National Library of Energy BETA

Sample records for lwr internal components

  1. Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment

    Broader source: Energy.gov [DOE]

    Recent experimental observations have made it clear that cavity formation can occur in light-water reactor internal components fabricated from austenitic stainless during the course of their...

  2. Low-temperature swelling in LWR internal components: a computational assessment

    SciTech Connect (OSTI)

    Stoller, Roger E; Golubov, Stanislav I; Barashev, Alexander V

    2015-01-01

    A modern cluster dynamics model has been used to investigate the materials and irradiation parameters that control microstructural evolution under the relatively low-temperature exposure conditions that are representative of the operating environment for in-core light water reactor components. The focus is on components fabricated from austenitic stainless steel. The model accounts for the synergistic interaction between radiation-produced vacancies and the helium that is produced by nuclear transmutation reactions. Cavity nucleation rates are shown to be relatively high in this temperature regime (275 to 325 C), but are sensitive to assumptions about the fine scale microstructure produced under low-temperature irradiation. The cavity nucleation rates observed run counter to the expectation that void swelling would not occur under these conditions. This expectation was based on previous research on void swelling in austenitic steels in fast reactors. This misleading impression arose primarily from an absence of relevant data. The results of the computational modeling are generally consistent with recent data obtained by examining ex-service components. The long-term objective of this research is to provide a predictive model of void swelling at relevant lifetime exposures to support extended reactor operations.

  3. Nonlinear analysis of LWR components: areas of investigation/benefits/recommendations

    SciTech Connect (OSTI)

    Brown, S. J.

    1980-04-01

    The purpose of this study is to identify specific topics of investigation into design procedures, design concepts, methods of analysis, testing practices, and standards which are characterized by nonlinear behavior (both geometric and material) and which are considered to offer some economic and/or technical benefits to the LWR industry (excluding piping). In this study these topics were collected, compiled, and subjectively evaluated as to their potential benefit. The topics considered to have the greatest benefit/impact potential are discussed. The topics listed are based upon the experience of ODAI and also based upon a sampling of over 100 engineers/scientists in the LWR industry. The topics of investigation were found to fall basically into three areas: component, code interpretation, and load/failure mechanism. The topics are arbitrarily reorganized into six areas of investigation: Fracture, Fatigue, Vibration/Dynamic/Seismic, Plasticity, Component/Computational Considerations, and Code Interpretation.

  4. Aging management of major LWR components with nondestructive evaluation

    SciTech Connect (OSTI)

    Shah, V.N.; MacDonald, P.E.; Akers, D.W.; Sellers, C.; Murty, K.L.; Miraglia, P.Q.; Mathew, M.D.; Haggag, F.M.

    1997-12-31

    Nondestructive evaluation of material damage can contribute to continued safe, reliable, and economical operation of nuclear power plants through their current and renewed license period. The aging mechanisms active in the major light water reactor components are radiation embrittlement, thermal aging, stress corrosion cracking, flow-accelerated corrosion, and fatigue, which reduce fracture toughness, structural strength, or fatigue resistance of the components and challenge structural integrity of the pressure boundary. This paper reviews four nondestructive evaluation methods with the potential for in situ assessment of damage caused by these mechanisms: stress-strain microprobe for determining mechanical properties of reactor pressure vessel and cast stainless materials, magnetic methods for estimating thermal aging damage in cast stainless steel, positron annihilation measurements for estimating early fatigue damage in reactor coolant system piping, and ultrasonic guided wave technique for detecting cracks and wall thinning in tubes and pipes and corrosion damage to embedded portion of metal containments.

  5. Full-scale hot cell test of an acoustic sensor dedicated to measurement of the internal gas pressure and composition of a LWR nuclear fuel rod

    SciTech Connect (OSTI)

    Ferrandis, J. Y.; Rosenkrantz, E.; Leveque, G.; Baron, D.; Segura, J. C.; Cecilia, G.; Provitina, O.

    2011-07-01

    A full-scale hot cell test of the internal gas pressure and composition measurement by an acoustic sensor was carried on successfully between 2008 and 2010 on irradiated fuel rods in the LECA-STAR facility at Cadarache Centre. The acoustic sensor has been specially designed in order to provide a nondestructive technique to easily carry out the measurement of the internal gas pressure and gas composition of a LWR nuclear fuel rod. This sensor has been achieved in 2007 and is now covered by an international patent. The first positive result, concerning the device behaviour, is that the sensor-operating characteristics have not been altered by a two-year exposure in the hot cell ambient. We performed the gas characterisation contained in irradiated fuel rods. The acoustic method accuracy is now {+-}5 bars on the pressure measurement result and {+-}0.3% on the evaluated gas composition. The results of the acoustic method were compared to puncture results. Another significant conclusion is that the efficiency of the acoustic method is not altered by the irradiation time, and possible modification of the cladding properties. These results make it possible to demonstrate the feasibility of the technique on irradiated fuel rods. The transducer and the associated methodology are now operational. (authors)

  6. MCNP LWR Core Generator

    SciTech Connect (OSTI)

    Fischer, Noah A.

    2012-08-14

    The reactor core input generator allows for MCNP input files to be tailored to design specifications and generated in seconds. Full reactor models can now easily be created by specifying a small set of parameters and generating an MCNP input for a full reactor core. Axial zoning of the core will allow for density variation in the fuel and moderator, with pin-by-pin fidelity, so that BWR cores can more accurately be modeled. LWR core work in progress: (1) Reflectivity option for specifying 1/4, 1/2, or full core simulation; (2) Axial zoning for moderator densities that vary with height; (3) Generating multiple types of assemblies for different fuel enrichments; and (4) Parameters for specifying BWR box walls. Fuel pin work in progress: (1) Radial and azimuthal zoning for generating further unique materials in fuel rods; (2) Options for specifying different types of fuel for MOX or multiple burn assemblies; (3) Additional options for replacing fuel rods with burnable poison rods; and (4) Control rod/blade modeling.

  7. Evaluation of Sialon internal combustion engine components and fabrication of several ceramic components for automotive applications

    SciTech Connect (OSTI)

    McMurtry, C.H.; Ten Eyck, M.O.

    1992-10-01

    Fabrication development work was carried out on a push-rod tip having a stepped OD design and a 90{degree} shoulder in the transition area. Spray-dried Sialon premix was used in dry press tooling, and components were densified to about 98% of theoretical density using pressureless sintering conditions. Upon evaluation of the sintered components, it was found that afl components showed defects in the transition area. Modifications of the pressing parameters, incorporation of a 45{degree} angle in the shoulder area, and the use of tailored premix did not lead to the fabrication of defect-free parts. From these observations, it was concluded that the original part design could not easily be adapted to high-volume ceramic manufacturing methods. Subsequently, a modification to the desip was implemented. An SiC material with improved toughness (Hexoloy SX) was used for fabricating several test components with a closely machined, straight OD design. Pressureless-sintered and post-hot isostatically pressed (HIPed) Hexoloy SX components were supplied to The American Ceramic Engine Company (ACE) for assembly and testing. Fuel pump push-rod assemblies with Hemoloy SX tips were prepared by ACE, but no testing has been carried out to date.

  8. Evaluation of Sialon internal combustion engine components and fabrication of several ceramic components for automotive applications

    SciTech Connect (OSTI)

    McMurtry, C.H.; Ten Eyck, M.O.

    1992-10-01

    Fabrication development work was carried out on a push-rod tip having a stepped OD design and a 90[degree] shoulder in the transition area. Spray-dried Sialon premix was used in dry press tooling, and components were densified to about 98% of theoretical density using pressureless sintering conditions. Upon evaluation of the sintered components, it was found that afl components showed defects in the transition area. Modifications of the pressing parameters, incorporation of a 45[degree] angle in the shoulder area, and the use of tailored premix did not lead to the fabrication of defect-free parts. From these observations, it was concluded that the original part design could not easily be adapted to high-volume ceramic manufacturing methods. Subsequently, a modification to the desip was implemented. An SiC material with improved toughness (Hexoloy SX) was used for fabricating several test components with a closely machined, straight OD design. Pressureless-sintered and post-hot isostatically pressed (HIPed) Hexoloy SX components were supplied to The American Ceramic Engine Company (ACE) for assembly and testing. Fuel pump push-rod assemblies with Hemoloy SX tips were prepared by ACE, but no testing has been carried out to date.

  9. Multiphysics Simulations for LWR Analysis

    SciTech Connect (OSTI)

    Hamilton, Steven P [ORNL; Clarno, Kevin T [ORNL; Berrill, Mark A [ORNL; Evans, Thomas M [ORNL; Lefebvre, Robert A [ORNL; Sampath, Rahul S [ORNL; Davidson, Gregory G [ORNL; Hansel, J [Texas A& M University; Ragusa, J [Texas A& M University; Josey, Colin [University of New Mexico, Albuquerque

    2013-01-01

    Accurate prediction of the neutron and temperature distributions within an operating nuclear reactor requires the solution of multiple coupled physics equations. In a light water reactor (LWR), there is a very strong coupling between the power distribution (governed by the radiation transport equation) and the temperature and density distributions (governed by a thermal diusion equation in combination with a fluid flow model). This study aims to begin to quantify the impact of such feedback mechanisms as well as identify numerical diculties associated with such multiphysics problems. A description of the multiphysics model and current solution strategy within the Exnihilo code package will be presented, along with numerical results for a representative 3 3 PWR mini-assembly.

  10. Multiphysics simulations for LWR analysis

    SciTech Connect (OSTI)

    Hamilton, S.; Clarno, K.; Berrill, M.; Evans, T.; Davidson, G.; Lefebvre, R.; Sampath, R. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States); Hansel, J.; Ragusa, J. [Department of Nuclear Engineering, Texas A and M University (United States); Josey, C. [Department of Chemical and Nuclear Engineering, University of New Mexico (United States)

    2013-07-01

    Accurate prediction of the neutron and temperature distributions within an operating nuclear reactor requires the solution of multiple coupled physics equations. In a light water reactor (LWR), there is a very strong coupling between the power distribution (described by the radiation transport equation) and the temperature and density distributions (described by a thermal diffusion equation in combination with a fluid flow model). This study aims to begin to quantify the impact of such feedback mechanisms as well as identify numerical difficulties associated with such multiphysics problems. A description of the multiphysics model and current solution strategy within the Exnihilo code package for coupling between 3-D radiation transport and 3-D heat transfer is given. Numerical results detailing the effects of varying the nature of the coupling and the impact of mesh refinement for a representative 3x3 pressurized water reactor (PWR) 'mini-assembly' are presented. (authors)

  11. Investigation of valve failure problems in LWR power plants

    SciTech Connect (OSTI)

    1980-04-01

    An analysis of component failures from information in the computerized Nuclear Safety Information Center (NSIC) data bank shows that for both PWR and BWR plants the component category most responsible for approximately 19.3% of light water reactor (LWR) power plant shutdowns. This investigation by Burns and Roe, Inc. shows that the greatest cause of shutdowns in LWRs due to valve failures is leakage from valve stem packing. Both BWR plants and PWR plants have stem leakage problems (BWRs, 21% and PWRs, 34%).

  12. Nonlinear Ultrasonic Techniques to Monitor Radiation Damage in RPV and Internal Components

    SciTech Connect (OSTI)

    Jacobs, Laurence; Kim, Jin-Yeon; Qu, Jisnmin; Ramuhalli, Pradeep; Wall, Joe

    2015-11-02

    The objective of this research is to demonstrate that nonlinear ultrasonics (NLU) can be used to directly and quantitatively measure the remaining life in radiation damaged reactor pressure vessel (RPV) and internal components. Specific damage types to be monitored are irradiation embrittlement and irradiation assisted stress corrosion cracking (IASCC). Our vision is to develop a technique that allows operators to assess damage by making a limited number of NLU measurements in strategically selected critical reactor components during regularly scheduled outages. This measured data can then be used to determine the current condition of these key components, from which remaining useful life can be predicted. Methods to unambiguously characterize radiation related damage in reactor internals and RPVs remain elusive. NLU technology has demonstrated great potential to be used as a material sensor – a sensor that can continuously monitor a material’s damage state. The physical effect being monitored by NLU is the generation of higher harmonic frequencies in an initially monochromatic ultrasonic wave. The degree of nonlinearity is quantified with the acoustic nonlinearity parameter, β, which is an absolute, measurable material constant. Recent research has demonstrated that nonlinear ultrasound can be used to characterize material state and changes in microscale characteristics such as internal stress states, precipitate formation and dislocation densities. Radiation damage reduces the fracture toughness of RPV steels and internals, and can leave them susceptible to IASCC, which may in turn limit the lifetimes of some operating reactors. The ability to characterize radiation damage in the RPV and internals will enable nuclear operators to set operation time thresholds for vessels and prescribe and schedule replacement activities for core internals. Such a capability will allow a more clear definition of reactor safety margins. The research consists of three tasks: (1

  13. Evaluation and silicon nitride internal combustion engine components. Final report, Phase I

    SciTech Connect (OSTI)

    Voldrich, W.

    1992-04-01

    The feasibility of silicon nitride (Si{sub 3}N{sub 4}) use in internal combustion engines was studied by testing three different components for wear resistance and lower reciprocating mass. The information obtained from these preliminary spin rig and engine tests indicates several design changes are necessary to survive high-stress engine applications. The three silicon nitride components tested were valve spring retainers, tappet rollers, and fuel pump push rod ends. Garrett Ceramic Components` gas-pressure sinterable Si{sub 3}N{sub 4} (GS-44) was used to fabricate the above components. Components were final machined from densified blanks that had been green formed by isostatic pressing of GS-44 granules. Spin rig testing of the valve spring retainers indicated that these Si{sub 3}N{sub 4} components could survive at high RPM levels (9,500) when teamed with silicon nitride valves and lower spring tension than standard titanium components. Silicon nitride tappet rollers showed no wear on roller O.D. or I.D. surfaces, steel axles and lifters; however, due to the uncrowned design of these particular rollers the cam lobes indicated wear after spin rig testing. Fuel pump push rod ends were successful at reducing wear on the cam lobe and rod end when tested on spin rigs and in real-world race applications.

  14. Enhanced Accident Tolerant LWR Fuels: Metrics Development

    SciTech Connect (OSTI)

    Shannon Bragg-Sitton; Lori Braase; Rose Montgomery; Chris Stanek; Robert Montgomery; Lance Snead; Larry Ott; Mike Billone

    2013-09-01

    The Department of Energy (DOE) Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) is conducting research and development on enhanced Accident Tolerant Fuels (ATF) for light water reactors (LWRs). This mission emphasizes the development of novel fuel and cladding concepts to replace the current zirconium alloy-uranium dioxide (UO2) fuel system. The overall mission of the ATF research is to develop advanced fuels/cladding with improved performance, reliability and safety characteristics during normal operations and accident conditions, while minimizing waste generation. The initial effort will focus on implementation in operating reactors or reactors with design certifications. To initiate the development of quantitative metrics for ATR, a LWR Enhanced Accident Tolerant Fuels Metrics Development Workshop was held in October 2012 in Germantown, MD. This paper summarizes the outcome of that workshop and the current status of metrics development for LWR ATF.

  15. Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments.

    SciTech Connect (OSTI)

    Chopra, O. K.; Alexandreanu, B.; Shack, W. J.; Energy Technology

    2005-07-31

    The ASME Boiler and Pressure Vessel Code provides rules for the design of Class 1 components of nuclear power plants. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify design curves for applicable structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. The existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. Under certain environmental and loading conditions, fatigue lives of austenitic stainless steels (SSs) can be a factor of 20 lower in water than in air. This report presents experimental data on the effect of heat treatment on fatigue crack initiation in austenitic Type 304 SS in LWR coolant environments. A detailed metallographic examination of fatigue test specimens was performed to characterize the crack morphology and fracture morphology. The key material, loading, and environmental parameters and their effect on the fatigue life of these steels are also described. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves for austenitic SSs as a function of material, loading, and environmental parameters. Two methods for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations are presented.

  16. Technical report on LWR design decision methodology. Phase I

    SciTech Connect (OSTI)

    None

    1980-03-01

    Energy Incorporated (EI) was selected by Sandia Laboratories to develop and test on LWR design decision methodology. Contract Number 42-4229 provided funding for Phase I of this work. This technical report on LWR design decision methodology documents the activities performed under that contract. Phase I was a short-term effort to thoroughly review the curret LWR design decision process to assure complete understanding of current practices and to establish a well defined interface for development of initial quantitative design guidelines.

  17. Advanced LWR Nuclear Fuel Development

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

    Water Reactor Sustainability R&D Program Advanced Instrumentation, Information, and Control Systems Technologies Overview Bruce P. Hallbert DOE-NE Webinar September 16, 2014 Light Water Sustainability Program Goals and Scope * Develop the fundamental scientific basis to understand, predict, and measure changes in materials and structures, systems, and components (SSCs) as they age in environments * Apply this knowledge to develop and demonstrate methods and technologies that support safe and

  18. LIFE vs. LWR: End of the Fuel Cycle

    SciTech Connect (OSTI)

    Farmer, J C; Blink, J A; Shaw, H F

    2008-10-02

    The worldwide energy consumption in 2003 was 421 quadrillion Btu (Quads), and included 162 quads for oil, 99 quads for natural gas, 100 quads for coal, 27 quads for nuclear energy, and 33 quads for renewable sources. The projected worldwide energy consumption for 2030 is 722 quads, corresponding to an increase of 71% over the consumption in 2003. The projected consumption for 2030 includes 239 quads for oil, 190 quads for natural gas, 196 quads for coal, 35 quads for nuclear energy, and 62 quads for renewable sources [International Energy Outlook, DOE/EIA-0484, Table D1 (2006) p. 133]. The current fleet of light water reactors (LRWs) provides about 20% of current U.S. electricity, and about 16% of current world electricity. The demand for electricity is expected to grow steeply in this century, as the developing world increases its standard of living. With the increasing price for oil and gasoline within the United States, as well as fear that our CO2 production may be driving intolerable global warming, there is growing pressure to move away from oil, natural gas, and coal towards nuclear energy. Although there is a clear need for nuclear energy, issues facing waste disposal have not been adequately dealt with, either domestically or internationally. Better technological approaches, with better public acceptance, are needed. Nuclear power has been criticized on both safety and waste disposal bases. The safety issues are based on the potential for plant damage and environmental effects due to either nuclear criticality excursions or loss of cooling. Redundant safety systems are used to reduce the probability and consequences of these risks for LWRs. LIFE engines are inherently subcritical, reducing the need for systems to control the fission reactivity. LIFE engines also have a fuel type that tolerates much higher temperatures than LWR fuel, and has two safety systems to remove decay heat in the event of loss of coolant or loss of coolant flow. These features of

  19. Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments.

    SciTech Connect (OSTI)

    Chopra, O. K.; Energy Technology

    2002-08-01

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of fatigue crack initiation in austenitic stainless steels in LWR coolant environments. The existing fatigue {var_epsilon}-N data have been evaluated to establish the effects of key material, loading, and environmental parameters (such as steel type, strain range, strain rate, temperature, dissolved-oxygen level in water, and flow rate) on the fatigue lives of these steels. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves for austenitic stainless steels as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are presented. The influence of reactor environments on the mechanism of fatigue crack initiation in these steels is also discussed.

  20. Options for Burning LWR SNF in LIFE Engine

    SciTech Connect (OSTI)

    Farmer, J

    2008-09-09

    We have pursued two processes in parallel for the burning of LWR SNF in the LIFE engine: (1) solid fuel option and (2) liquid fuel option. Approaches with both are discussed. The assigned Topical Report on liquid fuels is attached.

  1. 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 ...

  2. Uniform Corrosion of model FeCrAl Alloys in LWR Coolants (Conference...

    Office of Scientific and Technical Information (OSTI)

    Conference: Uniform Corrosion of model FeCrAl Alloys in LWR Coolants Citation Details In-Document Search Title: Uniform Corrosion of model FeCrAl Alloys in LWR Coolants Authors: ...

