsden, T.; Ainscough, C.; Saur, G.

    2012-07-01

    This report discusses key analysis results based on data from early 2005 through September 2011 from the U.S. Department of Energy's (DOE's) Controlled Hydrogen Fleet and Infrastructure Validation and Demonstration Project, also referred to as the National Fuel Cell Electric Vehicle (FCEV) Learning Demonstration. This report serves as one of many mechanisms to help transfer knowledge and lessons learned within various parts of DOE's Fuel Cell Technologies Program, as well as externally to other stakeholders. It is the fifth and final such report in a series, with previous reports being published in July 2007, November 2007, April 2008, and September 2010.

  2. Fuel Cell Electric Vehicle Powered by Renewable Hydrogen

    ScienceCinema (OSTI)

    None

    2013-05-29

    The National Renewable Energy Laboratory (NREL) recently received a Borrego fuel cell electric vehicle (FCEV) on loan from Kia for display at a variety of summer events. The Borrego is fueled using renewable hydrogen that is produced and dispensed at NREL's National Wind Technology Center near Boulder, Colorado. The hydrogen dispensed at the station is produced via renewable electrolysis as part of the wind-to-hydrogen project, which uses wind turbines and photovoltaic arrays to power electrolyzer stacks that split water into hydrogen and oxygen. The FCEV features state-of-the-art technology with zero harmful emissions.

  3. 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.

  4. 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.

  5. 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.

  6. Recent Sandia International Used Nuclear Fuel Management Collaborations

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

    International Used Nuclear Fuel Management Collaborations - 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 Energy Defense Waste

  7. 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.

  8. Estimating Source Terms for Diverse Spent Nuclear Fuel Types

    SciTech Connect (OSTI)

    Brett Carlsen; Layne Pincock

    2004-11-01

    The U.S. Department of Energy (DOE) National Spent Nuclear Fuel Program is responsible for developing a defensible methodology for determining the radionuclide inventory for the DOE spent nuclear fuel (SNF) to be dispositioned at the proposed Monitored Geologic Repository at the Yucca Mountain Site. SNF owned by DOE includes diverse fuels from various experimental, research, and production reactors. These fuels currently reside at several DOE sites, universities, and foreign research reactor sites. Safe storage, transportation, and ultimate disposal of these fuels will require radiological source terms as inputs to safety analyses that support design and licensing of the necessary equipment and facilities. This paper summarizes the methodology developed for estimating radionuclide inventories associated with DOE-owned SNF. The results will support development of design and administrative controls to manage radiological risks and may later be used to demonstrate conformance with repository acceptance criteria.

  9. 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)

  10. Locations of spent nuclear fuel and high-level radioactive waste ultimately destined for geologic disposal

    SciTech Connect (OSTI)

    Not Available

    1994-09-01

    Since the late 1950s, Americans have come to rely more and more on energy generated from nuclear reactors. Today, 109 commercial nuclear reactors supply over one-fifth of the electricity used to run our homes, schools, factories, and farms. When the nuclear fuel can no longer sustain a fission reaction in these reactors it becomes `spent` or `used` and is removed from the reactors and stored onsite. Most of our Nation`s spent nuclear fuel is currently being stored in specially designed deep pools of water at reactor sites; some is being stored aboveground in heavy thick-walled metal or concrete structures. Sites currently using aboveground dry storage systems include Virginia Power`s Surry Plant, Carolina Power and Light`s H.B. Robinson Plant, Duke Power`s Oconee Nuclear Station, Colorado Public Service Company`s shutdown reactor at Fort St. Vrain, Baltimore Gas and Electric`s Calvert Cliffs Plant, and Michigan`s Consumer Power Palisades Plant.

  11. 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.

  12. 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.

  13. Nuclear Fuel Leasing, Recycling and proliferation: Modeling a Global View

    SciTech Connect (OSTI)