  3. Modeling and Analysis of UN TRISO Fuel for LWR Application Using the PARFUME Code

    SciTech Connect (OSTI)

    Blaise Collin

    2014-08-01

    The Idaho National Laboraroty (INL) PARFUME (particle fuel model) code was used to assess the overall fuel performance of uranium nitride (UN) tristructural isotropic (TRISO) ceramic fuel under irradiation conditions typical of a Light Water Reactor (LWR). The dimensional changes of the fuel particle layers and kernel were calculated, including the formation of an internal gap. The survivability of the UN TRISO particle was estimated depending on the strain behavior of the constituent materials at high fast fluence and burn up. For nominal cases, internal gas pressure and representative thermal profiles across the kernel and layers were determined along with stress levels in the inner and outer pyrolytic carbon (IPyC/OPyC) and silicon carbide (SiC) layers. These parameters were then used to evaluate fuel particle failure probabilities. Results of the study show that the survivability of UN TRISO fuel under LWR irradiation conditions might only be guaranteed if the kernel and PyC swelling rates are limited at high fast fluence and burn up. These material properties have large uncertainties at the irradiation levels expected to be reached by UN TRISO fuel in LWRs. Therefore, a large experimental effort would be needed to establish material properties, including kernel and PyC swelling rates, under these conditions before definitive conclusions can be drawn on the behavior of UN TRISO fuel in LWRs.

  4. Swelling in light water reactor internal components: Insights from computational modeling

    SciTech Connect (OSTI)

    Stoller, Roger E.; Barashev, Alexander V.; Golubov, Stanislav I.

    2015-08-01

    A modern cluster dynamics model has been used to investigate the materials and irradiation parameters that control microstructural evolution under the relatively low-temperature exposure conditions that are representative of the operating environment for in-core light water reactor components. The focus is on components fabricated from austenitic stainless steel. The model accounts for the synergistic interaction between radiation-produced vacancies and the helium that is produced by nuclear transmutation reactions. Cavity nucleation rates are shown to be relatively high in this temperature regime (275 to 325°C), but are sensitive to assumptions about the fine scale microstructure produced under low-temperature irradiation. The cavity nucleation rates observed run counter to the expectation that void swelling would not occur under these conditions. This expectation was based on previous research on void swelling in austenitic steels in fast reactors. This misleading impression arose primarily from an absence of relevant data. The results of the computational modeling are generally consistent with recent data obtained by examining ex-service components. However, it has been shown that the sensitivity of the model s predictions of low-temperature swelling behavior to assumptions about the primary damage source term and specification of the mean-field sink strengths is somewhat greater that that observed at higher temperatures. Further assessment of the mathematical model is underway to meet the long-term objective of this research, which is to provide a predictive model of void swelling at relevant lifetime exposures to support extended reactor operations.

  5. Method for producing components with internal architectures, such as micro-channel reactors, via diffusion bonding sheets

    DOE Patents [OSTI]

    Alman, David E.; Wilson, Rick D.; Davis, Daniel L.

    2011-03-08

    This invention relates to a method for producing components with internal architectures, and more particularly, this invention relates to a method for producing structures with microchannels via the use of diffusion bonding of stacked laminates. Specifically, the method involves weakly bonding a stack of laminates forming internal voids and channels with a first generally low uniaxial pressure and first temperature such that bonding at least between the asperites of opposing laminates occurs and pores are isolated in interfacial contact areas, followed by a second generally higher isostatic pressure and second temperature for final bonding. The method thereby allows fabrication of micro-channel devices such as heat exchangers, recuperators, heat-pumps, chemical separators, chemical reactors, fuel processing units, and combustors without limitation on the fin aspect ratio.

  6. Improving the safety of LWR power plants. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-04-01

    This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs (improving or maintaining level of safety with simpler systems or in a more cost-effective manner).

  7. Development of FLUOREX Process as a Progressive LWR Reprocessing System

    SciTech Connect (OSTI)

    Sasahira, Akira; Kani, Yuko; Iino, Kenji; Hoshino, Kuniyoshi; Kawamura, Fumio

    2007-07-01

    New LWR fuel reprocessing technology named FLUOREX, the hybrid process of fluoride volatility and solvent extraction, proposed here is suitable for future thermal/fast reactors (coexistence) cycle. Recently we developed the flame reactor which was the main equipment to reduce volume of the spent nuclear fuel in order to down-size the PUREX like purification system. Newly constructed flame reactor, having 300 gU/h to 1 kgU/h production rate, was employed to examine the fluorination efficiency of UO{sub 2}. It was successfully demonstrated that we can control the residual amount of U within a range of 2 to 10 % by changing the excess amount of F{sub 2} gas during fluorination. This amount indicated that spent LWR fuel would be reduced to 8 to 15% by fluorination. (authors)

  8. Assessment of LWR piping design loading based on plant operating experience

    SciTech Connect (OSTI)

    Svensson, P. O.

    1980-08-01

    The objective of this study has been to: (1) identify current Light Water Reactor (LWR) piping design load parameters, (2) identify significant actual LWR piping loads from plant operating experience, (3) perform a comparison of these two sets of data and determine the significance of any differences, and (4) make an evaluation of the load representation in current LWR piping design practice, in view of plant operating experience with respect to piping behavior and response to loading.

  9. Fission product release from irradiated LWR fuel under accident conditions

    SciTech Connect (OSTI)

    Strain, R.V.; Sanecki, J.E.; Osborne, M.F.

    1984-01-01

    Fission product release from irradiated LWR fuel is being studied by heating fuel rod segments in flowing steam and an inert carrier gas to simulate accident conditions. Fuels with a range of irradiation histories are being subjected to several steam flow rates over a wide range of temperatures. Fission product release during each test is measured by gamma spectroscopy and by detailed examination of the collection apparatus after the test has been completed. These release results are complemented by a detailed posttest examination of samples of the fuel rod segment. Results of release measurements and fuel rod characterizations for tests at 1400 through 2000/sup 0/C are presented in this paper.

  10. LWR codes capability to address SFR BDBA scenarios: Modeling of the ABCOVE tests

    SciTech Connect (OSTI)

    Herranz, L. E.; Garcia, M.; Morandi, S.

    2012-07-01

    The sound background built-up in LWR source term analysis in case of a severe accident, make it worth to check the capability of LWR safety analysis codes to model accident SFR scenarios, at least in some areas. This paper gives a snapshot of such predictability in the area of aerosol behavior in containment. To do so, the AB-5 test of the ABCOVE program has been modeled with 3 LWR codes: ASTEC, ECART and MELCOR. Through the search of a best estimate scenario and its comparison to data, it is concluded that even in the specific case of in-containment aerosol behavior, some enhancements would be needed in the LWR codes and/or their application, particularly with respect to consideration of particle shape. Nonetheless, much of the modeling presently embodied in LWR codes might be applicable to SFR scenarios. These conclusions should be seen as preliminary as long as comparisons are not extended to more experimental scenarios. (authors)

  11. Effects of cooling time on a closed LWR fuel cycle

    SciTech Connect (OSTI)

    Arnold, R. P.; Forsberg, C. W.; Shwageraus, E.

    2012-07-01

    In this study, the effects of cooling time prior to reprocessing spent LWR fuel has on the reactor physics characteristics of a PWR fully loaded with homogeneously mixed U-Pu or U-TRU oxide (MOX) fuel is examined. A reactor physics analysis was completed using the CASM04e code. A void reactivity feedback coefficient analysis was also completed for an infinite lattice of fresh fuel assemblies. Some useful conclusions can be made regarding the effect that cooling time prior to reprocessing spent LWR fuel has on a closed homogeneous MOX fuel cycle. The computational analysis shows that it is more neutronically efficient to reprocess cooled spent fuel into homogeneous MOX fuel rods earlier rather than later as the fissile fuel content decreases with time. Also, the number of spent fuel rods needed to fabricate one MOX fuel rod increases as cooling time increases. In the case of TRU MOX fuel, with time, there is an economic tradeoff between fuel handling difficulty and higher throughput of fuel to be reprocessed. The void coefficient analysis shows that the void coefficient becomes progressively more restrictive on fuel Pu content with increasing spent fuel cooling time before reprocessing. (authors)

  12. Proceedings of the IAEA specialists` meeting on cracking in LWR RPV head penetrations

    SciTech Connect (OSTI)

    Pugh, C.E.; Raney, S.J.

    1996-07-01

    This report contains 17 papers that were presented in four sessions at the IAEA Specialists` meeting on Cracking in LWR RPV Head Penetrations held at ASTM Headquarters in Philadelphia on May 2-3, 1995. The papers are compiled here in the order that presentations were made in the sessions, and they relate to operational observations, inspection techniques, analytical modeling, and regulatory control. The goal of the meeting was to allow international experts to review experience in the field of ensuring adequate performance of reactor pressure vessel (RPV) heads and penetrations. The emphasis was to allow a better understanding of RPV material behavior, to provide guidance supporting reliability and adequate performance, and to assist in defining directions for further investigations. The international nature of the meeting is illustrated by the fact that papers were presented by researchers from 10 countries. There were technical experts present form other countries who participated in discussions of the results presented. This present document incorporates the final version of the papers as received from the authors. The final chapter includes conclusions and recommendations. Individual papers have been cataloged separately.

  13. Report on Assessment of Environmentally-­Assisted Fatigue for LWR Extended Service Conditions

    Broader source: Energy.gov [DOE]

    This report provides an update on the assessment of environmentally-assisted fatigue for light water reactor (LWR) extended service conditions. The report is a deliverable in FY11 under the work...

  14. Energy Return on Energy Investment for an LWR Fuel Cycle (Conference...

    Office of Scientific and Technical Information (OSTI)

    Title: Energy Return on Energy Investment for an LWR Fuel Cycle Authors: Greenberg, H R ; Smith, C A ; Blink, J A ; Fratoni, M ; Halsey, W G ; Simon, A J ; Sutton, M Publication ...

  15. Advanced LWR Nuclear Fuel Cladding System Development Trade-off Study

    Office of Energy Efficiency and Renewable Energy (EERE)

    The LWR Sustainability (LWRS) Program activities must support the timeline dictated by utility life extension decisions to demonstrate a lead test rod in a commercial reactor within 10 years. In...

  16. LWR fuel assembly designs for the transmutation of LWR Spent Fuel TRU with FCM and UO{sub 2}-ThO{sub 2} Fuels

    SciTech Connect (OSTI)

    Bae, G.; Hong, S. G.

    2013-07-01

    In this paper, transmutation of transuranic (TRU) nuclides from LWR spent fuels is studied by using LWR fuel assemblies which consist of UO{sub 2}-ThO{sub 2} fuel pins and FCM (Fully Ceramic Microencapsulated) fuel pins. TRU from LWR spent fuel is loaded in the kernels of the TRISO particle fuels of FCM fuel pins. In the FCM fuel pins, the TRISO particle fuels are distributed in SiC matrix having high thermal conductivity. The loading patterns of fuel pins and the fuel compositions are searched to have high transmutation rate and feasible neutronic parameters including pin power peaking, temperature reactivity coefficients, and cycle length. All studies are done only in fuel assembly calculation level. The results show that our fuel assembly designs have good transmutation performances without multi-recycling and without degradation of the safety-related neutronic parameters. (authors)

  17. Analysis of fission gas release in LWR fuel using the BISON code

    SciTech Connect (OSTI)

    G. Pastore; J.D. Hales; S.R. Novascone; D.M. Perez; B.W. Spencer; R.L. Williamson

    2013-09-01

    Recent advances in the development of the finite-element based, multidimensional fuel performance code BISON of Idaho National Laboratory are presented. Specifically, the development, implementation and testing of a new model for the analysis of fission gas behavior in LWR-UO2 fuel during irradiation are summarized. While retaining a physics-based description of the relevant mechanisms, the model is characterized by a level of complexity suitable for application to engineering-scale nuclear fuel analysis and consistent with the uncertainties pertaining to some parameters. The treatment includes the fundamental features of fission gas behavior, among which are gas diffusion and precipitation in fuel grains, growth and coalescence of gas bubbles at grain faces, grain growth and grain boundary sweeping effects, thermal, athermal, and transient gas release. The BISON code incorporating the new model is applied to the simulation of irradiation experiments from the OECD/NEA International Fuel Performance Experiments database, also included in the IAEA coordinated research projects FUMEX-II and FUMEX-III. The comparison of the results with the available experimental data at moderate burn-up is presented, pointing out an encouraging predictive accuracy, without any fitting applied to the model parameters.

  18. Advanced multiphysics coupling for LWR fuel performance analysis

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

    Hales, J. D.; Tonks, M. R.; Gleicher, F. N.; Spencer, B. W.; Novascone, S. R.; Williamson, R. L.; Pastore, G.; Perez, D. M.

    2015-10-01

    Even the most basic nuclear fuel analysis is a multiphysics undertaking, as a credible simulation must consider at a minimum coupled heat conduction and mechanical deformation. The need for more realistic fuel modeling under a variety of conditions invariably leads to a desire to include coupling between a more complete set of the physical phenomena influencing fuel behavior, including neutronics, thermal hydraulics, and mechanisms occurring at lower length scales. This paper covers current efforts toward coupled multiphysics LWR fuel modeling in three main areas. The first area covered in this paper concerns thermomechanical coupling. The interaction of these two physics,more » particularly related to the feedback effect associated with heat transfer and mechanical contact at the fuel/clad gap, provides numerous computational challenges. An outline is provided of an effective approach used to manage the nonlinearities associated with an evolving gap in BISON, a nuclear fuel performance application. A second type of multiphysics coupling described here is that of coupling neutronics with thermomechanical LWR fuel performance. DeCART, a high-fidelity core analysis program based on the method of characteristics, has been coupled to BISON. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during a depletion or a fast transient simulation. Two-way coupling between these codes was achieved by mapping fission rate density and fast neutron flux fields from DeCART to BISON and the temperature field from BISON to DeCART while employing a Picard iterative algorithm. Finally, the need for multiscale coupling is considered. Fission gas production and evolution significantly impact fuel performance by causing swelling, a reduction in the thermal conductivity, and fission gas release. The mechanisms involved occur at the atomistic and grain scale and are therefore not the domain of a fuel performance code. However, it is

  19. Advanced multiphysics coupling for LWR fuel performance analysis

    SciTech Connect (OSTI)

    Hales, J. D.; Tonks, M. R.; Gleicher, F. N.; Spencer, B. W.; Novascone, S. R.; Williamson, R. L.; Pastore, G.; Perez, D. M.

    2015-10-01

    Even the most basic nuclear fuel analysis is a multiphysics undertaking, as a credible simulation must consider at a minimum coupled heat conduction and mechanical deformation. The need for more realistic fuel modeling under a variety of conditions invariably leads to a desire to include coupling between a more complete set of the physical phenomena influencing fuel behavior, including neutronics, thermal hydraulics, and mechanisms occurring at lower length scales. This paper covers current efforts toward coupled multiphysics LWR fuel modeling in three main areas. The first area covered in this paper concerns thermomechanical coupling. The interaction of these two physics, particularly related to the feedback effect associated with heat transfer and mechanical contact at the fuel/clad gap, provides numerous computational challenges. An outline is provided of an effective approach used to manage the nonlinearities associated with an evolving gap in BISON, a nuclear fuel performance application. A second type of multiphysics coupling described here is that of coupling neutronics with thermomechanical LWR fuel performance. DeCART, a high-fidelity core analysis program based on the method of characteristics, has been coupled to BISON. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during a depletion or a fast transient simulation. Two-way coupling between these codes was achieved by mapping fission rate density and fast neutron flux fields from DeCART to BISON and the temperature field from BISON to DeCART while employing a Picard iterative algorithm. Finally, the need for multiscale coupling is considered. Fission gas production and evolution significantly impact fuel performance by causing swelling, a reduction in the thermal conductivity, and fission gas release. The mechanisms involved occur at the atomistic and grain scale and are therefore not the domain of a fuel performance code. However, it is possible to use

  20. Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report

    SciTech Connect (OSTI)

    Lori Braase

    2013-01-01

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: • Give “priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools.” • Give “special technical emphasis and funding priority…to activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors.” • Report “to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020.” Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and

  1. FOOD CONSUMPTION PATTERNS OF THE OZYORSK POPULATION IN 1948-1966, IMPORTANT FOR ESTIMATING PERORAL COMPONENT OF INTERNAL EXPOSURE DOSES

    SciTech Connect (OSTI)

    Mokrov, Y.; Martyushov, V. Z.; Stukalov, Pavel M.; Ivanov, I. A.; Beregich, D. A.; Anspaugh, L. R.; Napier, Bruce A.

    2008-06-01

    Results of reconstruction of food consumption patterns are presented for the residents of Ozyorsk for the period of 1948-1966. The reconstruction was performed on the basis analysis of the archive data. The given period of time is characterized by maximum releases into the atmosphere from the Mayak PA sources, and, therefore, it is considered to be the most significant period for calculating peroral component contribution to effective exposure doses to the population. The paper describes main foodstuff suppliers (regions) and their economic indices, as well as delivery rates and consumption rates for most important foodstuffs (primarily whole milk).

  2. Survey of LWR environmental control technology performance and cost

    SciTech Connect (OSTI)

    Heeb, C.M.; Aaberg, R.L.; Cole, B.M.; Engel, R.L.; Kennedy, W.E. Jr.; Lewallen, M.A.

    1980-03-01

    This study attempts to establish a ranking for species that are routinely released to the environment for a projected nuclear power growth scenario. Unlike comparisons made to existing standards, which are subject to frequent revision, the ranking of releases can be used to form a more logical basis for identifying the areas where further development of control technology could be required. This report describes projections of releases for several fuel cycle scenarios, identifies areas where alternative control technologies may be implemented, and discusses the available alternative control technologies. The release factors were used in a computer code system called ENFORM, which calculates the annual release of any species from any part of the LWR nuclear fuel cycle given a projection of installed nuclear generation capacity. This survey of fuel cycle releases was performed for three reprocessing scenarios (stowaway, reprocessing without recycle of Pu and reprocessing with full recycle of U and Pu) for a 100-year period beginning in 1977. The radioactivity releases were ranked on the basis of a relative ranking factor. The relative ranking factor is based on the 100-year summation of the 50-year population dose commitment from an annual release of radioactive effluents. The nonradioactive releases were ranked on the basis of dilution factor. The twenty highest ranking radioactive releases were identified and each of these was analyzed in terms of the basis for calculating the release and a description of the currently employed control method. Alternative control technology is then discussed, along with the available capital and operating cost figures for alternative control methods.

  3. Improved LWR Cladding Performance by EPD Surface Modification Technique

    SciTech Connect (OSTI)

    Corradini, Michael; Sridharan, Kumar

    2012-11-26

    This project will utilize the electro-phoretic deposition technique (EPD) in conjunction with nanofluids to deposit oxide coatings on prototypic zirconium alloy cladding surfaces. After demonstrating that this surface modification is reproducible and robust, the team will subject the modified surface to boiling and corrosion tests to characterize the improved nucleate boiling behavior and superior corrosion performance. The scope of work consists of the following three tasks: The first task will employ the EPD surface modification technique to coat the surface of a prototypic set of zirconium alloy cladding tube materials (e.g. Zircaloy and advanced alloys such as M5) with a micron-thick layer of zirconium oxide nanoparticles. The team will characterize the modified surface for uniformity using optical microscopy and scanning-electron microscopy, and for robustness using standard hardness measurements. After zirconium alloy cladding samples have been prepared and characterized using the EPD technique, the team will begin a set of boiling experiments to measure the heat transfer coefficient and critical heat flux (CHF) limit for each prepared sample and its control sample. This work will provide a relative comparison of the heat transfer performance for each alloy and the surface modification technique employed. As the boiling heat transfer experiments begin, the team will also begin corrosion tests for these zirconium alloy samples using a water corrosion test loop that can mimic light water reactor (LWR) operational environments. They will perform extended corrosion tests on the surface-modified zirconium alloy samples and control samples to examine the robustness of the modified surface, as well as the effect on surface oxidation

  4. Technical Development on Burn-up Credit for Spent LWR Fuel

    SciTech Connect (OSTI)

    Gauld, I.C.

    2001-12-26

    Technical development on burn-up credit for spent LWR fuels had been performed at JAERI since 1990 under the contract with Science and Technology Agency of Japan entitled ''Technical Development on Criticality Safety Management for Spent LWR Fuels.'' Main purposes of this work are to obtain the experimental data on criticality properties and isotopic compositions of spent LWR fuels and to verify burnup and criticality calculation codes. In this work three major experiments of exponential experiments for spent fuel assemblies to obtain criticality data, non-destructive gamma-ray measurement of spent fuel rods for evaluating axial burn-up profiles, and destructive analyses of spent fuel samples for determining precise burn-up and isotopic compositions were carried out. The measured data obtained were used for validating calculation codes as well as an examination of criticality safety analyses. Details of the work are described in this report.

  5. Development of an integrated, unattended assay system for LWR-MOX fuel pellet trays

    SciTech Connect (OSTI)

    Stewart, J.E.; Hatcher, C.R.; Pollat, L.L.

    1994-08-01

    Four identical unattended plutonium assay systems have been developed for use at the new light-water-reactor mixed oxide (LWR-MOX) fuel fabrication facility at Hanau, Germany. The systems provide quantitative plutonium verification for all MOX pellet trays entering or leaving a large, intermediate store. Pellet-tray transport and storage systems are highly automated. Data from the ``I-Point`` (information point) assay systems will be shared by the Euratom and International Atomic Energy Agency (IAEA) Inspectorates. The I-Point system integrates, for the first time, passive neutron coincidence counting (NCC) with electro-mechanical sensing (EMS) in unattended mode. Also, provisions have been made for adding high-resolution gamma spectroscopy. The system accumulates data for every tray entering or leaving the store between inspector visits. During an inspection, data are analyzed and compared with operator declarations for the previous inspection period, nominally one month. Specification of the I-point system resulted from a collaboration between the IAEA, Euratom, Siemens, and Los Alamos. Hardware was developed by Siemens and Los Alamos through a bilateral agreement between the German Federal Ministry of Research and Technology (BMFT) and the US DOE. Siemens also provided the EMS subsystem, including software. Through the USSupport Program to the IAEA, Los Alamos developed the NCC software (NCC COLLECT) and also the software for merging and reviewing the EMS and NCC data (MERGE/REVIEW). This paper describes the overall I-Point system, but emphasizes the NCC subsystem, along with the NCC COLLECT and MERGE/REVIEW codes. We also summarize comprehensive testing results that define the quality of assay performance.

  6. Fission product source terms for the LWR loss-of-coolant accident

    SciTech Connect (OSTI)

    Lorenz, R.A.; Collins, J.L.; Malinauskas, A.P.

    1980-07-01

    Models for cesium and iodine release from light-water reactor (LWR) fuel rods failed in steam were formulated based on experimental fission product release data from several types of failed LWR fuel rods. The models were applied to a pressurized water reactor (PWR) undergoing a hypothetical loss-of-coolant accident (LOCA) temperature transient. Calculated total iodine and cesium releases from the fuel rods were 0.053 and 0.025% of the total reactor inventories of these elements, respectively, with most of the release occurring at the time of rupture. These values are approximately two orders of magnitude less than releases used in WASH-1400, the Reactor Safety Study.

  7. Review of literature on the TMI accident and correlation to the LWR Safety Technology Program

    SciTech Connect (OSTI)

    Miller, W.J.

    1980-05-01

    This report is the result of approximately two man-months of effort devoted to assimilating and comprehending significant publicly available material related to Three Mile Island Unit 2 and events during and subsequent to the accident experienced on March 28, 1979. Those events were then correlated with the Preliminary LWR Safety Technology Program Plan (Preliminary Program Plan) prepared for the US Department of Energy by Sandia National Lab. This report is being submitted simultaneously with the SAI report entitled Preliminary Prioritization of Tasks in the Draft LWR Safety Technology Program Plan.

  8. Analysis of the Reuse of Uranium Recovered from the Reprocessing of Commercial LWR Spent Fuel

    SciTech Connect (OSTI)

    DelCul, Guillermo Daniel; Trowbridge, Lee D; Renier, John-Paul; Ellis, Ronald James; Williams, Kent Alan; Spencer, Barry B; Collins, Emory D

    2009-02-01

    This report provides an analysis of the factors involved in the reuse of uranium recovered from commercial light-water-reactor (LWR) spent fuels (1) by reenrichment and recycling as fuel to LWRs and/or (2) by recycling directly as fuel to heavy-water-reactors (HWRs), such as the CANDU (registered trade name for the Canadian Deuterium Uranium Reactor). Reuse is an attractive alternative to the current Advanced Fuel Cycle Initiative (AFCI) Global Nuclear Energy Partnership (GNEP) baseline plan, which stores the reprocessed uranium (RU) for an uncertain future or attempts to dispose of it as 'greater-than-Class C' waste. Considering that the open fuel cycle currently deployed in the United States already creates a huge excess quantity of depleted uranium, the closed fuel cycle should enable the recycle of the major components of spent fuel, such as the uranium and the hazardous, long-lived transuranic (TRU) actinides, as well as the managed disposal of fission product wastes. Compared with the GNEP baseline scenario, the reuse of RU in the uranium fuel cycle has a number of potential advantages: (1) avoidance of purchase costs of 11-20% of the natural uranium feed; (2) avoidance of disposal costs for a large majority of the volume of spent fuel that is reprocessed; (3) avoidance of disposal costs for a portion of the depleted uranium from the enrichment step; (4) depending on the {sup 235}U assay of the RU, possible avoidance of separative work costs; and (5) a significant increase in the production of {sup 238}Pu due to the presence of {sup 236}U, which benefits somewhat the transmutation value of the plutonium and also provides some proliferation resistance.

  9. A review of the effects of coolant environments on the fatigue life of LWR structural materials.

    SciTech Connect (OSTI)

    Chopra, O. K.; Shack, W. J.

    2009-04-01

    The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code specifies design curves for the fatigue life of structural materials in nuclear power plants. However, the effects of light water reactor (LWR) coolant environments were not explicitly considered in the development of the design curves. The existing fatigue-strain-versus-life ({var_epsilon}-N) data indicate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. Under certain environmental and loading conditions, fatigue lives in water relative to those in air can be a factor of 15 lower for austenitic stainless steels and a factor of {approx}30 lower for carbon and low-alloy steels. This paper reviews the current technical basis for the understanding of the fatigue of piping and pressure vessel steels in LWR environments. The existing fatigue {var_epsilon}-N data have been evaluated to identify the various material, environmental, and loading parameters that influence fatigue crack initiation and to establish the effects of key parameters on the fatigue life of these steels. Statistical models are presented for estimating fatigue life as a function of material, loading, and environmental conditions. An environmental fatigue correction factor for incorporating the effects of LWR environments into ASME Code fatigue evaluations is described. This paper also presents a critical review of the ASME Code fatigue design margins of 2 on stress (or strain) and 20 on life and assesses the possible conservatism in the current choice of design margins.

  10. Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation

    SciTech Connect (OSTI)

    Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki

    2012-06-06

    Some interesting issues are attributed to nuclide compositions of spent fuels from thermal reactors as well as fast reactors such as a potential to reuse as recycled fuel, and a possible capability to be manage as a fuel for destructive devices. In addition, analysis on nuclear forensics which is related to spent fuel compositions becomes one of the interesting topics to evaluate the origin and the composition of spent fuels from the spent fuel foot-prints. Spent fuel compositions of different fuel types give some typical spent fuel foot prints and can be estimated the origin of source of those spent fuel compositions. Some technics or methods have been developing based on some science and technological capability including experimental and modeling or theoretical aspects of analyses. Some foot-print of nuclear forensics will identify the typical information of spent fuel compositions such as enrichment information, burnup or irradiation time, reactor types as well as the cooling time which is related to the age of spent fuels. This paper intends to evaluate the typical spent fuel compositions of light water (LWR) and fast breeder reactors (FBR) from the view point of some foot prints of nuclear forensics. An established depletion code of ORIGEN is adopted to analyze LWR spent fuel (SF) for several burnup constants and decay times. For analyzing some spent fuel compositions of FBR, some coupling codes such as SLAROM code, JOINT and CITATION codes including JFS-3-J-3.2R as nuclear data library have been adopted. Enriched U-235 fuel composition of oxide type is used for fresh fuel of LWR and a mixed oxide fuel (MOX) for FBR fresh fuel. Those MOX fuels of FBR come from the spent fuels of LWR. Some typical spent fuels from both LWR and FBR will be compared to distinguish some typical foot-prints of SF based on nuclear forensic analysis.

  11. Evaluation of FSV-1 cask for the transport of LWR irradiated fuel assemblies

    SciTech Connect (OSTI)

    Not Available

    1980-05-01

    The Model FSV-1 spent fuel shipping cask was designed by General Atomic Company (GA) to service the Fort St. Vrain (FSV) nuclear generating station, a High Temperature Gas Reactor (HTGR) owned and operated by Public Service Company of Colorado (PSC). This report presents an evaluation of the suitability of the FSV-1 cask for the transport of irradiated Light Water Reactor (LWR) fuel assemblies from both Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). The FSV-1 cask evaluation parameters covered a wide spectrum of LWR fuel assemblies, based on burnup in Megawatt Days/Metric Ton of Heavy Metal (MWD/MTHM) and years of decay since irradiation. The criteria for suitability included allowable radiation dose rates, cask surface and interior temperatures and the Gross Vehicle Weight (GVW) of the complete shipping system.

  12. LWR design decision methodology: Phase II. Final report

    SciTech Connect (OSTI)

    None

    1981-01-01

    Techniques were identified to augment existing design process at the component and system level in order to optimize cost and safety between alternative system designs. The method was demonstrated using the Surry Low Pressure Injection System (LPIS). Three possible backfit options were analyzed for the Surry LPIS, assessing the safety level of each option and estimating the acquisition and installation costs for each. (DLC)

  13. APEX nuclear fuel cycle for production of LWR fuel and elimination of radioactive waste

    SciTech Connect (OSTI)

    Steinberg, M.; Powell, J.R.

    1981-08-01

    The development of a nuclear fission fuel cycle is proposed which eliminates all the radioactive fission product waste effluent and the need for geological-age high level waste storage and provides a long term supply of fissile fuel for an LWR power reactor economy. The fuel cycle consists of reprocessing LWR spent fuel (1 to 2 years old) to remove the stable nonradioactive (NRFP, e.g. lanthanides, etc.) and short-lived fission products (SLFP e.g. half-lives of (1 to 2 years) and returning, in dilute form, the long-lived fission products, ((LLFPs, e.g. 30 y half-life Cs, Sr, and 10 y Kr, and 16 x 10/sup 6/ y I) and the transuranics (TUs, e.g. Pu, Am, Cm, and Np) to be refabricated into fresh fuel elements. Makeup fertile and fissile fuel are to be supplied through the use of a Spallator (linear accelerator spallation-target fuel-producer). The reprocessing of LWR fuel elements is to be performed by means of the Chelox process which consists of Airox treatment (air oxidation and hydrogen reduction) followed by chelation with an organic reagent (..beta..-diketonate) and vapor distillation of the organometallic compounds for separation and partitioning of the fission products.

  14. FMDP reactor alternative summary report. Volume 1 - existing LWR alternative

    SciTech Connect (OSTI)

    Greene, S.R.; Bevard, B.B.

    1996-10-07

    Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] are becoming surplus to national defense needs in both the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. This document summarizes the results of analysis concerned with existing light water reactor plutonium disposition alternatives.

  15. LWR spent fuel reduction by the removal of U and the compact storage of Pu with FP for long-term nuclear sustainability

    SciTech Connect (OSTI)

    Fukasawa, T.; Hoshino, K.; Takano, M.; Sato, S.; Shimazu, Y.

    2013-07-01

    Fast breeder reactors (FBR) nuclear fuel cycle is needed for long-term nuclear sustainability while preventing global warming and maximum utilizing the limited uranium (U) resources. The 'Framework for Nuclear Energy Policy' by the Japanese government on October 2005 stated that commercial FBR deployment will start around 2050 under its suitable conditions by the successive replacement of light water reactors (LWR) to FBR. Even after Fukushima Daiichi Nuclear Power Plant accident which made Japanese tendency slow down the nuclear power generation activities, Japan should have various options for energy resources including nuclear, and also consider the delay of FBR deployment and increase of LWR spent fuel (LWR-SF) storage amounts. As plutonium (Pu) for FBR deployment will be supplied from LWR-SF reprocessing and Japan will not possess surplus Pu, the authors have developed the flexible fuel cycle initiative (FFCI) for the transition from LWR to FBR. The FFCI system is based on the possibility to stored recycled materials (U, Pu)temporarily for a suitable period according to the FBR deployment rate to control the Pu demand/supply balance. This FFCI system is also effective after the Fukushima accident for the reduction of LWR-SF and future LWR-to-FBR transition. (authors)

  16. Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study

    SciTech Connect (OSTI)

    Kristine Barrett; Shannon Bragg-Sitton

    2012-09-01

    The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R&D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental improvements are required in the areas of nuclear fuel composition, cladding integrity, and the fuel/cladding interaction to allow power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an “accident tolerant” fuel system that would offer improved coping time under accident scenarios. With a development time of about 20 – 25 years, advanced fuel designs must be started today and proven in current reactors if future reactor designs are to be able to use them with confidence.

  17. Microstructural evolution of type 304 and 316 stainless steels under neutron irradiation at LWR relevant conditions

    SciTech Connect (OSTI)

    Tan, Lizhen; Stoller, Roger E.; Field, Kevin G.; Yang, Ying; Morgan, Dane; Wirth, Brian D.; Gussev, Maxim N.; Busby, Jeremy T.; Nam, H.

    2015-12-11

    Extension of light water reactors' useful life will expose austenitic internal core components to irradiation damage levels beyond 100 displacements per atom (dpa), which will lead to profound microstructural evolution and consequent degradation of macroscopic properties. Microstructural evolution, including Frank loops, cavities, precipitates, and segregation at boundaries and the resultant radiation hardening in type 304 and 316 stainless steel (SS) variants, were studied in this work via experimental characterization and multiple simulation methods. Experimental data for up to 40 heats of type 304SS and 316SS variants irradiated in different reactors to 0.6–120 dpa at 275–375°C were either generated from this work or collected from literature reports. These experimental data were then combined with models of Frank loop and cavity evolution, computational thermodynamics and precipitation, and ab initio and rate theory integrated radiation-induced segregation models to provide insights into microstructural evolution and degradation at higher radiation doses.

  18. Ice Thermal Storage Systems for LWR Supplemental Cooling and Peak Power Shifting

    SciTech Connect (OSTI)

    Haihua Zhao; Hongbin Zhang; Phil Sharpe; Blaise Hamanaka; Wei Yan; WoonSeong Jeong

    2010-06-01

    Availability of enough cooling water has been one of the major issues for the nuclear power plant site selection. Cooling water issues have frequently disrupted the normal operation at some nuclear power plants during heat waves and long draught. The issues become more severe due to the new round of nuclear power expansion and global warming. During hot summer days, cooling water leaving a power plant may become too hot to threaten aquatic life so that environmental regulations may force the plant to reduce power output or even temporarily to be shutdown. For new nuclear power plants to be built at areas without enough cooling water, dry cooling can be used to remove waste heat directly into the atmosphere. However, dry cooling will result in much lower thermal efficiency when the weather is hot. One potential solution for the above mentioned issues is to use ice thermal storage systems (ITS) that reduce cooling water requirements and boost the plant’s thermal efficiency in hot hours. ITS uses cheap off-peak electricity to make ice and uses those ice for supplemental cooling during peak demand time. ITS is suitable for supplemental cooling storage due to its very high energy storage density. ITS also provides a way to shift large amount of electricity from off peak time to peak time. Some gas turbine plants already use ITS to increase thermal efficiency during peak hours in summer. ITSs have also been widely used for building cooling to save energy cost. Among three cooling methods for LWR applications: once-through, wet cooling tower, and dry cooling tower, once-through cooling plants near a large water body like an ocean or a large lake and wet cooling plants can maintain the designed turbine backpressure (or condensation temperature) during 99% of the time; therefore, adding ITS to those plants will not generate large benefits. For once-through cooling plants near a limited water body like a river or a small lake, adding ITS can bring significant economic

  19. Rate Theory Modeling and Simulations of Silicide Fuel at LWR Conditions

    SciTech Connect (OSTI)

    Miao, Yinbin; Ye, Bei; Mei, Zhigang; Hofman, Gerard; Yacout, Abdellatif

    2015-12-10

    Uranium silicide (U3Si2) fuel has higher thermal conductivity and higher uranium density, making it a promising candidate for the accident-tolerant fuel (ATF) used in light water reactors (LWRs). However, previous studies on the fuel performance of U3Si2, including both experimental and computational approaches, have been focusing on the irradiation conditions in research reactors, which usually involve low operation temperatures and high fuel burnups. Thus, it is important to examine the fuel performance of U3Si2 at typical LWR conditions so as to evaluate the feasibility of replacing conventional uranium dioxide fuel with this silicide fuel material. As in-reactor irradiation experiments involve significant time and financial cost, it is appropriate to utilize modeling tools to estimate the behavior of U3Si2 in LWRs based on all those available research reactor experimental references and state-of-the-art density functional theory (DFT) calculation capabilities at the early development stage. Hence, in this report, a comprehensive investigation of the fission gas swelling behavior of U3Si2 at LWR conditions is introduced. The modeling efforts mentioned in this report was based on the rate theory (RT) model of fission gas bubble evolution that has been successfully applied for a variety of fuel materials at devious reactor conditions. Both existing experimental data and DFT-calculated results were used for the optimization of the parameters adopted by the RT model. Meanwhile, the fuel-cladding interaction was captured by the coupling of the RT model with simplified mechanical correlations. Therefore, the swelling behavior of U3Si2 fuel and its consequent interaction with cladding in LWRs was predicted by the rate theory modeling, providing valuable information for the development of U3Si2 fuel as an accident

  20. Uranium Nitride as LWR TRISO Fuel: Thermodynamic Modeling of U-C-N

    SciTech Connect (OSTI)

    Besmann, Theodore M; Shin, Dongwon

    2012-01-01

    TRISO coated particle fuel is envisioned as a next generation replacement for current urania pellet fuel in LWR applications. To obtain adequate fissile loading the kernel of the TRISO particle will need to be UN. In support of the fuel development effort, an assessment of phase regions of interest in the U-C-N system was undertaken as the fuel will be prepared by the carbothermic reduction of the oxide and it will be in equilibrium with carbon within the TRISO particle. The phase equilibria and thermochemistry of the U-C-N system is reviewed, including nitrogen pressure measurements above various phase fields. Selected measurements were used to fit a first order model of the UC1-xNx phase, represented by the inter-solution of UN and UC. Fit to the data was significantly improved by also adjusting the heat of formation for UN by ~12 kJ/mol and the phase equilbria was best reproduced by also adjusting the heat for U2N3 by +XXX. The determined interaction parameters yielded a slightly positive deviation from ideality, which agrees with lattice parameter measurements which show positive deviation from Vegard s law. The resultant model together with reported values for other phases in the system were used to generate isothermal sections of the U-C-N phase diagram. Nitrogen partial pressures were also computed for regions of interest.

  1. Uniform corrosion of FeCrAl alloys in LWR coolant environments

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

    Terrani, K. A.; Pint, B. A.; Kim, Y. -J.; Unocic, K. A.; Yang, Y.; Silva, C. M.; Meyer, III, H. M.; Rebak, R. B.