    Crozat, M P; Choi, J; Reis, V H; Hill, R

    2004-03-10

    On February 11, 2004, U.S. President George W. Bush, in a speech to the National Defense University stated: ''The world must create a safe, orderly system to field civilian nuclear plants without adding to the danger of weapons proliferation. The world's leading nuclear exporters should ensure that states have reliable access at reasonable cost to fuel for civilian reactors, so long as those states renounce enrichment and reprocessing. Enrichment and reprocessing are not necessary for nations seeking to harness nuclear energy for peaceful purposes.'' This concept would require nations to choose one of two paths for civilian nuclear development: those that only have reactors and those that contain one or more elements of the nuclear fuel cycle, including recycling. ''Fuel cycle'' states would enrich uranium, manufacture and lease fuel to ''reactor'' states and receive the reactor states' spent fuel. All parties would accede to stringent security and safeguard standards, embedded within a newly invigorated international regime. Reactor states would be relieved of the financial, environmental (and political) burden of enriching and manufacturing fuel and dealing with spent fuel. Fuel cycle states would potentially earn money on leasing the fuel and perhaps on sales of reactors to the reactor states. Such a leasing concept is especially interesting in scenarios which envision growth in nuclear power, and an important consideration for such a nuclear growth regime is the role of recycling of civilian spent fuel. Recycling holds promise for improved management of spent fuel and efficient utilization of resources, but continues to raise the specter of a world with uncontrolled nuclear weapons proliferation. If done effectively, a fuel-leasing concept could help create a political and economic foundation for significant growth of clean, carbon-free nuclear power while providing a mechanism for significant international cooperation to reduce proliferation concern. This

  14. 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.

  15. 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.

  16. 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.

  17. National Fuel Cell Electric Vehicle Learning Demonstration Final Report

    SciTech Connect (OSTI)

    Wipke, K.; Sprik, S.; Kurtz, J.; Ramsden, T.; Ainscough, C.; Saur, G.

    2012-07-01

    This report discusses key analysis results based on data from early 2005 through September 2011 from the U.S. Department of Energy’s (DOE’s) Controlled Hydrogen Fleet and Infrastructure Validation and Demonstration Project, also referred to as the National Fuel Cell Electric Vehicle (FCEV) Learning Demonstration. It is the fifth and final such report in a series, with previous reports being published in July 2007, November 2007, April 2008, and September 2010.

  18. 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)

  19. 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 ...

  20. 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 ...

  1. 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 ...

  2. 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 ...

  3. 5 Things to Know When Filling Up Your Fuel Cell Electric Vehicle |

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

    Department of Energy Things to Know When Filling Up Your Fuel Cell Electric Vehicle 5 Things to Know When Filling Up Your Fuel Cell Electric Vehicle July 19, 2016 - 11:23am Addthis Watch this video to see just how easy it is to fill up your fuel cell electric vehicle. Mike Mueller Senior Digital Content Strategist, EERE Communications Learn More About Fuel Cell Electric Vehicles How Fuel Cells Work Washington D.C.'s New Hydrogen Fuel Station Demonstration Facility U.S. Department of

  4. Alternative Fuels Data Center: Charging Plug-In Electric Vehicles at Home

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    at Home to someone by E-mail Share Alternative Fuels Data Center: Charging Plug-In Electric Vehicles at Home on Facebook Tweet about Alternative Fuels Data Center: Charging Plug-In Electric Vehicles at Home on Twitter Bookmark Alternative Fuels Data Center: Charging Plug-In Electric Vehicles at Home on Google Bookmark Alternative Fuels Data Center: Charging Plug-In Electric Vehicles at Home on Delicious Rank Alternative Fuels Data Center: Charging Plug-In Electric Vehicles at Home on Digg Find

  5. Combined cycle phosphoric acid fuel cell electric power system

    SciTech Connect (OSTI)

    Mollot, D.J.; Micheli, P.L.

    1995-12-31

    By arranging two or more electric power generation cycles in series, combined cycle systems are able to produce electric power more efficiently than conventional single cycle plants. The high fuel to electricity conversion efficiency results in lower plant operating costs, better environmental performance, and in some cases even lower capital costs. Despite these advantages, combined cycle systems for the 1 - 10 megawatt (MW) industrial market are rare. This paper presents a low noise, low (oxides of nitrogen) NOx, combined cycle alternative for the small industrial user. By combining a commercially available phosphoric acid fuel cell (PAFC) with a low-temperature Rankine cycle (similar to those used in geothermal applications), electric conversion efficiencies between 45 and 47 percent are predicted. While the simple cycle PAFC is competitive on a cost of energy basis with gas turbines and diesel generators in the 1 to 2 MW market, the combined cycle PAFC is competitive, on a cost of energy basis, with simple cycle diesel generators in the 4 to 25 MW market. In addition, the efficiency and low-temperature operation of the combined cycle PAFC results in a significant reduction in carbon dioxide emissions with NO{sub x} concentration on the order of 1 parts per million (per weight) (ppmw).

  6. Impact of the proposed energy tax on nuclear electric generating technologies

    SciTech Connect (OSTI)

    Edmunds, T.A.; Lamont, A.D.; Pasternak, A.D.; Rousseau, W.F.; Walter, C.E.

    1993-05-01

    The President`s new economic initiatives include an energy tax that will affect the costs of power from most electric generating technologies. The tax on nuclear power could be applied in a number of different ways at several different points in the fuel cycle. These different approaches could have different effects on the generation costs and benefits of advanced reactors. The Office of Nuclear Energy has developed models for assessing the costs and benefits of advanced reactor cycles which must be updated to take into account the impacts of the proposed tax. This report has been prepared to assess the spectrum of impacts of the energy tax on nuclear power and can be used in updating the Office`s economic models. This study was conducted in the following steps. First, the most authoritative statement of the proposed tax available at this time was obtained. Then the impacts of the proposed tax on the costs of nuclear and fossil fueled generation were compared. Finally several other possible approaches to taxing nuclear energy were evaluated. The cost impact on several advanced nuclear technologies and a current light water technology were computed. Finally, the rationale for the energy tax as applied to various electric generating methods was examined.

  7. 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.

  8. EXTENDING NUCLEAR ENERGY TO NON-ELECTRICAL APPLICATIONS

    SciTech Connect (OSTI)

    R. Boardman; M. McKellar; D. Ingersoll; Z. Houghton; , R. Bromm; C. Desportes

    2014-09-01

    Electricity represents less than half of all energy consumed in the United States and globally. Although a few commercial nuclear power plants world-wide provide energy to non-electrical applications such as district heating and water desalination, nuclear energy has been largely relegated to base-load electricity production. A new generation of smaller-sized nuclear power plants offers significant promise for extending nuclear energy to many non-electrical applications. The NuScale small modular reactor design is especially well suited for these non-traditional customers due to its small unit size, very robust reactor protection features and a highly flexible and scalable plant design. A series of technical and economic evaluation studies have been conducted to assess the practicality of using a NuScale plant to provide electricity and heat to a variety of non-electrical applications, including water desalination, oil refining, and hydrogen production. The studies serve to highlight the unique design features of the NuScale plant for these applications and provide encouraging conclusions regarding the technical and economic viability of extending clean nuclear energy to a broad range of non-electrical energy consumers.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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

  14. Hybrid fusion reactor for production of nuclear fuel with minimum radioactive contamination of the fuel cycle

    SciTech Connect (OSTI)

    Velikhov, E. P.; Kovalchuk, M. V.; Azizov, E. A. Ignatiev, V. V.; Subbotin, S. A. Tsibulskiy, V. F.

    2015-12-15

    The paper presents the results of the system research on the coordinated development of nuclear and fusion power engineering in the current century. Considering the increasing problems of resource procurement, including limited natural uranium resources, it seems reasonable to use fusion reactors as high-power neutron sources for production of nuclear fuel in a blanket. It is shown that the share of fusion sources in this structural configuration of the energy system can be relatively small. A fundamentally important aspect of this solution to the problem of closure of the fuel cycle is that recycling of highly active spent fuel can be abandoned. Radioactivity released during the recycling of the spent fuel from the hybrid reactor blanket is at least two orders of magnitude lower than during the production of the same number of fissile isotopes after the recycling of the spent fuel from a fast reactor.

  15. 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.

  16. 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.

  17. 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.

  18. Alternative Fuels Data Center: Plug-In Electric Vehicle Deployment Policy

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Tools: Zoning, Codes, and Parking Ordinances Plug-In Electric Vehicle Deployment Policy Tools: Zoning, Codes, and Parking Ordinances to someone by E-mail Share Alternative Fuels Data Center: Plug-In Electric Vehicle Deployment Policy Tools: Zoning, Codes, and Parking Ordinances on Facebook Tweet about Alternative Fuels Data Center: Plug-In Electric Vehicle Deployment Policy Tools: Zoning, Codes, and Parking Ordinances on Twitter Bookmark Alternative Fuels Data Center: Plug-In Electric

  19. Alternative Fuels Data Center: Silicon Valley-based Electric Vehicle Parade

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Breaks Guinness World Record Silicon Valley-based Electric Vehicle Parade Breaks Guinness World Record to someone by E-mail Share Alternative Fuels Data Center: Silicon Valley-based Electric Vehicle Parade Breaks Guinness World Record on Facebook Tweet about Alternative Fuels Data Center: Silicon Valley-based Electric Vehicle Parade Breaks Guinness World Record on Twitter Bookmark Alternative Fuels Data Center: Silicon Valley-based Electric Vehicle Parade Breaks Guinness World Record on