    2016-06-29

    In this study, the corrosion behavior of commercial and model FeCrAl alloys and type 310 stainless steel was examined by autoclave tests and compared to Zircaloy-4, the reference cladding materials in light water reactors. The corrosion studies were carried out in three distinct water chemistry environments found in pressurized and boiling water reactor primary coolant loop conditions for up to one year. The structure and morphology of the oxides formed on the surface of these alloys was consistent with thermodynamic predictions. Spinel-type oxides were found to be present after hydrogen water chemistry exposures, while the oxygenated water tests resulted inmore » the formation of very thin and protective hematite-type oxides. Unlike the alloys exposed to oxygenated water tests, the alloys tested in hydrogen water chemistry conditions experienced mass loss as a function of time. This mass loss was the result of net sum of mass gain due to parabolic oxidation and mass loss due to dissolution that also exhibits parabolic kinetics. Finally, the maximum thickness loss after one year of LWR water corrosion in the absence of irradiation was ~2 μm, which is inconsequential for a ~300–500 μm thick cladding.« less

  2. Stability of SiC-Matrix Microencapsulated Fuel Constituents at Relevant LWR Conditions

    SciTech Connect (OSTI)

    Terrani, Kurt A; Katoh, Yutai; Leonard, Keith J; Perez-Bergquist, Alex G; Silva, Chinthaka M; Snead, Lance Lewis

    2014-01-01

    This paper addresses certain key feasibility issues facing the application of SiC-matrix microencapsulated fuels for light water reactor application. Issues addressed are the irradiation stability of the SiC-based nano-powder ceramic matrix under LWR-relevant irradiation conditions, the presence or extent of reaction of the SiC matrix with zirconium-based cladding, the stability of the inner and outer pyrolytic graphite layers of the microencapsulated (TRISO) particle at this uncharacteristically low irradiation temperature, and the state of the particle-matrix interface following irradiation which could possibly effect thermal transport. In the process of determining these feasibility issues microstructural evolution and change in dimension and thermal conductivity was studied. As a general finding the SiC matrix was found to be quite stable with behavior similar to that of CVD SiC. In magnitude the irradiation-induced swelling of the matrix material was slightly higher and irradiation-degraded thermal conductivity was slightly lower as compared to CVD SiC. No significant reaction of this SiC-based nano-powder ceramic matrix material with Zircaloy was observed. Irradiation of the TRISO in the 320-360 C range to a maximum dose of 7.7 1025 n/m2 (E > 0.1 MeV) did not have significant negative impact on the constituent layers of the TRISO fuel. At the highest dose studied layer structure and interface integrity remained essentially unchanged with good apparent thermal transport through the microsphere to the surrounding matrix.

  3. Microstructural evolution of type 304 and 316 stainless steels under neutron irradiation at LWR relevant conditions

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

    Tan, Lizhen; Stoller, Roger E.; Field, Kevin G.; Yang, Ying; Morgan, Dane; Wirth, Brian D.; Gussev, Maxim N.; Busby, Jeremy T.; Nam, H.

    2015-12-11

    Extension of light water reactors' useful life will expose austenitic internal core components to irradiation damage levels beyond 100 displacements per atom (dpa), which will lead to profound microstructural evolution and consequent degradation of macroscopic properties. Microstructural evolution, including Frank loops, cavities, precipitates, and segregation at boundaries and the resultant radiation hardening in type 304 and 316 stainless steel (SS) variants, were studied in this work via experimental characterization and multiple simulation methods. Experimental data for up to 40 heats of type 304SS and 316SS variants irradiated in different reactors to 0.6–120 dpa at 275–375°C were either generated from thismore » work or collected from literature reports. These experimental data were then combined with models of Frank loop and cavity evolution, computational thermodynamics and precipitation, and ab initio and rate theory integrated radiation-induced segregation models to provide insights into microstructural evolution and degradation at higher radiation doses.« less

  4. A Review and Analysis of European Industrial Experience in Handling LWR Spent Fuel and Vitrified High-Level Waste

    SciTech Connect (OSTI)

    Blomeke, J.O.

    2001-07-10

    The industrial facilities that have been built or are under construction in France, the United Kingdom, Sweden, and West Germany to handle light-water reactor (LWR) spent fuel and canisters of vitrified high-level waste before ultimate disposal are described and illustrated with drawings and photographs. Published information on the operating performance of these facilities is also given. This information was assembled for consideration in planning and design of similar equipment and facilities needed for the Federal Waste Management System in the United States.

  5. Internal Dosimetry

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

    21-2008 October 2008 DOE STANDARD INTERNAL DOSIMETRY U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1121-2008 iii FOREWORD 1. This Department of Energy (DOE) standard is approved for use by all DOE Components and their

  6. Lower East Fork Poplar Creek | Department of Energy

    Office of Environmental Management (EM)

    Modeling Assessment | Department of Energy Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment Recent experimental observations have made it clear that cavity formation can occur in light-water reactor internal components fabricated from austenitic stainless during the course of their service life. In order to assess the potential for cavity swelling in these

  7. Fast, quantitative, and nondestructive evaluation of hydrided LWR fuel cladding by small angle incoherent neutron scattering of hydrogen

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

    Yan, Y.; Qian, S.; Littrell, K.; Parish, C. M.; Plummer, L. K.

    2015-02-13

    A non-destructive neutron scattering method to precisely measure the uptake of hydrogen and the distribution of hydride precipitates in light water reactor (LWR) fuel cladding was developed. Zircaloy-4 cladding used in commercial LWRs was used to produce hydrided specimens. The hydriding apparatus consists of a closed stainless steel vessel that contains Zr alloy specimens and hydrogen gas. Following hydrogen charging, the hydrogen content of the hydrided specimens was measured using the vacuum hot extraction method, by which the samples with desired hydrogen concentration were selected for the neutron study. Optical microscopy shows that our hydriding procedure results in uniform distributionmore » of circumferential hydrides across the wall. Small angle neutron incoherent scattering was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. This study demonstrates that the hydrogen in commercial Zircaloy-4 cladding can be measured very accurately in minutes by this nondestructive method over a wide range of hydrogen concentrations from a very small amount ( 20 ppm) to over 1000 ppm. The hydrogen distribution in a tube sample was obtained by scaling the neutron scattering rate with a factor determined by a calibration process using standard, destructive direct chemical analysis methods on the specimens. This scale factor will be used in future tests with unknown hydrogen concentrations, thus providing a nondestructive method for absolute hydrogen concentration determination.« less

  8. Fast, quantitative, and nondestructive evaluation of hydrided LWR fuel cladding by small angle incoherent neutron scattering of hydrogen

    SciTech Connect (OSTI)

    Yan, Y.; Qian, S.; Littrell, K.; Parish, C. M.; Plummer, L. K.

    2015-02-13

    A non-destructive neutron scattering method to precisely measure the uptake of hydrogen and the distribution of hydride precipitates in light water reactor (LWR) fuel cladding was developed. Zircaloy-4 cladding used in commercial LWRs was used to produce hydrided specimens. The hydriding apparatus consists of a closed stainless steel vessel that contains Zr alloy specimens and hydrogen gas. Following hydrogen charging, the hydrogen content of the hydrided specimens was measured using the vacuum hot extraction method, by which the samples with desired hydrogen concentration were selected for the neutron study. Optical microscopy shows that our hydriding procedure results in uniform distribution of circumferential hydrides across the wall. Small angle neutron incoherent scattering was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. This study demonstrates that the hydrogen in commercial Zircaloy-4 cladding can be measured very accurately in minutes by this nondestructive method over a wide range of hydrogen concentrations from a very small amount ( 20 ppm) to over 1000 ppm. The hydrogen distribution in a tube sample was obtained by scaling the neutron scattering rate with a factor determined by a calibration process using standard, destructive direct chemical analysis methods on the specimens. This scale factor will be used in future tests with unknown hydrogen concentrations, thus providing a nondestructive method for absolute hydrogen concentration determination.

  9. Storage of LWR spent fuel in air: Volume 1: Design and operation of a spent fuel oxidation test facility

    SciTech Connect (OSTI)

    Thornhill, C.K.; Campbell, T.K.; Thornhill, R.E.

    1988-12-01

    This report describes the design and operation and technical accomplishments of a spent-fuel oxidation test facility at the Pacific Northwest Laboratory. The objective of the experiments conducted in this facility was to develop a data base for determining spent-fuel dry storage temperature limits by characterizing the oxidation behavior of light-water reactor (LWR) spent fuels in air. These data are needed to support licensing of dry storage in air as an alternative to spent-fuel storage in water pools. They are to be used to develop and validate predictive models of spent-fuel behavior during dry air storage in an Independent Spent Fuel Storage Installation (ISFSI). The present licensed alternative to pool storage of spent fuel is dry storage in an inert gas environment, which is called inerted dry storage (IDS). Licensed air storage, however, would not require monitoring for maintenance of an inert-gas environment (which IDS requires) but does require the development of allowable temperature limits below which UO/sub 2/ oxidation in breached fuel rods would not become a problem. Scoping tests at PNL with nonirradiated UO/sub 2/ pellets and spent-fuel fragment specimens identified the need for a statistically designed test matrix with test temperatures bounding anticipated maximum acceptable air-storage temperatures. This facility was designed and operated to satisfy that need. 7 refs.

  10. Fast, Quantitative, and Nondestructive Evaluation on Hydrided LWR Fuel Cladding by Small Angle Incoherent Neutron Scattering of Hydrogen

    SciTech Connect (OSTI)

    Yan, Yong; Qian, Shuo; Littrell, Ken; Parish, Chad M; Plummer, Lee K

    2015-01-01

    A non-destructive neutron scattering method to precisely measure the uptake of hydrogen and the distribution of hydride precipitates in light water reactor (LWR) fuel cladding was developed. Zircaloy-4 cladding used in commercial LWRs was used to produce hydrided specimens. The hydriding apparatus consists of a closed stainless steel vessel that contains Zr alloy specimens and hydrogen gas. Following hydrogen charging, the hydrogen content of the hydrided specimens was measured using the vacuum hot extraction method, by which the samples with desired hydrogen concentration were selected for the neutron study. Optical microscopy shows that our hydriding procedure results in uniform distribution of circumferential hydrides across the wall. Small angle neutron incoherent scattering was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. Our study demonstrates that the hydrogen in commercial Zircaloy-4 cladding can be measured very accurately in minutes by this nondestructive method over a wide range of hydrogen concentrations from a very small amount ( 20 ppm) to over 1000 ppm. The hydrogen distribution in a tube sample was obtained by scaling the neutron scattering rate with a factor determined by a calibration process using standard, destructive direct chemical analysis methods on the specimens. This scale factor can be used in future tests with unknown hydrogen concentrations, thus providing a nondestructive method for absolute hydrogen concentration determination.

  11. Thermal hydraulic codes for LWR safety analysis - present status and future perspective

    SciTech Connect (OSTI)

    Staedtke, H.

    1997-07-01

    The aim of the present paper is to give a review on the current status and future perspective of present best-estimate Thermal Hydraulic codes. Reference is made to internationally well-established codes which have reached a certain state of maturity. The first part of the paper deals with the common basic code features with respect to the physical modelling and their numerical methods used to describe complex two-phase flow and heat transfer processes. The general predictive capabilities are summarized identifying some remaining code deficiencies and their underlying limitations. The second part discusses various areas including physical modelling, numerical techniques and informatic structure where the codes could be substantially improved.

  12. Using NDA Techniques to Improve Safeguards Metrics on Burnup Quantification and Plutonium Content in LWR SNF

    SciTech Connect (OSTI)

    Saavedra, Steven F; Charlton, William S; Solodov, Alexander A; Ehinger, Michael H

    2010-01-01

    Globally, there exists a long history in reprocessing in evaluation of the shipper/receiver difference (SRD) on spent nuclear fuel (SNF) received and processed. Typically, the declared shipper s values for uranium and plutonium in SNF (based on calculations involving the initial manufacturer s data and reactor operating history) are used as the input quantities to the head-end process of the facility. Problems have been encountered when comparing these values with measured results of the input accountability tank contents. A typical comparison yields a systematic bias indicated as a loss of 5 7 percent of the plutonium (Pu) and approximately 1 percent for the uranium (U). Studies suggest that such deviation can be attributed to the non-linear nature of the axial burnup values of the SNF. Oak Ridge National Laboratory and Texas A&M University are co-investigating the development of a new method, via Nondestructive Assay (NDA) techniques, to improve the accuracy in burnup and Pu content quantification. Two major components have been identified to achieve this objective. The first component calculates a measurement-based burnup profile along the axis of a fuel rod. Gamma-ray data is collected at numerous locations along the axis of the fuel rod using a High Purity Germanium (HPGe) detector designed for a wide range of gamma-ray energies. Using two fission products, 137Cs and 134Cs, the burnup is calculated at each measurement location and a profile created along the axis of the rod based on the individual measurement locations. The second component measures the U/Pu ratio using an HPGe detector configured for relatively low-energy gamma-rays including x-rays. Fluorescence x-rays from U and Pu are measured and compared to the U/Pu ratio determined from a destructive analysis of the sample. This will be used to establish a relationship between the measured and actual values. This relationship will be combined with the burnup analysis results to establish a relationship

  13. Surveillance of LWR spent fuel in wet storage. Final report, October 1984

    SciTech Connect (OSTI)

    Bailey, W.J.; Johnson, A.B. Jr.

    1984-10-01

    Battelle, Pacific Northwest Laboratories established a surveillance program for EPRI that documents the integrity of spent light-water reactor fuel and structural materials (spent fuel storage pool liners, racks, piping, etc.) during wet storage. The program involves providing an update on the overall performance of spent fuel in wet storage, monitoring Licensee Event Reports (LERs) for pertinent significant occurrences, identifying lead spent fuel assemblies that are of particular interest to EPRI, monitoring developments in fuel design and performance and assessing their influence on spent fuel storage characteristics, and identifying specific actions or programs that may be needed to maintain the viability of wet storage of spent fuel for extended periods. Experience to date indicates that wet storage is a well-developed technology with no associated major technological problems. Spent fuel storage pools are operated without substantial risk to the public or the plant personnel. A list of lead spent fuel assemblies is presented. Pertinent occurrences from LERs are listed. Very few fuel assemblies have suffered major mechanical damage as a result of handling operations at spent fuel storage pools. Experience to date with handling operations at spent fuel storage pools indicates that failed fuel rods and inadvertent fracturing of fuel rods can be accommodated. Minor problems have occurred with spent fuel storage pool components such as liners, racks, and piping. Surveillance continues to be needed on: (1) possible effects on handling and storage of spent fuel from extended burnup, hydrogen injection at boiling water reactors, and rod consolidation operations; (2) extended pool exposure of neutron-absorbing materials; (3) cracking of spent fuel storage pool piping at pressurized water reactors; and (4) control of impurities in spent fuel pool waters. 120 references, 13 figures, 10 tables.

  14. Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures: Revision 2015

    SciTech Connect (OSTI)

    Katoh, Yutai; Terrani, Kurt A.

    2015-08-01

    Fuels and core structures in current light water reactors (LWR’s) are vulnerable to catastrophic failure in severe accidents as unfortunately evidenced by the March 2011 Fukushima Dai-ichi Nuclear Power Plant Accident. This vulnerability is attributed primarily to the rapid oxidation kinetics of zirconium alloys in a water vapor environment at very high temperatures. Zr alloys are the primary material in LWR cores except for the fuel itself. Therefore, alternative materials with reduced oxidation kinetics as compared to zirconium alloys are sought to enable enhanced accident-tolerant fuels and cores.

  15. Hydrogen Analysis (H2A) Production Component Model

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

    selling cost given a specified after-tax internal rate of return. Key Attributes & Strengths Part of suite of H2A Models (Production, Delivery Components, Delivery Scenario). ...

  16. Anthony International: Order (2013-CE-5357)

    Broader source: Energy.gov [DOE]

    DOE ordered Anthony International to pay a $8,000 civil penalty after finding Anthony International had failed to certify that any basic models of walk-in cooler and freezer components comply with the applicable energy conservation standards.

  17. International Rectifier Corporation | Open Energy Information

    Open Energy Info (EERE)

    components that enable high performance of end products in home appliances, industrial motor-driven equipment, autos, and information technology. References: International...

  18. Material Performance of Fully-Ceramic Micro-Encapsulated Fuel under Selected LWR Design Basis Scenarios: Final Report

    SciTech Connect (OSTI)

    B. Boer; R. S. Sen; M. A. Pope; A. M. Ougouag

    2011-09-01

    The extension to LWRs of the use of Deep-Burn coated particle fuel envisaged for HTRs has been investigated. TRISO coated fuel particles are used in Fully-Ceramic Microencapsulated (FCM) fuel within a SiC matrix rather than the graphite of HTRs. TRISO particles are well characterized for uranium-fueled HTRs. However, operating conditions of LWRs are different from those of HTRs (temperature, neutron energy spectrum, fast fluence levels, power density). Furthermore, the time scales of transient core behavior during accidents are usually much shorter and thus more severe in LWRs. The PASTA code was updated for analysis of stresses in coated particle FCM fuel. The code extensions enable the automatic use of neutronic data (burnup, fast fluence as a function of irradiation time) obtained using the DRAGON neutronics code. An input option for automatic evaluation of temperature rise during anticipated transients was also added. A new thermal model for FCM was incorporated into the code; so-were updated correlations (for pyrocarbon coating layers) suitable to estimating dimensional changes at the high fluence levels attained in LWR DB fuel. Analyses of the FCM fuel using the updated PASTA code under nominal and accident conditions show: (1) Stress levels in SiC-coatings are low for low fission gas release (FGR) fractions of several percent, as based on data of fission gas diffusion in UO{sub 2} kernels. However, the high burnup level of LWR-DB fuel implies that the FGR fraction is more likely to be in the range of 50-100%, similar to Inert Matrix Fuels (IMFs). For this range the predicted stresses and failure fractions of the SiC coating are high for the reference particle design (500 {micro}mm kernel diameter, 100 {micro}mm buffer, 35 {micro}mm IPyC, 35 {micro}mm SiC, 40 {micro}mm OPyC). A conservative case, assuming 100% FGR, 900K fuel temperature and 705 MWd/kg (77% FIMA) fuel burnup, results in a 8.0 x 10{sup -2} failure probability. For a 'best-estimate' FGR fraction

  19. International Conference

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

    Internal Combustion Engine Basics Internal Combustion Engine Basics November 22, 2013 - 2:02pm Addthis Pictured here is an animation showing the basic mechanics of how an internal combustion engine works. With support from the Energy Department, General Motors researchers developed a new technology -- the Intake Valve Lift Control -- that is helping save fuel and lower emissions in the 2014 Chevy Impala. As visualized in the closeup of the graphic, the Intake Valve Lift Control can operate at

  20. Amnesty International

    ScienceCinema (OSTI)

    None

    2011-04-25

    Martin Ennals est secrétaire général d'Amnesty International et fait un discours sur les droits de l'homme

  1. Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

    SciTech Connect (OSTI)

    Farmer, Mitchell T.; Bunt, R.; Corradini, M.; Ellison, Paul B.; Francis, M.; Gabor, John D.; Gauntt, R.; Henry, C.; Linthicum, R.; Luangdilok, W.; Lutz, R.; Paik, C.; Plys, M.; Rabiti, Cristian; Rempe, J.; Robb, K.; Wachowiak, R.

    2015-01-31

    The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy’s (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

  2. Major Components of Lending

    Broader source: Energy.gov [DOE]

    The major components of a clean energy financing program are described below, centered around the characteristics and sources of capital.

  3. Reactor component automatic grapple

    DOE Patents [OSTI]

    Greenaway, Paul R.

    1982-01-01

    A grapple for handling nuclear reactor components in a medium such as liquid sodium which, upon proper seating and alignment of the grapple with the component as sensed by a mechanical logic integral to the grapple, automatically seizes the component. The mechanical logic system also precludes seizure in the absence of proper seating and alignment.

  4. Stationary turbine component with laminated skin

    DOE Patents [OSTI]

    James, Allister W.

    2012-08-14

    A stationary turbine engine component, such as a turbine vane, includes a internal spar and an external skin. The internal spar is made of a plurality of spar laminates, and the external skin is made of a plurality of skin laminates. The plurality of skin laminates interlockingly engage the plurality of spar laminates such that the external skin is located and held in place. This arrangement allows alternative high temperature materials to be used on turbine engine components in areas where their properties are needed without having to make the entire component out of such material. Thus, the manufacturing difficulties associated with making an entire component of such a material and the attendant high costs are avoided. The skin laminates can be made of advanced generation single crystal superalloys, intermetallics and refractory alloys.

  5. International Feedstock

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

    1.2.1.5 International Feedstock March 24, 2015 Feedstocks Patrick Lamers, PhD Idaho National Laboratory This presentation does not contain any proprietary, confidential, or otherwise restricted information 2 | Bioenergy Technologies Office Goal Statement Put the U.S. bioeconomy strategy in the context of global, competitive feedstock markets. * Evaluate international impacts on U.S. feedstock supply costs * Improve U.S. feedstock cost and volume projections * Leverage existing expertise and

  6. International Fellows

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

    Alexander and Lienert selected as ASM International Fellows November 6, 2013 David Alexander and Thomas Lienert of Metallurgy (MST-6) are among ASM International's 2013 Class of Fellows, who are honored for their distinguished contributions to materials science and engineering. A total of nine ASM fellows have come from Los Alamos over the years, according to the society, which is commemorating its 100th anniversary. Alexander achievements The citation for Alexander reads: "For excellence

  7. International Sunport

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

    International Programs International Programs The U.S. Department of Energy (DOE) Office of Environmental Management (EM) has a mission to complete the safe clean-up of the environmental legacy resulting from six decades of weapons production and energy research. This effort is recognized as one of the largest and most diverse and technically complex environmental clean-up operations in the world. As described in the DOE Strategic Plan, to accomplish this mission, the Department will leverage

  8. Fueling Components Testing and Certification | Department of Energy

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

    Fueling Components Testing and Certification Fueling Components Testing and Certification These slides were presented at the Onboard Storage Tank Workshop on April 29, 2010. componentstesting_certification_ostw.pdf (257.49 KB) More Documents & Publications CSA International Certification Discussion Hydrogen Technology Workshop Component and System Qualification Workshop Proceedings CODES & STANDARDS FOR THE HYDROGEN ECONOMY

  9. CSA International Certification Discussion Hydrogen Technology Workshop |

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

    Department of Energy CSA International Certification Discussion Hydrogen Technology Workshop CSA International Certification Discussion Hydrogen Technology Workshop Slides from the U.S. Department of Energy Hydrogen Component and System Qualification Workshop held November 4, 2010 in Livermore, CA. csqw_gruss.pdf (1.25 MB) More Documents & Publications Fueling Components Testing and Certification Component and System Qualification Workshop Proceedings CODES & STANDARDS FOR THE

  10. Air cooled turbine component having an internal filtration system

    DOE Patents [OSTI]

    Beeck, Alexander R.

    2012-05-15

    A centrifugal particle separator is provided for removing particles such as microscopic dirt or dust particles from the compressed cooling air prior to reaching and cooling the turbine blades or turbine vanes of a turbine engine. The centrifugal particle separator structure has a substantially cylindrical body with an inlet arranged on a periphery of the substantially cylindrical body. Cooling air enters centrifugal particle separator through the separator inlet port having a linear velocity. When the cooling air impinges the substantially cylindrical body, the linear velocity is transformed into a rotational velocity, separating microscopic particles from the cooling air. Microscopic dust particles exit the centrifugal particle separator through a conical outlet and returned to a working medium.

  11. Internal shim

    DOE Patents [OSTI]

    Barth, Clyde H.; Blizinski, Theodore W.

    2003-05-13

    An internal shim used to accurately measure spaces in conjunction with a standard small probe has a shim top and a chassis. The internal shim is adjustably fixed within the space to be measured using grippers that emerge from the chassis and which are controlled by an arm pivotably attached to the shim top. A standard small probe passes through the shim along guides on the chassis and measures the distance between the exterior of the chassis and the boundary. By summing the measurements on each side of the chassis and the width of the chassis, the dimension of the space can be determined to within 0.001 inches.

  12. Internal Dosimetry

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

    MEASUREMENT SENSITIVE DOE-STD-1121-2008 Change Notice No.1 October 2013 DOE STANDARD INTERNAL DOSIMETRY U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://energy.gov/hss/information-center/department-energy- technical-standards-program ii Change Notice 1. Internal Dosimetry DOE-STD-1121-2008 Page/Section

  13. Component and System Qualification Workshop Proceedings | Department of

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

    Energy Component and System Qualification Workshop Proceedings Component and System Qualification Workshop Proceedings Proceedings from the U.S. DOE Hydrogen Component and System Qualification Workshop, held at Sandia National Laboratory in Livermore, CA, on November 4, 2010. Component and System Qualification Workshop Proceedings (106.01 KB) More Documents & Publications CSA International Certification Discussion Hydrogen Technology Workshop Certification and Listing Process and

  14. Ceramic component for electrodes

    DOE Patents [OSTI]

    Marchant, David D.

    1979-01-01

    A ceramic component suitable for preparing MHD generator electrodes consists of HfO.sub.2 and sufficient Tb.sub.4 O.sub.7 to stabilize at least 60 volume percent of the HfO.sub.2 into the cubic structure. The ceramic component may also contain a small amount of PrO.sub.2, Yb.sub.2 O.sub.3 or a mixture of both to improve stability and electronic conductivity of the electrode. The component is highly resistant to corrosion by molten potassium seed and molten coal slag in the MHD fluid and exhibits both ionic and electronic conductivity.

  15. Montena Components | Open Energy Information

    Open Energy Info (EERE)

    Components Jump to: navigation, search Name: Montena Components Place: Rossens, Switzerland Zip: CH 1728 Product: Montena Components is a manufacturer of ultracapacitors and...

  16. Integrating Program Component Executables

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

    Integrating Program Component Executables on Distributed Memory Architectures via MPH Chris Ding and Yun He Computational Research Division, Lawrence Berkeley National Laboratory University of California, Berkeley, CA 94720, USA chqding@lbl.gov, yhe@lbl.gov Abstract A growing trend in developing large and complex ap- plications on today's Teraflop computers is to integrate stand-alone and/or semi-independent program components into a comprehensive simulation package. One example is the climate

  17. INTERNATIONAL AGREEMENTS

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

    INTERNATIONAL AGREEMENTS Signed by Secretary Spencer Abraham January 2001-December 2004 TABLE OF CONTENTS Joint Statement of ntent between the Department of Energy of the United States ofAmerica and The Ministry of Energy and Mines of the Republic ofPeru on Cooperation in the Field of Energy -Tab 1 Fifth Hemispheric Energy Ministers Meeting Mexico City, Mexico - March 9, 2001. Mexico Declaration - Energy: A Crucial Factor for Integration and Sustainable Development in the Hemisphere - Tab 2

  18. International Collaboration

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

    Chapter 6 Buildings sector energy consumption Overview Energy consumed in the buildings sector consists of residential and commercial end users and accounts for 20.1% of the total delivered energy consumed worldwide. Consumption of delivered, or site, energy contrasts with the use of the primary energy that also includes the energy used to generate and deliver electricity to individual sites such as homes, offices, or industrial plants. In the International Energy Outlook 2016 (IEO2016)

  19. International Affairs - DOE Directives, Delegations, and Requirements

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

    International Affairs

  20. Components in the Pipeline

    SciTech Connect (OSTI)

    Gorton, Ian; Wynne, Adam S.; Liu, Yan; Yin, Jian

    2011-02-24

    Scientists commonly describe their data processing systems metaphorically as software pipelines. These pipelines input one or more data sources and apply a sequence of processing steps to transform the data and create useful results. While conceptually simple, pipelines often adopt complex topologies and must meet stringent quality of service requirements that place stress on the software infrastructure used to construct the pipeline. In this paper we describe the MeDICi Integration Framework, which is a component-based framework for constructing complex software pipelines. The framework supports composing pipelines from distributed heterogeneous software components and provides mechanisms for controlling qualities of service to meet demanding performance, reliability and communication requirements.

  1. Ceramic component for electrodes

    DOE Patents [OSTI]

    Marchant, David D.; Bates, J. Lambert

    1980-01-01

    A ceramic component suitable for preparing MHD generator electrodes having the compositional formula: Y.sub.x (Mg.sub.y Cr.sub.z).sub.w Al.sub.(1-w) O.sub.3 where x=0.9 to 1.05, y=0.02 to 0.2, z=0.8 to 1.05 and w=1.0 to 0.5. The component is resistant to the formation of hydration products in an MHD environment, has good electrical conductivity and exhibits a lower electrochemical corrosion rate than do comparable compositions of lanthanum chromite.

  2. Steam boosted internal combustion engine

    SciTech Connect (OSTI)

    Green, M.A.

    1987-01-20

    A device is described to supplement the power produced by burning fuel in an internal combustion engine with steam, the device comprising: a means for producing a constant flow of water past a boiler means; a means for allowing the water to flow in the direction of the boiler; a boiler means external to the internal combustion engine to convert the water into superheated steam; a means for controlling the pressure of the water such that the water pressure is greater than the pressure of the steam produced by the boiler; and a means for injection of the superheated steam directly into a cylinder of the internal combustion engine, a means for producing a constant flow of water at a pressure greater than the pressure of the superheated steam, wherein the constant flow means at greater pressure comprises a chamber with a gaseous component, with the gaseous component being of constant volume and exerting constant pressure upon water within the chamber.

  3. Anthony International: Proposed Penalty (2013-CE-5357)

    Broader source: Energy.gov [DOE]

    DOE alleged in a Notice of Proposed Civil Penalty that Anthony International failed to certify a variety of walk-in cooler or freezer components as compliant with the applicable energy conservation standards.

  4. Materials & Components Compatibility

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

    Components Compatibility - 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 Advanced

  5. SunConnex International BV | Open Energy Information

    Open Energy Info (EERE)

    Sector: Solar Product: Dutch PV installer established in 1989; supplier of modules, inverters, and components necessary to build solar plants. References: SunConnex International...

  6. Component for thermoelectric generator

    DOE Patents [OSTI]

    Purdy, David L.

    1977-01-01

    In a thermoelectric generator, a component comprises a ceramic insulator, having over limited areas thereof, each area corresponding to a terminal end of thermoelectric wires, a coating of a first metal which adheres to the insulator, and an electrical thermoelectric junction including a second metal which wets said first metal and adheres to said terminal ends but does not wet said insulator, and a cloth composed of electrically insulating threads interlaced with thermoelectric wires.

  7. Solid state lighting component

    DOE Patents [OSTI]

    Yuan, Thomas; Keller, Bernd; Ibbetson, James; Tarsa, Eric; Negley, Gerald

    2010-10-26

    An LED component comprising an array of LED chips mounted on a planar surface of a submount with the LED chips capable of emitting light in response to an electrical signal. The LED chips comprise respective groups emitting at different colors of light, with each of the groups interconnected in a series circuit. A lens is included over the LED chips. Other embodiments can comprise thermal spreading structures included integral to the submount and arranged to dissipate heat from the LED chips.

  8. Solid state lighting component

    DOE Patents [OSTI]

    Keller, Bernd; Ibbetson, James; Tarsa, Eric; Negley, Gerald; Yuan, Thomas

    2012-07-10

    An LED component comprising an array of LED chips mounted on a planar surface of a submount with the LED chips capable of emitting light in response to an electrical signal. The LED chips comprise respective groups emitting at different colors of light, with each of the groups interconnected in a series circuit. A lens is included over the LED chips. Other embodiments can comprise thermal spreading structures included integral to the submount and arranged to dissipate heat from the LED chips.

  9. Injection molded component

    DOE Patents [OSTI]

    James, Allister W; Arrell, Douglas J

    2014-09-30

    An intermediate component includes a first wall member, a leachable material layer, and a precursor wall member. The first wall member has an outer surface and first connecting structure. The leachable material layer is provided on the first wall member outer surface. The precursor wall member is formed adjacent to the leachable material layer from a metal powder mixed with a binder material, and includes second connecting structure.

  10. Surface mount component jig

    DOE Patents [OSTI]

    Kronberg, James W.

    1990-08-07

    A device for bending and trimming the pins of a dual-inline-package component and the like for surface mounting rather than through mounting to a circuit board comprises, in a first part, in pin cutter astride a holder having a recess for holding the component, a first spring therebetween, and, in a second part, two flat members pivotally interconnected by a hinge and urged to an upward peaked position from a downward peaked position by a second spring. As a downward force is applied to the pin cutter it urges the holder downward, assisted by the first spring and a pair of ridges riding on shoulders of the holder, to carry the component against the upward peaked flat members which guide the pins outwardly. As the holder continues downwardly, the flat members pivot to the downward peaked position bending the pins upwardly against the sides of the holder. When the downward movement is met with sufficient resistance, the ridges of the pin cutter ride over the holder's shoulders to continue downward to cut any excess length of pin.

  11. Energetic component treatability study

    SciTech Connect (OSTI)

    Gildea, P.D.; Brandon, S.L.; Brown, B.G. [and others

    1997-11-01

    The effectiveness of three environmentally sound processes for small energetic component disposal was examined experimentally in this study. The three destruction methods, batch reactor supercritical water oxidation, sodium hydroxide base hydrolysis and calcium carbonate cookoff were selected based on their potential for producing a clean solid residue and minimum release of toxic gases after component detonation. The explosive hazard was destroyed by all three processes. Batch supercritical water oxidation destroyed both the energetics and organics. Further development is desired to optimize process parameters. Sodium hydroxide base hydrolysis and calcium carbonate cookoff results indicated the potential for scrubbing gaseous detonation products. Further study and testing are needed to quantify the effectiveness of these later two processes for full-scale munition destruction. The preliminary experiments completed in this study have demonstrated the promise of these three processes as environmentally sound technologies for energetic component destruction. Continuation of these experimental programs is strongly recommended to optimize batch supercritical water oxidation processing, and to fully develop the sodium hydroxide base hydrolysis and calcium carbonate cookoff technologies.

  12. Sprayed skin turbine component

    DOE Patents [OSTI]

    Allen, David B

    2013-06-04

    Fabricating a turbine component (50) by casting a core structure (30), forming an array of pits (24) in an outer surface (32) of the core structure, depositing a transient liquid phase (TLP) material (40) on the outer surface of the core structure, the TLP containing a melting-point depressant, depositing a skin (42) on the outer surface of the core structure over the TLP material, and heating the assembly, thus forming both a diffusion bond and a mechanical interlock between the skin and the core structure. The heating diffuses the melting-point depressant away from the interface. Subsurface cooling channels (35) may be formed by forming grooves (34) in the outer surface of the core structure, filling the grooves with a fugitive filler (36), depositing and bonding the skin (42), then removing the fugitive material.

  13. Component failure data handbook

    SciTech Connect (OSTI)

    Gentillon, C.D.

    1991-04-01

    This report presents generic component failure rates that are used in reliability and risk studies of commercial nuclear power plants. The rates are computed using plant-specific data from published probabilistic risk assessments supplemented by selected other sources. Each data source is described. For rates with four or more separate estimates among the sources, plots show the data that are combined. The method for combining data from different sources is presented. The resulting aggregated rates are listed with upper bounds that reflect the variability observed in each rate across the nuclear power plant industry. Thus, the rates are generic. Both per hour and per demand rates are included. They may be used for screening in risk assessments or for forming distributions to be updated with plant-specific data.

  14. Internal combustion engine

    SciTech Connect (OSTI)

    Perrin, G.; Bergmann, H.

    1984-06-12

    An externally auto-ignited four-stroke internal combustion engine which includes a combustion chamber disposed in an upper surface of a piston such that, in an upper dead-center position of the piston, the combustion chamber receives almost all of the fuel-air mixture. The combustion chamber includes a planar bottom portion and has a cross-sectional shape of a truncated cone expanding in a direction of the cylinder head. The internal combustion engine also includes a recess or depression provided in the cylinder head and disposed eccentrically with respect to a longitudinal center axis of the cylinder. The depression or recess in the cylinder head has the shape of a truncated cone expanding in a direction of the piston, with a spark plug projecting or penetrating into the recess or depression in the cylinder head. In order to enable the achievement of good combustion, increased overall engine performance, and the minimum amount of harmful components in the exhaust gases from the engine when different types of fuel are used, predetermined constructional parameters are selected with respect to the combustion chamber and recess or depression disposed above the combustion chamber as well as the disposition of the combustion chamber with respect to a longitudinal center axis of the cylinder.

  15. Investigations into High Temperature Components and Packaging

    SciTech Connect (OSTI)

    Marlino, L.D.; Seiber, L.E.; Scudiere, M.B.; M.S. Chinthavali, M.S.; McCluskey, F.P.

    2007-12-31

    The purpose of this report is to document the work that was performed at the Oak Ridge National Laboratory (ORNL) in support of the development of high temperature power electronics and components with monies remaining from the Semikron High Temperature Inverter Project managed by the National Energy Technology Laboratory (NETL). High temperature electronic components are needed to allow inverters to operate in more extreme operating conditions as required in advanced traction drive applications. The trend to try to eliminate secondary cooling loops and utilize the internal combustion (IC) cooling system, which operates with approximately 105 C water/ethylene glycol coolant at the output of the radiator, is necessary to further reduce vehicle costs and weight. The activity documented in this report includes development and testing of high temperature components, activities in support of high temperature testing, an assessment of several component packaging methods, and how elevated operating temperatures would impact their reliability. This report is organized with testing of new high temperature capacitors in Section 2 and testing of new 150 C junction temperature trench insulated gate bipolar transistor (IGBTs) in Section 3. Section 4 addresses some operational OPAL-GT information, which was necessary for developing module level tests. Section 5 summarizes calibration of equipment needed for the high temperature testing. Section 6 details some additional work that was funded on silicon carbide (SiC) device testing for high temperature use, and Section 7 is the complete text of a report funded from this effort summarizing packaging methods and their reliability issues for use in high temperature power electronics. Components were tested to evaluate the performance characteristics of the component at different operating temperatures. The temperature of the component is determined by the ambient temperature (i.e., temperature surrounding the device) plus the

  16. Futuristic concepts in engines and components

    SciTech Connect (OSTI)

    1995-12-31

    This publication includes papers on two-stroke engines and components, Brayton Stirling and Otto Cycles, alternative cycles, advanced combustion, and other related topics. Contents include: Paving the way to controlled combustion engines (CCE); A new class of stratified-charge internal combustion engine; Internal combustion (IC) engine with minimum number of moving parts; New type of heat engine -- externally heated air engine; A porous media burner for reforming methanol for fuel cell powered electric vehicles; Using a Stirling engine simulation program as a regenerator design aid; In-cylinder regenerated engines; High speed electronic fuel injection for direct injected rotary engine; and The characteristics of fuel consumption and exhaust emissions of the side exhaust port rotary engine.

  17. Cooling system for electronic components

    DOE Patents [OSTI]

    Anderl, William James; Colgan, Evan George; Gerken, James Dorance; Marroquin, Christopher Michael; Tian, Shurong

    2015-12-15

    Embodiments of the present invention provide for non interruptive fluid cooling of an electronic enclosure. One or more electronic component packages may be removable from a circuit card having a fluid flow system. When installed, the electronic component packages are coincident to and in a thermal relationship with the fluid flow system. If a particular electronic component package becomes non-functional, it may be removed from the electronic enclosure without affecting either the fluid flow system or other neighboring electronic component packages.

  18. International Commitments Management

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2008-11-18

    This Order establishes a process to manage the Department's International Commitments under the administrative direction of the Office of Policy and International Affairs. No cancellation.

  19. Student Trainee (Engineering)- Intern

    Broader source: Energy.gov [DOE]

    The purpose of the Pathways Intern Employment Program is to provide the intern with exposure to public service, enhance educational experience, and support educational goals. The program is...

  20. Advanced LWR Nuclear Fuel Development

    Energy Savers [EERE]

    ... clustering is modeled based on molecular dynamics simulation 3. The ... for hybrid welding processes - Hybrid laser weld processing model to optimize the ...

  1. Advanced LWR Nuclear Fuel Development

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

    ... - X-ray microtomography * Chemical mapping - TOF-SIMSXPS - X-ray diffraction - FTIRRaman * Mechanical mapping - Nanoindenter XMT of EPR Nanoindenter 0 20 40 60 80 100 P, % 1 10 ...

  2. 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 ...

  3. Advanced LWR Nuclear Fuel Development

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

    ... The white rectangle shows an area that can be EBSD scanned without specimen rotation operations. c) A typical EBSD scan of the cracked area. Scanning electron microscopy (SEM) was ...