  20. Alternative Fuels Data Center: Utility Initiatives Foster Plug-In Electric

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Vehicle Charging at Home and Work Utility Initiatives Foster Plug-In Electric Vehicle Charging at Home and Work to someone by E-mail Share Alternative Fuels Data Center: Utility Initiatives Foster Plug-In Electric Vehicle Charging at Home and Work on Facebook Tweet about Alternative Fuels Data Center: Utility Initiatives Foster Plug-In Electric Vehicle Charging at Home and Work on Twitter Bookmark Alternative Fuels Data Center: Utility Initiatives Foster Plug-In Electric Vehicle Charging at

  1. 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.

  2. 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.

  3. SUPPLEMENT ANALYSIS PROPOSED SHIPMENT OF COMMERCIAL SPENT NUCLEAR FUEL

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

    SUPPLEMENT ANALYSIS PROPOSED SHIPMENT OF COMMERCIAL SPENT NUCLEAR FUEL TO DOE NATIONAL LABORATORIES FOR RESEARCH AND DEVELOPMENT PURPOSES Office of Nuclear Energy U.S. DEPARTMENT OF ENERGY DECEMBER 2015 DOE/EIS-0203-SA-07 DOE/EIS-0250F-S-1-SA-02 Commercial Fuel Shipment SA DOE/EIS-0203-SA-07 December 2015 CONVERSION FACTORS Metric to English English to Metric Multiply by To get Multiply by To get Area Square kilometers 247.1 Acres Square kilometers 0.3861 Square miles Square meters 10.764 Square

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

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

    Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites Prepared for U.S. Department of Energy Nuclear Fuels Storage and Transportation Planning Project Steven J. Maheras (PNNL) Ralph E. Best (PNNL) Steven B. Ross (PNNL) Kenneth A. Buxton (PNNL) Jeffery L. England (SRNL) Paul E. McConnell (SNL) Lawrence M. Massaro (FRA) Philip J. Jensen (PNNL) October 1, 2014 FCRD- NFST-2014-000091 Rev. 1 PNNL-22676 Rev. 4 DISCLAIMER This information was prepared as an account of work sponsored

  5. 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.

  6. Sizing up nuclear fuel | Y-12 National Security Complex

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

    Sizing up nuclear fuel Sizing up nuclear fuel Posted: May 7, 2014 - 5:50pm | Y-12 Report | Volume 10, Issue 2 | 2014 When is small too small? Y-12 researchers analyzing samples of uranium materials would answer, "Almost never." In response to a request from the International Atomic Energy Agency, a team from Y-12's Analytical Chemistry and Development organizations evaluated natural and low-enriched-uranium samples - most no larger than 15 grams, or roughly comparable to a teaspoon of

  7. 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

  8. 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.

  9. 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.

  10. 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)

  11. Characterization of Nuclear Fuel using Multivariate Statistical Analysis

    SciTech Connect (OSTI)

    Robel, M; Robel, M; Robel, M; Kristo, M J; Kristo, M J

    2007-11-27

    Various combinations of reactor type and fuel composition have been characterized using principle components analysis (PCA) of the concentrations of 9 U and Pu isotopes in the 10 fuel as a function of burnup. The use of PCA allows the reduction of the 9-dimensional data (isotopic concentrations) into a 3-dimensional approximation, giving a visual representation of the changes in nuclear fuel composition with burnup. Real-world variation in the concentrations of {sup 234}U and {sup 236}U in the fresh (unirradiated) fuel was accounted for. The effects of reprocessing were also simulated. The results suggest that, 15 even after reprocessing, Pu isotopes can be used to determine both the type of reactor and the initial fuel composition with good discrimination. Finally, partial least squares discriminant analysis (PSLDA) was investigated as a substitute for PCA. Our results suggest that PLSDA is a better tool for this application where separation between known classes is most important.

  12. 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)

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. Nuclear Hydrogen for Peak Electricity Production and Spinning Reserve

    SciTech Connect (OSTI)

    Forsberg, C.W.