  4. Sandia National Laboratories: Summer institute introduces Sandia interns to

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

    NW work By Sue Major Holmes Thursday, September 01, 2016 Summer institute introduces Sandia interns to NW work Summer institute introduces Sandia interns to NW work The "sprint" part of Sandia's summer NW SPRINT competition for interns was more of an all-out run. Three intern teams, augmented by Sandia staff, designed a nuclear weapon component, built it with additive manufacturing techniques, and tested it on a centrifuge - spending eight weeks on work that Advanced Mechanical

  5. Renewable Energy Resources Inc formerly Internal Hydro International...

    Open Energy Info (EERE)

    Inc formerly Internal Hydro International Inc Jump to: navigation, search Name: Renewable Energy Resources Inc (formerly Internal Hydro International Inc) Place: Tampa, Florida...

  6. Irradiation Planning for Fully-Ceramic Micro-encsapsulated fuel in ATR at LWR-relevant conditions: year-end report on FY-2011

    SciTech Connect (OSTI)

    Abderrafi M. Ougouag; R. Sonat Sen; Michael A. Pope; Brian Boer

    2011-09-01

    This report presents the estimation of required ATR irradiation levels for the DB-FCM fuel design (fueled with Pu and MAs). The fuel and assembly designs are those considered in a companion report [R. S. Sen et al., FCR&D-2011- 00037 or INL/EXT-11-23269]. These results, pertaining to the DB-FCM fuel, are definitive in as much as the design of said fuel is definitive. In addition to the work performed, as required, for DB-FCM fuel, work has started in a preliminary fashion on single-cell UO2 and UN fuels. These latter activities go beyond the original charter of this project and although the corresponding work is incomplete, significant progress has been achieved. However, in this context, all that has been achieved is only preliminary because the corresponding fuel designs are neither finalized nor optimized. In particular, the UO2 case is unlikely to result in a viable fuel design if limited to enrichment at or under 20 weight % in U-235. The UN fuel allows reasonable length cycles and is likely to make an optimal design possible. Despite being limited to preliminary designs and offering only preliminary conclusions, the irradiation planning tasks for UO2 and UN fuels that are summarized in this report are useful to the overall goal of devising and deploying FCM-LWR fuel since the methods acquired and tested in this project and the overall procedure for planning will be available for planning tests for the finalized fuel design. Indeed, once the fuel design is finalized and the expected burnup level is determined, the methodology that has been assembled will allow the prompt finalization of the neutronic planning of the irradiation experiment and would provide guidance on the expected experimental performance of the fuel. Deviations from the expected behavior will then have to be analyzed and the outcome of the analysis may be corrections or modifications for the assessment models as well as, possibly, fuel design modifications, and perhaps even variation of

  7. STEP Intern Job Description

    Broader source: Energy.gov [DOE]

    STEP Intern Job Description, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  8. Multi-tipped optical component

    DOE Patents [OSTI]

    D'Urso, Brian R.; Simpson, John T.

    2010-04-13

    An optical component has a plurality of parallel noncontiguous optical conduits of at least one protrusive phase material embedded in a recessive phase material that acts as a support structure. The optical conduits extend from a proximal surface to a distal surface of the optical component. The distal surface has a plurality of spaced apart surface features of the protrusive phase material. Each independent optical conduits act as waveguides for a wavelength or range of wavelengths. The optical component can be formed such that the protruding surface features at the distal end of the component form an ordered array. An optical instrument can include the optical component in conjunction with a light source for illuminating a sample and a detector in optical communication optical component via the optical conduits.

  9. Multi-component assembly casting

    DOE Patents [OSTI]

    James, Allister W.

    2015-10-13

    Multi-component vane segment and method for forming the same. Assembly includes: positioning a pre-formed airfoil component (12) and a preformed shroud heat resistant material (18) in a mold, wherein the airfoil component (12) and the shroud heat resistant material (18) each comprises an interlocking feature (24); preheating the mold; introducing molten structural material (46) into the mold; and solidifying the molten structural material such that it interlocks the pre-formed airfoil component (12) with respect to the preformed shroud heat resistant material (18) and is effective to provide structural support for the shroud heat resistant material (18). Surfaces between the airfoil component (12) and the structural material (46), between the airfoil component (12) and the shroud heat resistant material (18), and between the shroud heat resistant material (18) and the structural material (46) are free of metallurgical bonds.

  10. Chemical kinetic modeling of component mixtures relevant to gasoline

    SciTech Connect (OSTI)

    Mehl, M; Curran, H J; Pitz, W J; Westbrook, C K

    2009-02-13

    Real fuels are complex mixtures of thousands of hydrocarbon compounds including linear and branched paraffins, naphthenes, olefins and aromatics. It is generally agreed that their behavior can be effectively reproduced by simpler fuel surrogates containing a limited number of components. In this work, a recently revised version of the kinetic model by the authors is used to analyze the combustion behavior of several components relevant to gasoline surrogate formulation. Particular attention is devoted to linear and branched saturated hydrocarbons (PRF mixtures), olefins (1-hexene) and aromatics (toluene). Model predictions for pure components, binary mixtures and multi-component gasoline surrogates are compared with recent experimental information collected in rapid compression machine, shock tube and jet stirred reactors covering a wide range of conditions pertinent to internal combustion engines. Simulation results are discussed focusing attention on the mixing effects of the fuel components.

  11. Heat treating of manufactured components

    SciTech Connect (OSTI)

    Ripley, Edward B.

    2012-05-22

    An apparatus for heat treating manufactured components using microwave energy and microwave susceptor material is disclosed. The system typically includes an insulating vessel placed within a microwave applicator chamber. A moderating material is positioned inside the insulating vessel so that a substantial portion of the exterior surface of each component for heat treating is in contact with the moderating material.

  12. International photovoltaic products and manufacturers directory, 1995

    SciTech Connect (OSTI)

    Shepperd, L.W.

    1995-11-01

    This international directory of more than 500 photovoltaic-related manufacturers is intended to guide potential users of photovoltaics to sources for systems and their components. Two indexes help the user to locate firms and materials. A glossary describes equipment and terminology commonly used in the photovoltaic industry.

  13. Apparatus for remotely handling components

    DOE Patents [OSTI]

    Szkrybalo, Gregory A.; Griffin, Donald L.

    1994-01-01

    The inventive apparatus for remotely handling bar-like components which define a longitudinal direction includes a gripper mechanism for gripping the component including first and second gripper members longitudinally fixedly spaced from each other and oriented parallel to each other in planes transverse to the longitudinal direction. Each gripper member includes a jaw having at least one V-groove with opposing surfaces intersecting at a base and extending radially relative to the longitudinal direction for receiving the component in an open end between the opposing surfaces. The V-grooves on the jaw plate of the first and second gripper members are aligned in the longitudinal direction to support the component in the first and second gripper members. A jaw is rotatably mounted on and a part of each of the first and second gripper members for selectively assuming a retracted mode in which the open end of the V-groove is unobstructed and active mode in which the jaw spans the open end of the V-groove in the first and second gripper members. The jaw has a locking surface for contacting the component in the active mode to secure the component between the locking surface of the jaw and the opposing surfaces of the V-groove. The locking surface has a plurality of stepped portions, each defining a progressively decreasing radial distance between the base of the V-groove and the stepped portion opposing the base to accommodate varying sizes of components.

  14. Ceramic component for MHD electrode

    DOE Patents [OSTI]

    Marchant, David D.; Bates, Junior L.

    1981-01-01

    A ceramic component which exhibits electrical conductivity down to near room temperatures has the formula: Hf.sub.x In.sub.y A.sub.z O.sub.2 where x=0.1 to 0.4, y=0.3 to 0.6, z=0.1 to 0.4 and A is a lanthanide rare earth or yttrium. The component is suitable for use in the fabrication of MHD electrodes or as the current leadout portion of a composite electrode with other ceramic components.

  15. Proceedings of the international workshop on spallation materials technology

    SciTech Connect (OSTI)

    Mansur, L.K.; Ullmaier, H. [comps.] [comps.

    1996-10-01

    This document contains papers which were presented at the International Workshop on Spallation Materials Technology. Topics included: overviews and thermal response; operational experience; materials experience; target station and component design; particle transport and damage calculations; neutron sources; and compatibility.

  16. International Energy Statistics - EIA

    Gasoline and Diesel Fuel Update (EIA)

    International > International Energy Statistics International Energy Statistics Petroleum Production | Annual Monthly/Quarterly Consumption | Annual Monthly/Quarterly Capacity | Bunker Fuels | Stocks | Annual Monthly/Quarterly Reserves | Imports | Annual Monthly/Quarterly Exports | CO2 Emissions | Heat Content Natural Gas All Flows | Production | Consumption | Reserves | Imports | Exports | Carbon Dioxide Emissions | Heat Content Coal All Flows | Production | Consumption | Reserves | Imports

  17. Advanced Component Research Facility (ACRES)

    SciTech Connect (OSTI)

    Bohn, M.

    1980-07-01

    A detailed description of the SERI Advanced Component Research Facility (ACRES) is given. Background information explicates the facility's history, developed around the two Omnium-G parabolic dish concentrators. The Omnium-G concentrators and electrical power plant are described. The purpose and a detailed descripttion of ACRES is also given. Included is a description of the measurement capabilities, the controls, and each component of the facility.

  18. (Durability of building materials and components)

    SciTech Connect (OSTI)

    Naus, D.J.

    1990-11-27

    The traveler participated in the fourth meeting of RILEM 100-TSL, Techniques for Service Life Prediction,'' and The Fifth International Conference on Durability of Building Materials and Components.'' In addition, the traveler met with staff members at Taywood Engineering Ltd., Electricite de France, and AEA Technology. The meeting pertained to performance of concrete materials in nuclear power plant structures, time variation of concrete material properties, methods for evaluating concrete structures, and modeling to predict the effects of degradation factors on concrete materials. As many of the concrete structures in general civil engineering applications as well as nuclear power plant applications in Europe are aging, there is increasing emphasis on assessing the durability of these structures. Information was provided of direct application to the Structural Aging Program which would not have been available without these visits. Of equal, or possibly more importance, was the individual contacts established at the organizations visited. Each organization was extremely interested in both the approach and scope of the Structural Aging Program and requested that they be informed of progress. The initial steps were taken to cooperate with several of these researchers and this should help the Structural Aging Program keep abreast of related European activities. In summary, information obtained during this trip will benefit the ongoing Structural Aging Program by informing Oak Ridge National Laboratory (ORNL) of the extensive European research programs addressing the durability of concrete structures, and also by forming and strengthening acquaintances with counterparts in other countries, thus enhancing the basis for possible international cooperation.

  19. Synergistic failure of BWR internals

    SciTech Connect (OSTI)

    A. G. Ware; T. Y. Chang

    1999-10-25

    Boiling Water Reactor (BWR) core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. An initial phase has been completed in which background material was gathered and evaluated, and potential accident sequences were identified. A second phase is underway to perform a simplified, quantitative probabilistic risk assessment on a representative high-power BWR/4. Results of the initial study conducted on the jet pumps show that any cascading failures would not result in a significant increase in the core damage frequency. The methodology is currently being extended to other major reactor internals components.

  20. Synergistic Failure of BWR Internals

    SciTech Connect (OSTI)

    Ware, Arthur Gates; Chang, T-Y

    1999-10-01

    Boiling Water Reactor (BWR) core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. An initial phase has been completed in which background material was gathered and evaluated, and potential accident sequences were identified. A second phase is underway to perform a simplified, quantitative probabilistic risk assessment on a representative high-power BWR/4. Results of the initial study conducted on the jet pumps show that any cascading failures would not result in a significant increase in the core damage frequency. The methodology is currently being extended to other major reactor internals components.

  1. Transducer for downhole drilling components

    DOE Patents [OSTI]

    Hall, David R; Fox, Joe R

    2006-05-30

    A robust transmission element for transmitting information between downhole tools, such as sections of drill pipe, in the presence of hostile environmental conditions, such as heat, dirt, rocks, mud, fluids, lubricants, and the like. The transmission element maintains reliable connectivity between transmission elements, thereby providing an uninterrupted flow of information between drill string components. A transmission element is mounted within a recess proximate a mating surface of a downhole drilling component, such as a section of drill pipe. The transmission element may include an annular housing forming a trough, an electrical conductor disposed within the trough, and an MCEI material disposed between the annular housing and the electrical conductor.

  2. An Internal Coaxil Cable Seal System

    DOE Patents [OSTI]

    Hall, David R.; Hall, Jr., H. Tracy; Pixton, David; Dahlgren, Scott; Sneddon, Cameron; Briscoe, Michael; Fox, Joe

    2004-12-23

    The invention is a seal system for a coaxial cable more specifically an internal seal system placed within the coaxial cable and its constituent components. A series of seal stacks including flexible rigid rings and elastomeric rings are placed on load bearing members within the coaxial cable. The current invention is adapted to seal the annular space between the coaxial cable and an electrical contact passing there through. The coaxial cable is disposed within drilling components to transmit electrical signals between drilling components within a drill string. During oil and gas exploration, a drill string can see a range of pressures and temperatures thus resulting in multiple combinations of temperature and pressure and increasing the difficulty of creating a robust seal for all combinations. The seal system can be used in a plurality of downhole components, such as sections of pipe in a drill string, drill collars, heavy weight drill pipe, and jars.

  3. International safeguards data authentication

    SciTech Connect (OSTI)

    Melton, R.B.; Smith, C.E.; DeLand, S.M.; Manatt, D.R.

    1996-07-01

    The International Safeguards community is becoming increasingly reliant on information stored in electronic form. In international monitoring and related activities it must be possible to verify and maintain the integrity of this electronic information. This paper discusses the use of data authentication technology to assist in accomplishing this task. The paper provides background information, identifies the relevance to international safeguards, discusses issues related to export controls, algorithm patents, key management and the use of commercial vs. custom software.

  4. International petroleum statistics report

    SciTech Connect (OSTI)

    1996-08-01

    This report provides information on current international petroleum production, demand, imports, and stocks. World oil demand and OECD demand data are presented for the years 1970 thru 1995.

  5. Internal Revenue Service

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

    ode X SCHEDULE A (Form 5500) Department of the Treasury Internal Revenue Service Department of Labor Employee Benefits Security Administration Pension Benefit...

  6. International Subcommittee Report

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

    Report Dr. Regis A. Matzie, Chair NEAC Meeting December 10, 2014 1 Externalities of Nuclear Power Important International Considerations Safety - because of the potential...

  7. Native Intern Profile Page

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

    The intern will work with the executive management teams to solve other problems as they arise. Morgan Gray Tribal A liation: Chickasaw Nation University: Oklahoma State University ...

  8. EM International. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1993-07-01

    It is the intent of EM International to describe the Office of Environmental Restoration and Waste Management`s (EM`s) various roles and responsibilities within the international community. Cooperative agreements and programs, descriptions of projects and technologies, and synopses of visits to international sites are all highlighted in this semiannual journal. Focus on EM programs in this issue is on international collaboration in vitrification projects. Technology highlights covers: in situ sealing for contaminated sites; and remote sensors for toxic pollutants. Section on profiles of countries includes: Arctic contamination by the former Soviet Union, and EM activities with Germany--cooperative arrangements.

  9. Large Component Removal/Disposal

    SciTech Connect (OSTI)

    Wheeler, D. M.

    2002-02-27

    This paper describes the removal and disposal of the large components from Maine Yankee Atomic Power Plant. The large components discussed include the three steam generators, pressurizer, and reactor pressure vessel. Two separate Exemption Requests, which included radiological characterizations, shielding evaluations, structural evaluations and transportation plans, were prepared and issued to the DOT for approval to ship these components; the first was for the three steam generators and one pressurizer, the second was for the reactor pressure vessel. Both Exemption Requests were submitted to the DOT in November 1999. The DOT approved the Exemption Requests in May and July of 2000, respectively. The steam generators and pressurizer have been removed from Maine Yankee and shipped to the processing facility. They were removed from Maine Yankee's Containment Building, loaded onto specially designed skid assemblies, transported onto two separate barges, tied down to the barges, th en shipped 2750 miles to Memphis, Tennessee for processing. The Reactor Pressure Vessel Removal Project is currently under way and scheduled to be completed by Fall of 2002. The planning, preparation and removal of these large components has required extensive efforts in planning and implementation on the part of all parties involved.

  10. International Program Action Table - October 2012 | Department...

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

    Communication & Engagement International Programs International Program Action Table - October 2012 International Program Action Table - October 2012 International Program ...

  11. NEAC International Subcommittee Recommendations

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

    International Subcommittee Recommendations December 2014 Background Externalities of nuclear power are major considerations in the international arena. These externalities are primarily geopolitical considerations and considerations related to: * Safety of nuclear power plants - because of the potential impact that severe accidents can have on the nuclear industry globally; * Energy security - particularly in countries with little domestic energy resources because of the stable and reliable

  12. Component Modeling Approach Software Tool

    SciTech Connect (OSTI)

    2010-08-23

    The Component Modeling Approach Software Tool (CMAST) establishes a set of performance libraries of approved components (frames, glass, and spacer) which can be accessed for configuring fenestration products for a project, and btaining a U-factor, Solar Heat Gain Coefficient (SHGC), and Visible Transmittance (VT) rating for those products, which can then be reflected in a CMA Label Certificate for code compliance. CMAST is web-based as well as client-based. The completed CMA program and software tool will be useful in several ways for a vast array of stakeholders in the industry: Generating performance ratings for bidding projects Ascertaining credible and accurate performance data Obtaining third party certification of overall product performance for code compliance

  13. Nuclear component horizontal seismic restraint

    DOE Patents [OSTI]

    Snyder, Glenn J.

    1988-01-01

    A nuclear component horizontal seismic restraint. Small gaps limit horizontal displacement of components during a seismic occurrence and therefore reduce dynamic loadings on the free lower end. The reactor vessel and reactor guard vessel use thicker section roll-forged rings welded between the vessel straight shell sections and the bottom hemispherical head sections. The inside of the reactor guard vessel ring forging contains local vertical dovetail slots and upper ledge pockets to mount and retain field fitted and installed blocks. As an option, the horizontal displacement of the reactor vessel core support cone can be limited by including shop fitted/installed local blocks in opposing alignment with the reactor vessel forged ring. Beams embedded in the wall of the reactor building protrude into apertures in the thermal insulation shell adjacent the reactor guard vessel ring and have motion limit blocks attached thereto to provide to a predetermined clearance between the blocks and reactor guard vessel ring.

  14. Component Modeling Approach Software Tool

    Energy Science and Technology Software Center (OSTI)

    2010-08-23

    The Component Modeling Approach Software Tool (CMAST) establishes a set of performance libraries of approved components (frames, glass, and spacer) which can be accessed for configuring fenestration products for a project, and btaining a U-factor, Solar Heat Gain Coefficient (SHGC), and Visible Transmittance (VT) rating for those products, which can then be reflected in a CMA Label Certificate for code compliance. CMAST is web-based as well as client-based. The completed CMA program and software toolmore » will be useful in several ways for a vast array of stakeholders in the industry: Generating performance ratings for bidding projects Ascertaining credible and accurate performance data Obtaining third party certification of overall product performance for code compliance« less

  15. Fueling Components Testing and Certification

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

    Standards and Codes * National Recognized Standards * Enforceable Docs by 2012 * Code Cycle 2012 Vehicles ∙ Commercialization 2015 ∙ 50,000 by 2017 ∙ Consumer price ∙ 80% in CA Infrastructure ∙ 200 Stations in CA ∙ Accurate and Safe Equipment ∙ Commercial Venture ∙ Station Certification Implementation ∙ Component Certification * Public Awareness * General Education ∙ Technician Training ∙ Safety, Reliability and Accurate Evolving Hydrogen Vehicle Industry 3 Time Line -

  16. Energy Storage Components and Systems

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

    Components and Systems - 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 Advanced

  17. Laser ultrasonic multi-component imaging

    SciTech Connect (OSTI)

    Williams, Thomas K.; Telschow, Kenneth

    2011-01-25

    Techniques for ultrasonic determination of the interfacial relationship of multi-component systems are discussed. In implementations, a laser energy source may be used to excite a multi-component system including a first component and a second component at least in partial contact with the first component. Vibrations resulting from the excitation may be detected for correlation with a resonance pattern indicating if discontinuity exists at the interface of the first and second components.

  18. International petroleum statistics report

    SciTech Connect (OSTI)

    1995-10-01

    The International Petroleum Statistics Report is a monthly publication that provides current international oil data. This report presents data on international oil production, demand, imports, exports and stocks. The report has four sections. Section 1 contains time series data on world oil production, and on oil demand and stocks in the Organization for Economic Cooperation and Development (OECD). Section 2 presents an oil supply/demand balance for the world, in quarterly intervals for the most recent two years. Section 3 presents data on oil imports by OECD countries. Section 4 presents annual time series data on world oil production and oil stocks, demand, and trade in OECD countries.

  19. International energy annual 1996

    SciTech Connect (OSTI)

    1998-02-01

    The International Energy Annual presents an overview of key international energy trends for production, consumption, imports, and exports of primary energy commodities in over 220 countries, dependencies, and areas of special sovereignty. Also included are population and gross domestic product data, as well as prices for crude oil and petroleum products in selected countries. Renewable energy reported in the International Energy Annual includes hydroelectric power, geothermal, solar, and wind electric power, biofuels energy for the US, and biofuels electric power for Brazil. New in the 1996 edition are estimates of carbon dioxide emissions from the consumption of petroleum and coal, and the consumption and flaring of natural gas. 72 tabs.

  20. Electric Drive Component Manufacturing Facilities | Department...

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

    Component Manufacturing Facilities Electric Drive Component Manufacturing Facilities 2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review ...

  1. Electric Drive Component Manufacturing Facilities | Department...

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

    Component Manufacturing Facilities Electric Drive Component Manufacturing Facilities 2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review ...

  2. Transformer Resilience and Advanced Components (TRAC) Program...

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

    OE's Transformer Resilience and Advanced Components (TRAC) program supports modernization ... which are a critical component of the electricity delivery system, are a concern because ...

  3. Porous templated pyrolytic carbons as electrocatalyst components...

    Office of Scientific and Technical Information (OSTI)

    Porous templated pyrolytic carbons as electrocatalyst components. Citation Details In-Document Search Title: Porous templated pyrolytic carbons as electrocatalyst components. ...

  4. Certification of alternative aviation fuels and blend components

    SciTech Connect (OSTI)

    Wilson III, George R. ); Edwards, Tim; Corporan, Edwin ); Freerks, Robert L. )

    2013-01-15

    Aviation turbine engine fuel specifications are governed by ASTM International, formerly known as the American Society for Testing and Materials (ASTM) International, and the British Ministry of Defence (MOD). ASTM D1655 Standard Specification for Aviation Turbine Fuels and MOD Defence Standard 91-91 are the guiding specifications for this fuel throughout most of the world. Both of these documents rely heavily on the vast amount of experience in production and use of turbine engine fuels from conventional sources, such as crude oil, natural gas condensates, heavy oil, shale oil, and oil sands. Turbine engine fuel derived from these resources and meeting the above specifications has properties that are generally considered acceptable for fuels to be used in turbine engines. Alternative and synthetic fuel components are approved for use to blend with conventional turbine engine fuels after considerable testing. ASTM has established a specification for fuels containing synthesized hydrocarbons under D7566, and the MOD has included additional requirements for fuels containing synthetic components under Annex D of DS91-91. New turbine engine fuel additives and blend components need to be evaluated using ASTM D4054, Standard Practice for Qualification and Approval of New Aviation Turbine Fuels and Fuel Additives. This paper discusses these specifications and testing requirements in light of recent literature claiming that some biomass-derived blend components, which have been used to blend in conventional aviation fuel, meet the requirements for aviation turbine fuels as specified by ASTM and the MOD. The 'Table 1' requirements listed in both D1655 and DS91-91 are predicated on the assumption that the feedstocks used to make fuels meeting these requirements are from approved sources. Recent papers have implied that commercial jet fuel can be blended with renewable components that are not hydrocarbons (such as fatty acid methyl esters). These are not allowed blend

  5. Rotor component displacement measurement system

    DOE Patents [OSTI]

    Mercer, Gary D.; Li, Ming C.; Baum, Charles R.

    2003-05-27

    A measuring system for measuring axial displacement of a tube relative to an axially stationary component in a rotating rotor assembly includes at least one displacement sensor adapted to be located normal to a longitudinal axis of the tube; an insulated cable system adapted for passage through the rotor assembly; a rotatable proximitor module located axially beyond the rotor assembly to which the cables are connected; and a telemetry system operatively connected to the proximitor module for sampling signals from the proximitor module and forwarding data to a ground station.

  6. International petroleum statistics report

    SciTech Connect (OSTI)

    1996-03-01

    This report presents data on international oil production, demand, imports, exports, and stocks. World oil production and OECD demand data are for the years 1970 through 1994; OECD stocks from 1973 through 1994; and OECD trade from 1984 through 1994.

  7. International petroleum statistics report

    SciTech Connect (OSTI)

    1996-12-01

    This report presents data on international oil production, demand, imports, and stocks. World oil production and OECD demand data are for the years 1970 through 1995; stocks from 1973 through 1995, and trade from 1985 through 1995.

  8. Internal Controls Evaluations

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

    4, 2016 U.S. DEPARTMENT OF ENERGY Internal Control Evaluations Fiscal Year 2016 Guidance Page | 2 Table of Contents I. Introduction .............................................................................................................................................. 4 A. Background ......................................................................................................................................... 4 B. New for FY

  9. International resources law

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    This book covers: Historical origins of civil code legal systems; Modern civil law practice for mineral lawyers; Treaties and agreements for protection of international investments; Europe 1992-toward a single energy market; Dispute resolution in international agreements; Assessment of political risk; Reducing political risk; Protecting mineral investments from upheaval in developing countries; Typical world petroleum arrangements; government take in the Pacific Rim - Papua New Guinea; Mineral base of the USSR and prospects of investment; International taxation for the mining practitioner; Tax considerations - branch versus subsidiary; Doing business in the host country - nontax considerations; Impact of host-country laws on operations and profits; Mineral development and native rights - New Zealand; Designing the investment vehicle: mining; International oil and gas joint ventures; Selected U.S. laws with extraterritorial effect; U.S. tax and securities laws applied to foreign joint venturers; and Extraterritorial effect of U.S. laws.

  10. Internal Patent Instructions

    Broader source: Energy.gov [DOE]

    The internal patent instructions (IPIs) were originally established as a means for providing a common reference source to all patent counsel offices on centralized instructions, as stated in the...

  11. NEMS International Energy Module

    Gasoline and Diesel Fuel Update (EIA)

    EIA NEMS International Energy Module Model Documentation Report vii Mr. G. Daniel Butler U.S. Department of Energy EI-812 1000 Independence Ave., SW Washington, DC 20585 Tel:...

  12. International Energy Module

    Gasoline and Diesel Fuel Update (EIA)

    EIA NEMS International Energy Module Model Documentation Report vii Mr. G. Daniel Butler U.S. Department of Energy EI-812 1000 Independence Ave., SW Washington, DC 20585 Tel:...

  13. International Energy Module

    Gasoline and Diesel Fuel Update (EIA)

    self-contained units which are linked by an integrating mechanism. The NEMS International Energy Module (IEM) computes world oil prices, provides a set of crude oil and refined...

  14. NEAC International Subcommittee Report

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

    ... for Peace Conference Room, 5A-118 1000 Independence Ave, SW Washington, DC 20585 11 DOE NEAC International Subcommittee Meeting October 29-30, 2015 Room 5A-118, Atoms for Peace ...

  15. HydroVision International

    Broader source: Energy.gov [DOE]

    The HydroVision International Conference and Exhibition offers attendees countless opportunities to network, share best practices, meet with product and service providers, and more.  Held over five...

  16. International Energy Agency

    Broader source: Energy.gov [DOE]

    DOE's market transformation efforts have reached to European and other countries who are part of the international distributed and decentralized energy community. Through its partnership with DOE, the combined heat and power (CHP) program of the International Energy Agency (IEA) conducts research and analysis of CHP markets and deployment efforts around the world and has used lessons learned from U.S. research, development, and deployment efforts to recommend market transformation activities and policies that will lead to new CHP installations worldwide.

  17. International petroleum statistics report

    SciTech Connect (OSTI)

    Not Available

    1994-05-01

    This monthly publication provides current international oil data. The Report presents data on international oil production, demand, imports, exports, and stocks. Section 1 contains time series data on world oil production, and on oil demand and stocks in the OECD. Section 2 presents an oil supply/demand balance for the world. Section 3 presents data on oil imports by OECD countries. Section 4 presents annual time series data on world oil production and oil stocks, demand, and trade in OECD countries.

  18. Internal combustion engine

    SciTech Connect (OSTI)

    Bernauer, O.

    1980-10-07

    An internal combustion engine is described that has walls delimiting the working space or spaces of the internal combustion engine, in which a hydrogen-impervious, encapsulated metal hydride storage device is provided which is in heat-conducting contact with these walls; the interior of the encapsulation is adapted to be selectively connected to a source of hydrogen and/or to a separate further hydrogen storage device.

  19. (International meetings on ecology)

    SciTech Connect (OSTI)

    DeAngelis, D.L.; Garten, C.T. Jr.; Turner, M.G.

    1990-09-25

    the travelers attended the Fifth International Congress of Ecology (INTECOL) in Yokohama, Japan, and two presented invited papers and chaired symposia. One traveler also attended the OJI International Seminar in Gifu, Japan and the Fukuoka Symposium on Theoretical Ecology in Fukuoka, Japan and presented invited papers. At these scientific gatherings, a large number of symposia and specific presentations were relevant to current research at Oak Ridge National Laboratory (ORNL), especially in the areas of landscape dynamics, plant physiology, and aquatic ecosystems.

  20. International Energy Outlook 2016

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

    484(2016) I May 2016 International Energy Outlook 2016 ~ Independent Statistics & Ana[ysis e~ ~* a~ 1 U.S. ~~ergy. Information Administration Contacts The International Energy Outlook 2016 was prepared by the U.S. Energy Information Administration (EIA) under the direction of John Conti, Assistant Administrator for Energy Analysis (john.conti@eia.gov, 202-586-2222); Paul Holtberg, Team Leader, Analysis Integration Team (paul.holtberg@eia.gov, 202-586-1284); Jim Diefenderfer, Director, Office

  1. International petroleum development agreements

    SciTech Connect (OSTI)

    Smith, E.E.

    1993-12-31

    There are recognizable legal elements in all of the international arrangements for petroleum development currently in use but no arrangements are exactly like the typical American oil and gas lease. This article discusses differences and approaches to the differences in legal aspects of international petroleum development agreements. Topics covered include the following: oil and national sovereignty; obtaining a development agreement; concession and production sharing agreements; participation; differences among agreements.

  2. Three-component gyrotropic metamaterial

    SciTech Connect (OSTI)

    Tralle, Igor, E-mail: tralle@ur.edu.pl; Zi?ba, Pawe?; Pa?ko, Wioletta [Faculty of Mathematics and Natural Sciences, Theoretical Physics Department, University of Rzeszw, Pigonia 1, 35-310 Rzeszw (Poland)

    2014-06-21

    All of the proposed ever since designs of metamaterials are characterized by ever-increasing sophistication of fabrication methods. Here, a comparatively simple recipe for the fabrication of a metamaterial, which is both gyrotropic and of the simultaneously negative permittivity and permeability, is proposed. The idea is to make a mixture of three ingredients, where one of them would be responsible for the negativity of ?, while the other two would be responsible for the negativity of ?. The first component of the mixture is the swarm of single-domain ferromagnetic nano-particles, immersed in a mixture of other two, silver and mercury cadmium telluride. By carrying out the computer simulations, the domains of gyromagnetic metamaterial exist, relative to all parameters characterizing the model, that is, the temperature, external magnetic field, parameters of nano-particles, and the fraction of cadmium in Hg{sub 1?x}Cd{sub x}Te-compound as well as relative concentrations of the mixture components are established.

  3. International Activities | Department of Energy

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

    International Activities International Activities International Activities The International Program assists the DOE Office of Environmental Management (EM) in identifying technologies and strategies for waste processing, groundwater and soil remediation, spent nuclear fuel and surplus nuclear material disposition, and facility deactivation and decommissioning. The International Program seeks to transform advances in science and engineering into practical solutions for environmental remediation.

  4. Heavy Water Components Test Reactor Decommissioning - Major Component Removal

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2010-05-05

    The Heavy Water Components Test Reactor (HWCTR) facility (Figure 1) was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR facility is on high, well-drained ground, about 30 meters above the water table. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. It was not a defense-related facility like the materials production reactors at SRS. The reactor was moderated with heavy water and was rated at 50 megawatts thermal power. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In 1965, fuel assemblies were removed, systems that contained heavy water were drained, fluid piping systems were drained, deenergized and disconnected and the spent fuel basin was drained and dried. The doors of the reactor facility were shut and it wasn't until 10 years later that decommissioning plans were considered and ultimately postponed due to budget constraints. In the early 1990s, DOE began planning to decommission HWCTR again. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. The $1.6 billion allocation from the American Recovery and Reinvestment Act to SRS for site clean up at SRS has opened the doors to the HWCTR again - this time for final decommissioning. During the lifetime of HWCTR, 36 different fuel assemblies were tested in the facility. Ten of these

  5. Multi-tipped optical component

    DOE Patents [OSTI]

    D'urso, Brian R; Simpson, John T

    2010-04-13

    An optical component includes a support structure having a first composition including a recessive phase material and a second composition including protrusive phase material, the protrusive phase material defining a plurality of spaced apart surface features, each of the surface features comprising a distal end opposite the support structure, integrated with the support structure, and protruding distally from a surface of the support structure, each of the surface features reducing in cross sectional area distally from the support structure to provide a lowest cross sectional area at the distal end, the recessive phase material supporting and separating the surface features and defining a contiguous recessed surface area between the surface features, at least two of the protrusive features being characterized as optical waveguides.

  6. ,,,,,,"Coal Components",,,"Coke",,,"Electricity Components",,,,,,,,,,,,,,"Natural Gas Components",,,"Steam Components"

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

    Relative Standard Errors for Table 7.1;" " Unit: Percents." ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,"Selected Wood and Other Biomass Components" ,,,,,,"Coal Components",,,"Coke",,,"Electricity Components",,,,,,,,,,,,,,"Natural Gas Components",,,"Steam Components" " "," ",,,,,,,,,,,,,"Total",,,,,,,,,,,,,,,,,,,,,,,"Wood Residues",,,," " " "," ","

  7. Biofuels International | Open Energy Information

    Open Energy Info (EERE)

    International Jump to: navigation, search Name: Biofuels International Place: Indiana Sector: Biofuels Product: Pittsburgh based biofuels project developer presently developing a...

  8. OK International | Open Energy Information

    Open Energy Info (EERE)

    OK International Jump to: navigation, search Name: OK International Address: san francisco Place: San Francisco, California Website: www.okinternational.org Coordinates:...

  9. Edison International | Open Energy Information

    Open Energy Info (EERE)

    International Jump to: navigation, search Name: Edison International Place: Rosemead, California Zip: 91770 Product: Utility company and parent of SCE and Edison Mission Energy....

  10. Carbon International | Open Energy Information

    Open Energy Info (EERE)

    International Jump to: navigation, search Name: Carbon International Place: London, United Kingdom Zip: NW1 8LH Sector: Carbon Product: London-based energy and communications...

  11. Student Trainee (Engineering)- Intern NTE

    Broader source: Energy.gov [DOE]

    The purpose of the Pathways Intern Employment Program is to provide the intern with exposure to public service, enhance educational experience, and support educational goals. The program is...

  12. BBI International | Open Energy Information

    Open Energy Info (EERE)

    BBI International Jump to: navigation, search Name: BBI International Place: Salida, Colorado Zip: 81201 Sector: Biofuels Product: Information service provider for the Biofuels...

  13. International energy annual 1997

    SciTech Connect (OSTI)

    1999-04-01

    The International Energy Annual presents an overview of key international energy trends for production, consumption, imports, and exports of primary energy commodities in over 220 countries, dependencies, and areas of special sovereignty. Also included are population and gross domestic product data, as well as prices for crude oil and petroleum products in selected countries. Renewable energy reported in the International Energy Annual includes hydroelectric power and geothermal, solar, and wind electric power. Also included are biomass electric power for Brazil and the US, and biomass, geothermal, and solar energy produced in the US and not used for electricity generation. This report is published to keep the public and other interested parties fully informed of primary energy supplies on a global basis. The data presented have been largely derived from published sources. The data have been converted to units of measurement and thermal values (Appendices E and F) familiar to the American public. 93 tabs.

  14. International energy outlook 1994

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    The International Energy Outlook 1994 (IEO94) presents an assessment by the Energy Information Administration (EIA) of the outlook for international energy markets between 1990 and 2010. The report is provided as a statistical service to assist energy managers and analysts, both in government and in the private sector. These forecasts are used by international agencies, Federal and State governments, trade associations, and other planners and decisionmakers. They are published pursuant to the Depart. of Energy Organization Act of 1977 (Public Law 95-91), Section 205(c). The IEO94 projections are based on US and foreign government policies in effect on October 1, 1993-which means that provisions of the Climate Change Action Plan unveiled by the Administration in mid-October are not reflected by the US projections.

  15. INTERNAL CUTTING DEVICE

    DOE Patents [OSTI]

    Russell, W.H. Jr.

    1959-06-30

    A device is described for removing material from the interior of a hollow workpiece so as to form a true spherical internal surface in a workpiece, or to cut radial slots of an adjustable constant depth in an already established spherical internal surface. This is accomplished by a spring loaded cutting tool adapted to move axially wherein the entire force urging the tool against the workpiece is derived from the spring. Further features of importance involve the provision of a seal between the workpiece and the cutting device and a suction device for carrying away particles of removed material.

  16. International petroleum statistics report

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    This document is a monthly publication that provides current international oil data. The Report presents data on international oil production, demand, imports, exports, and stocks. Section 1 contains time series data on world oil production, and on oil demand and stocks in the OECD. Section 2 presents an oil supply/demand balance for the world. This balance is presented in quarterly intervals for the most recent two years. Section 3 presents data on oil imports by OECD countries. Section 4 presents annual time series data on world oil production and oil stocks, demand and trade in OECD countries.

  17. Earth shelter goes international

    SciTech Connect (OSTI)

    Boyer, L.L.

    1983-06-01

    Since the mid-1970's earth sheltered buildings in the US have become more numerous and important as a contemporary passive building concept. Further, an intense international interest has now developed, as evidenced by a number of important activities. One of these events is the 1983 International Conference on Energy Efficient Buildings with Earth Shelter Protection to be conducted during 1-6 August in Sydney, Australia. A review of past activities leading up to this event, as well as a brief review of the conference program, is the subject of this discussion.

  18. INTERNAL REPAIR OF PIPELINES

    SciTech Connect (OSTI)

    Robin Gordon; Bill Bruce; Nancy Porter; Mike Sullivan; Chris Neary

    2003-05-01

    The two broad categories of deposited weld metal repair and fiber-reinforced composite repair technologies were reviewed for potential application for internal repair of gas transmission pipelines. Both are used to some extent for other applications and could be further developed for internal, local, structural repair of gas transmission pipelines. Preliminary test programs were developed for both deposited weld metal repairs and for fiber-reinforced composite repair. To date, all of the experimental work pertaining to the evaluation of potential repair methods has focused on fiber-reinforced composite repairs. Hydrostatic testing was also conducted on four pipeline sections with simulated corrosion damage: two with composite liners and two without.