    2005-01-20

    Nuclear energy can be used to produce hydrogen. The key strategic question is this: ''What are the early markets for nuclear hydrogen?'' The answer determines (1) whether there are incentives to implement nuclear hydrogen technology today or whether the development of such a technology could be delayed by decades until a hydrogen economy has evolved, (2) the industrial partners required to develop such a technology, and (3) the technological requirements for the hydrogen production system (rate of production, steady-state or variable production, hydrogen purity, etc.). Understanding ''early'' markets for any new product is difficult because the customer may not even recognize that the product could exist. This study is an initial examination of how nuclear hydrogen could be used in two interconnected early markets: the production of electricity for peak and intermediate electrical loads and spinning reserve for the electrical grid. The study is intended to provide an initial description that can then be used to consult with potential customers (utilities, the Electric Power Research Institute, etc.) to better determine the potential real-world viability of this early market for nuclear hydrogen and provide the starting point for a more definitive assessment of the concept. If this set of applications is economically viable, it offers several unique advantages: (1) the market is approximately equivalent in size to the existing nuclear electric enterprise in the United States, (2) the entire market is within the utility industry and does not require development of an external market for hydrogen or a significant hydrogen infrastructure beyond the utility site, (3) the technology and scale match those of nuclear hydrogen production, (4) the market exists today, and (5) the market is sufficient in size to justify development of nuclear hydrogen production techniques independent of the development of any other market for hydrogen. These characteristics make it an ideal

  18. 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 world’s 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.

  19. 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

  20. 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.

  1. Potential Applications for Nuclear Energy besides Electricity Generation: AREVA Global Perspective of HTR Potential Market

    SciTech Connect (OSTI)

    Soutworth, Finis; Gauthier, Jean-Claude; Lecomte, Michel; Carre, Franck

    2007-07-01

    Energy supply is increasingly showing up as a major issue for electricity supply, transportation, settlement, and process heat industrial supply including hydrogen production. Nuclear power is part of the solution. For electricity supply, as exemplified in Finland and France, the EPR brings an immediate answer; HTR could bring another solution in some specific cases. For other supply, mostly heat, the HTR brings a solution inaccessible to conventional nuclear power plants for very high or even high temperature. As fossil fuels costs increase and efforts to avoid generation of Greenhouse gases are implemented, a market for nuclear generated process heat will develop. Following active developments in the 80's, HTR have been put on the back burner up to 5 years ago. Light water reactors are widely dominating the nuclear production field today. However, interest in the HTR technology was renewed in the past few years. Several commercial projects are actively promoted, most of them aiming at electricity production. ANTARES is today AREVA's response to the cogeneration market. It distinguishes itself from other concepts with its indirect cycle design powering a combined cycle power plant. Several reasons support this design choice, one of the most important of which is the design flexibility to adapt readily to combined heat and power applications. From the start, AREVA made the choice of such flexibility with the belief that the HTR market is not so much in competition with LWR in the sole electricity market but in the specific added value market of cogeneration and process heat. In view of the volatility of the costs of fossil fuels, AREVA's choice brings to the large industrial heat applications the fuel cost predictability of nuclear fuel with the efficiency of a high temperature heat source free of greenhouse gases emissions. The ANTARES module produces 600 MWth which can be split into the required process heat, the remaining power drives an adapted prorated

  2. Alternative Fuels Data Center: Batteries for Hybrid and Plug-In Electric

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Vehicles Batteries for Hybrid and Plug-In Electric Vehicles to someone by E-mail Share Alternative Fuels Data Center: Batteries for Hybrid and Plug-In Electric Vehicles on Facebook Tweet about Alternative Fuels Data Center: Batteries for Hybrid and Plug-In Electric Vehicles on Twitter Bookmark Alternative Fuels Data Center: Batteries for Hybrid and Plug-In Electric Vehicles on Google Bookmark Alternative Fuels Data Center: Batteries for Hybrid and Plug-In Electric Vehicles on Delicious Rank

  3. Alternative Fuels Data Center: Car2Go Launches Electric Carsharing Fleet in

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    San Diego Car2Go Launches Electric Carsharing Fleet in San Diego to someone by E-mail Share Alternative Fuels Data Center: Car2Go Launches Electric Carsharing Fleet in San Diego on Facebook Tweet about Alternative Fuels Data Center: Car2Go Launches Electric Carsharing Fleet in San Diego on Twitter Bookmark Alternative Fuels Data Center: Car2Go Launches Electric Carsharing Fleet in San Diego on Google Bookmark Alternative Fuels Data Center: Car2Go Launches Electric Carsharing Fleet in San

  4. Alternative Fuels Data Center: Georgia Sets the Pace for Plug-In Electric

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Vehicles Georgia Sets the Pace for Plug-In Electric Vehicles to someone by E-mail Share Alternative Fuels Data Center: Georgia Sets the Pace for Plug-In Electric Vehicles on Facebook Tweet about Alternative Fuels Data Center: Georgia Sets the Pace for Plug-In Electric Vehicles on Twitter Bookmark Alternative Fuels Data Center: Georgia Sets the Pace for Plug-In Electric Vehicles on Google Bookmark Alternative Fuels Data Center: Georgia Sets the Pace for Plug-In Electric Vehicles on Delicious

  5. Alternative Fuels Data Center: San Diego Dealers Plug-In to Electric

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Vehicle Progress San Diego Dealers Plug-In to Electric Vehicle Progress to someone by E-mail Share Alternative Fuels Data Center: San Diego Dealers Plug-In to Electric Vehicle Progress on Facebook Tweet about Alternative Fuels Data Center: San Diego Dealers Plug-In to Electric Vehicle Progress on Twitter Bookmark Alternative Fuels Data Center: San Diego Dealers Plug-In to Electric Vehicle Progress on Google Bookmark Alternative Fuels Data Center: San Diego Dealers Plug-In to Electric Vehicle

  6. fuel cells | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    fuel cells Sandia National Laboratories wins TechConnect Innovation Award NNSA's Sandia National Laboratories received an Innovation Award from global technology outreach and development organization TechConnect for the development of prototype Hydrocarbon Membranes for Energy and Water Electrochemical Systems. Sandia's submission placed in the top 15... Bay Area national labs team to tackle long-standing automotive hydrogen storage challenge Sandia National Laboratories chemist Mark Allendorf,

  7. Fuel Cell Electric Vehicles and Hydrogen Infrastructure: Deployment and Issues

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

    Electric Vehicles and Hydrogen Infrastructure: Deployment and Issues Bill Elrick California Fuel Cell Partnership 3/19/2013 The cars are coming HyundaiTucson ix35 FCEV production launch 2/26/13 Daimler/Nissan/Ford joint development announces 2017 launch of affordable FCEV 1/28/13 Toyota partnership with BMW 1/24/2013 Toyota announces sedan-type FCEV launch in 2015 9/24/12 The buses are coming HyundaiTucson ix35 FCEV production launch 2/26/13 Daimler/Nissan/Ford joint development announces 2017

  8. 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.

  9. 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.

  10. 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...

  11. 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...

  12. 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.

  13. 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.

  14. 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)

  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. 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.

  17. Overview of the international R&D recycling activities of the nuclear fuel cycle

    SciTech Connect (OSTI)

    Patricia Paviet-Hartmann

    2012-12-01

    Nuclear power has demonstrated over the last thirty years its capacity to produce base-load electricity at a low, predictable and stable cost due to the very low economic dependence of the price of uranium. However the management of used nuclear fuel (UNF) remains the “Achilles’ heel of this energy source since the storage of UNF is increasing as evidenced by the following number with 2,000 to 2,300 of UNF produced each year by the 104 US nuclear reactor units which equates to a total of 62,000 UNF assemblies stored in dry cask storage and 88,000 stored in pools. Alarmingly, more than half of US commercial reactor sites have filled their pools to capacity and have had to add dry cask storage facilities. Two options adopted by several countries will be discussed. The first one adopted by Europe, Japan and Russia consists of recycling the used nuclear fuel after irradiation in a nuclear reactor. Ninety six percent of uranium and plutonium contained in the spent fuel could be reused to produce electricity and are worth recycling. The separation of uranium and plutonium from the wastes is realized through the industrial PUREX process so that they can be recycled for re-use in a nuclear reactor as a mixed oxide (MOX) fuel. The second option undertaken by Finland, Sweden and the United States implies the direct disposal of UNF into a geologic formation. One has to remind that only 30% of the worldwide UNF are currently recycled, the larger part being stored (90% in pool) waiting for scientific or political decisions. A third option is emerging with a closed fuel cycle which will improve the global sustainability of nuclear energy. This option will not only decrease the volume amount of nuclear waste but also the long-term radiotoxicity of the final waste, as well as improving the long-term safety and the heat-loading of the final repository. At the present time, numerous countries are focusing on the R&D recycling activities of the ultimate waste composed of fission

  18. 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.

  19. 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.

  20. Locations of Spent Nuclear Fuel and High-Level Radioactive Waste

    Broader source: Energy.gov [DOE]

    Map of the United States of America showing the locations of spent nuclear fuel and high-level radioactive waste.