  19. High temperature two component explosive

    DOE Patents [OSTI]

    Mars, James E.; Poole, Donald R.; Schmidt, Eckart W.; Wang, Charles

    1981-01-01

    A two component, high temperature, thermally stable explosive composition comprises a liquid or low melting oxidizer and a liquid or low melting organic fuel. The oxidizer and fuel in admixture are incapable of substantial spontaneous exothermic reaction at temperatures on the order of 475.degree. K. At temperatures on the order of 475.degree. K., the oxidizer and fuel in admixture have an activation energy of at least about 40 kcal/mol. As a result of the high activation energy, the preferred explosive compositions are nondetonable as solids at ambient temperature, and become detonable only when heated beyond the melting point. Preferable oxidizers are selected from alkali or alkaline earth metal nitrates, nitrites, perchlorates, and/or mixtures thereof. Preferred fuels are organic compounds having polar hydrophilic groups. The most preferred fuels are guanidinium nitrate, acetamide and mixtures of the two. Most preferred oxidizers are eutectic mixtures of lithium nitrate, potassium nitrate and sodium nitrate, of sodium nitrite, sodium nitrate and potassium nitrate, and of potassium nitrate, calcium nitrate and sodium nitrate.

  20. International energy indicators. [International and US statistics

    SciTech Connect (OSTI)

    Bauer, E.K.

    1980-03-01

    For the international sector, a table of data is first presented followed by corresponding graph of the data for the following: (1) Iran: crude oil capacity, production, and shut-in, 1974 to February 1980; (2) Saudi Arabia (same as Iran); (3) OPEC (ex-Iran and Saudi Arabia); capacity, production, and shut-in, 1974 to January 1980; (4) non-OPEC Free World and US production of crude oil, 1973 to January 1980; (5) oil stocks: Free World, US, Japan, and Europe (landed), 1973 to 1979; (6) petroleum consumption by industrial countries, 1973 to October 1979; (7) USSR crude oil production, 1974 to February 1980; (8) Free World and US nuclear generation capacity, 1973 to January 1980. For the United States, the same data format is used for the following: (a) US imports of crude oil and products 1973 to January 1980; (b) landed cost of Saudi Arabia crude oil in current and 1974 dollars, 1974 to October 1979; (c) US trade in coal, 1973 to 1979; (d) summary of US merchandise trade, 1976 to January 1980; and (e) US energy/GNP ratio (in 1972 dollars), 1947 to 1979.

  1. International petroleum statistics report

    SciTech Connect (OSTI)

    1997-05-01

    The International Petroleum Statistics Report is a monthly publication that provides current international oil data. This report is published for the use of Members of Congress, Federal agencies, State agencies, industry, and the general public. Publication of this report is in keeping with responsibilities given the Energy Information Administration in Public Law 95-91. The International Petroleum Statistics Report presents data on international oil production, demand, imports, and stocks. The report has four sections. Section 1 contains time series data on world oil production, and on oil demand and stocks in the Organization for Economic Cooperation and Development (OECD). This section contains annual data beginning in 1985, and monthly data for the most recent two years. Section 2 presents an oil supply/demand balance for the world. This balance is presented in quarterly intervals for the most recent two years. Section 3 presents data on oil imports by OECD countries. This section contains annual data for the most recent year, quarterly data for the most recent two quarters, and monthly data for the most recent twelve months. Section 4 presents annual time series data on world oil production and oil stocks, demand, and trade in OECD countries. World oil production and OECD demand data are for the years 1970 through 1995; OECD stocks from 1973 through 1995; and OECD trade from 1985 through 1995.

  2. Rotary internal combustion engine

    SciTech Connect (OSTI)

    Le, L.K.

    1990-11-20

    This patent describes an internal combustion engine comprising; a rotary compressor mechanism; a rotary expander mechanism; and combustion chamber means disposed between the compressor mechanism and the expander mechanism, whereby compressed air is delivered to the combustion chamber through the compressor discharge port, and pressurized gas is delivered from the combustion chamber into the expander mechanism through the pressurized gas intake port.

  3. Requirements for Xenon International

    SciTech Connect (OSTI)

    Hayes, James C.; Ely, James H.

    2013-09-26

    This document defines the requirements for the new Xenon International radioxenon system. The output of this project will be a Pacific Northwest National Laboratory (PNNL) developed prototype and a manufacturer-developed production prototype. The two prototypes are intended to be as close to matching as possible; this will be facilitated by overlapping development cycles and open communication between PNNL and the manufacturer.

  4. Requirements for Xenon International

    SciTech Connect (OSTI)

    Hayes, James C.; Ely, James H.; Haas, Derek A.; Harper, Warren W.; Heimbigner, Tom R.; Hubbard, Charles W.; Humble, Paul H.; Madison, Jill C.; Morris, Scott J.; Panisko, Mark E.; Ripplinger, Mike D.; Stewart, Timothy L.

    2015-12-30

    This document defines the requirements for the new Xenon International radioxenon system. The output of this project will be a Pacific Northwest National Laboratory (PNNL) developed prototype and a manufacturer-developed production prototype. The two prototypes are intended to be as close to matching as possible; this will be facilitated by overlapping development cycles and open communication between PNNL and the manufacturer.

  5. Internal Control Program

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2008-10-28

    To ensure sound internal controls and overall consistency in exercising the statutory authorities that vest in the Secretary, the Administrator, National Nuclear Security Administration (NNSA), and Department's Chief Financial Officer (CFO), and to implement the Federal Managers' Financial Integrity Act of 1982 and related central agency guidance. Supersedes DOE O 413.1A.

  6. Internal split field generator

    DOE Patents [OSTI]

    Thundat; Thomas George; Van Neste, Charles W.; Vass, Arpad Alexander

    2012-01-03

    A generator includes a coil of conductive material. A stationary magnetic field source applies a stationary magnetic field to the coil. An internal magnetic field source is disposed within a cavity of the coil to apply a moving magnetic field to the coil. The stationary magnetic field interacts with the moving magnetic field to generate an electrical energy in the coil.

  7. International energy outlook 1996

    SciTech Connect (OSTI)

    1996-05-01

    This International Energy Outlook presents historical data from 1970 to 1993 and EIA`s projections of energy consumption and carbon emissions through 2015 for 6 country groups. Prospects for individual fuels are discussed. Summary tables of the IEO96 world energy consumption, oil production, and carbon emissions projections are provided in Appendix A. The reference case projections of total foreign energy consumption and of natural gas, coal, and renewable energy were prepared using EIA`s World Energy Projection System (WEPS) model. Reference case projections of foreign oil production and consumption were prepared using the International Energy Module of the National Energy Modeling System (NEMS). Nuclear consumption projections were derived from the International Nuclear Model, PC Version (PC-INM). Alternatively, nuclear capacity projections were developed using two methods: the lower reference case projections were based on analysts` knowledge of the nuclear programs in different countries; the upper reference case was generated by the World Integrated Nuclear Evaluation System (WINES)--a demand-driven model. In addition, the NEMS Coal Export Submodule (CES) was used to derive flows in international coal trade. As noted above, foreign projections of electricity demand are now projected as part of the WEPS. 64 figs., 62 tabs.

  8. STEP Intern Reference Check Sheet

    Broader source: Energy.gov [DOE]

    STEP Intern Reference Check Sheet, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  9. NREL: International Activities Home Page

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

    Sponsors and Partners NREL conducts its international programs in support of many U.S. agencies-including the Department of Energy, Agency for International Development, Department of State, Environmental Protection Agency, Millennium Challenge Corporation, Overseas Private Development Investment Corporation, as well as numerous international sponsors and partners, including the United Nations (UN) agencies, the Australian government, Global Green Growth Institute, International Renewable

  10. Battery components employing a silicate binder

    DOE Patents [OSTI]

    Delnick, Frank M.; Reinhardt, Frederick W.; Odinek, Judy G.

    2011-05-24

    A battery component structure employing inorganic-silicate binders. In some embodiments, casting or coating of components may be performed using aqueous slurries of silicates and electrode materials or separator materials.

  11. A Plan for Modularization of Tritium Components

    Office of Environmental Management (EM)

    Tritium Components Randy Davis Davis Consultants M-TRT-H-00089 Savannah River Nuclear Solutions, LLC April 22, 2014 M-TRT-H-00089 Current Approach * All "tritium wetted components" ...

  12. Interaction potentials and thermodynamic properties of two component semiclassical plasma

    SciTech Connect (OSTI)

    Ramazanov, T. S.; Moldabekov, Zh. A.; Ismagambetova, T. N.; Gabdullin, M. T.

    2014-01-15

    In this paper, the effective interaction potential in two component semiclassical plasma, taking into account the long-range screening and the quantum-mechanical diffraction effects at short distances, is obtained on the basis of dielectric response function method. The structural properties of the semiclassical plasma are considered. The thermodynamic characteristics (the internal energy and the equation of state) are calculated using two methods: the method of effective potentials and the method of micropotentials with screening effect taken into account by the Ornstein-Zernike equation in the HNC approximation.

  13. Renewable: A key component of our global energy future

    SciTech Connect (OSTI)

    Hartley, D.

    1995-12-31

    Inclusion of renewable energy sources in national and international energy strategies is a key component of a viable global energy future. The global energy balance is going to shift radically in the near future brought about by significant increases in population in China and India, and increases in the energy intensity of developing countries. To better understand the consequences of such global shifts in energy requirements and to develop appropriate energy strategies to respond to these shifts, we need to look at the factors driving choices among supply options by geopolitical consumers and the impact these factors can have on the future energy mix.

  14. Waste Package Component Design Methodology Report

    SciTech Connect (OSTI)

    D.C. Mecham

    2004-07-12

    This Executive Summary provides an overview of the methodology being used by the Yucca Mountain Project (YMP) to design waste packages and ancillary components. This summary information is intended for readers with general interest, but also provides technical readers a general framework surrounding a variety of technical details provided in the main body of the report. The purpose of this report is to document and ensure appropriate design methods are used in the design of waste packages and ancillary components (the drip shields and emplacement pallets). The methodology includes identification of necessary design inputs, justification of design assumptions, and use of appropriate analysis methods, and computational tools. This design work is subject to ''Quality Assurance Requirements and Description''. The document is primarily intended for internal use and technical guidance for a variety of design activities. It is recognized that a wide audience including project management, the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission, and others are interested to various levels of detail in the design methods and therefore covers a wide range of topics at varying levels of detail. Due to the preliminary nature of the design, readers can expect to encounter varied levels of detail in the body of the report. It is expected that technical information used as input to design documents will be verified and taken from the latest versions of reference sources given herein. This revision of the methodology report has evolved with changes in the waste package, drip shield, and emplacement pallet designs over many years and may be further revised as the design is finalized. Different components and analyses are at different stages of development. Some parts of the report are detailed, while other less detailed parts are likely to undergo further refinement. The design methodology is intended to provide designs that satisfy the safety and operational

  15. Manufacturing complex silica aerogel target components

    SciTech Connect (OSTI)

    Defriend Obrey, Kimberly Ann [Los Alamos National Laboratory; Day, Robert D [Los Alamos National Laboratory; Espinoza, Brent F [Los Alamos National Laboratory; Hatch, Doug [Los Alamos National Laboratory; Patterson, Brian M [Los Alamos National Laboratory; Feng, Shihai [Los Alamos National Laboratory

    2008-01-01

    Aerogel is a material used in numerous components in High Energy Density Physics targets. In the past these components were molded into the proper shapes. Artifacts left in the parts from the molding process, such as contour irregularities from shrinkage and density gradients caused by the skin, have caused LANL to pursue machining as a way to make the components.

  16. HVAC component data modeling using industry foundation classes

    SciTech Connect (OSTI)

    Bazjanac, Vladimir; Forester, James; Haves, Philip; Sucic, Darko; Xu, Peng

    2002-07-01

    The Industry Foundation Classes (IFC) object data model of buildings is being developed by the International Alliance for Interoperability (IAI). The aim is to support data sharing and exchange in the building and construction industry across the life-cycle of a building. This paper describes a number of aspects of a major extension of the HVAC part of the IFC data model. First is the introduction of a more generic approach for handling HVAC components. This includes type information, which corresponds to catalog data, occurrence information, which defines item-specific attributes such as location and connectivity, and performance history information, which documents the actual performance of the component instance over time. Other IFC model enhancements include an extension of the connectivity model used to specify how components forming a system can be traversed and the introduction of time-based data streams. This paper includes examples of models of particular types of HVAC components, such as boilers and actuators, with all attributes included in the definitions. The paper concludes by describing the on-going process of model testing, implementation and integration into the complete IFC model and how the model can be used by software developers to support interoperability between HVAC-oriented design and analysis tools.

  17. Clean Diesel Component Improvement Program

    SciTech Connect (OSTI)

    2005-06-30

    The research conducted in this program significantly increased the knowledge and understanding in the fields of plasma physics and chemistry in diesel exhaust, the performance and characteristics of multifunctional catalysts in diesel exhaust, and the complexities of controlling a combination of such systems to remove NOx. Initially this program was designed to use an in-line plasma system (know as a plasma assisted catalyst system or PAC) to convert NO {yields} NO{sub 2}, a more catalytically active form of nitrogen oxides, and to crack hydrocarbons (diesel fuel in particular) into active species. The NO{sub 2} and the cracked hydrocarbons were then flowed over an in-line ceramic NOx catalyst that removed NO{sub 2} from the diesel exhaust. Even though the PAC system performed well technically and was able to remove over 95% of NOx from diesel exhaust the plasma component proved not to be practical or commercially feasible. The lack of practical and commercial viability was due to high unit costs and lack of robustness. The plasma system and its function was replaced in the NOx removal process by a cracking reforming catalyst that converted diesel fuel to a highly active reductant for NOx over a downstream ceramic NOx catalyst. This system was designated the ceramic catalyst system (CCS). It was also determined that NO conversion to NO{sub 2} was not required to achieve high levels of NOx reduction over ceramic NOx catalyst if that catalyst was properly formulated and the cracking reforming produced a reductant optimized for that NOx catalyst formulation. This system has demonstrated 92% NOx reduction in a diesel exhaust slipstream and 65% NOx reduction from the full exhaust of a 165 hp diesel engine using the FTP cycle. Although this system needs additional development to be commercial, it is simple, cost effective (does not use precious metals), sulfur tolerant, operates at high space velocities, does not require a second fluid be supplied as a reductant, has low

  18. Simple thermodynamics of strongly coupled one-component-plasma in two and three dimensions

    SciTech Connect (OSTI)

    Khrapak, Sergey A.; Khrapak, Alexey G.

    2014-10-15

    Simple analytical approximations for the internal energy of the strongly coupled one-component-plasma in two and three dimensions are discussed. As a result, new practical expressions for the internal energy in the fluid phase are proposed. Their accuracy is checked by evaluating the location of the fluid-solid phase transition from the free energy consideration. Possible applications to other related systems are briefly discussed.

  19. International Energy Agency

    SciTech Connect (OSTI)

    Claudy, D.E.

    1982-01-01

    The International Energy Agency (IEA) responded to the 1973-1974 oil embargo with an emergency allocation program outlined in the Agreement on an International Energy Program (IEP), viewed by the US as an executive agreement and by most participants as a treaty. The IEA's four standing groups on Relations with Producer and other Consumer Countries, on Long-Term Cooperation, on the Oil Market, and on Emergency Questions are organized to accommodate co041869flicting interests through voting rights and to allow constructive interaction among intergovernmental bodies. A description of the allocation system and industry's role in emergencies is followed by a summary of US legal requirements relating to these activities. Four appendices reproduce the IEP Agreement and diagram the IEA organizational structure, the IEA emergency allocation system, and the Emergency Management Organization. (DCK)

  20. International Nuclear Security

    SciTech Connect (OSTI)

    Doyle, James E.

    2012-08-14

    This presentation discusses: (1) Definitions of international nuclear security; (2) What degree of security do we have now; (3) Limitations of a nuclear security strategy focused on national lock-downs of fissile materials and weapons; (4) What do current trends say about the future; and (5) How can nuclear security be strengthened? Nuclear security can be strengthened by: (1) More accurate baseline inventories; (2) Better physical protection, control and accounting; (3) Effective personnel reliability programs; (4) Minimize weapons-usable materials and consolidate to fewer locations; (5) Consider local threat environment when siting facilities; (6) Implement pledges made in the NSS process; and (7) More robust interdiction, emergency response and special operations capabilities. International cooperation is desirable, but not always possible.

  1. Internal core tightener

    DOE Patents [OSTI]

    Brynsvold, Glen V.; Snyder, Jr., Harold J.

    1976-06-22

    An internal core tightener which is a linear actuated (vertical actuation motion) expanding device utilizing a minimum of moving parts to perform the lateral tightening function. The key features are: (1) large contact areas to transmit loads during reactor operation; (2) actuation cam surfaces loaded only during clamping and unclamping operation; (3) separation of the parts and internal operation involved in the holding function from those involved in the actuation function; and (4) preloaded pads with compliant travel at each face of the hexagonal assembly at the two clamping planes to accommodate thermal expansion and irradiation induced swelling. The latter feature enables use of a "fixed" outer core boundary, and thus eliminates the uncertainty in gross core dimensions, and potential for rapid core reactivity changes as a result of core dimensional change.

  2. Rotary internal combustion engine

    SciTech Connect (OSTI)

    Murray, J.L.; Mosca, J.O.

    1992-02-25

    This patent describes a rotary internal combustion engine. It includes a housing; a cam track internally disposed within the housing and adapted to receive a cam follower; an engine block disposed within the housing, the engine block being relatively rotatable within the housing about a central axis; means connectable to an external drive member for translating the relative rotation of the engine block with respect to the housing into useful work; at least one radially arranged cylinder assembly on the block, each cylinder assembly including a cylinder having a longitudinal axis extending generally radially outwardly from the rotational axis of the block, the cylinder including means defining an end wall, a piston member disposed within the cylinder and adapted to reciprocate within the cylinder; the piston, cylinder and cylinder end wall together.

  3. Internal combustion rotary engine

    SciTech Connect (OSTI)

    Chen, S.P.

    1993-08-24

    An internal combustion rotary engine is described comprising: an internal combustion chamber wherein a combustible fuel-air mixture is ignited for producing a driving gas flow; a central rotor having an outer surface in which at least one group of curved channels circumferentially-and-axially extending without radially extending through the central rotor; and at least one annular rotor each enclosing the central rotor having an inner surface in which a corresponding number of curved channels circumferentially-and-axially extending without radially extending through the annular rotor; when the curved channels in the central rotor communicate with the curved channels in the annular rotor, the driving gas flow circumferentially-and-axially passing between the outer surface of the central rotor and the inner surface of the annular rotor for rotating the central rotor and the annular rotor in opposite directions.

  4. International Algae Symposium

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy’s Bioenergy Technologies Office Advanced Algal Systems Technology Manager Daniel Fishman represented the Office at the International Algae Symposium in Tokyo, Japan. Hosted at the University of Tsukuba’s newly established Algae Biomass Bioenergy Development Research Center, the symposium was an opportunity for algae researchers, policy makers, and industry leaders across the globe to learn about each other’s work.

  5. International markets for CCTs

    SciTech Connect (OSTI)

    Ferriter, J.P.

    1997-12-31

    The paper begins by describing the role of the International Energy Agency, the importance of coal, what the IEA is doing in the area of clean coal technology, and the role of the IEA Coal Industry Advisory Board. The paper then discusses which coal technologies will be chosen, what the problem areas are, and what can be done to accelerate the take-up of clean coal technologies.

  6. International petroleum statistics report

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    This report presents data on international oil production, demand, imports, exports, and stocks. Section 1 contains time series data on world oil production, and on oil demand and stocks in the OECD. Section 2 presents an oil supply/demand balance for the world, presented in quarterly intervals for the most recent two years. Section 3 presents data on oil imports by OECD countries. Section 4 presents annual time series data on world oil production, oil stocks, demand, and trade in OECD countries.

  7. International petroleum statistics report

    SciTech Connect (OSTI)

    1997-11-01

    This document is a monthly publication which provides current data on international oil production,demand,imports and stocks. This report has four sections which contain time series data on world oil production and oil demand and stocks in the Organization for Economic Cooperation and Development (OECD). Also included is oil supply/demand balance information for the world, and data on oil imports and trade by OECD countries.

  8. International petroleum statistics report

    SciTech Connect (OSTI)

    Not Available

    1995-01-01

    This monthly publication provides current data on international oil production, demand, imports, exports, and stocks. Section 1 contains time series data on world oil production, and on oil demand and stocks in the OECD. Section 2 presents an oil supply/demand balance for the world. Section 3 presents data on oil imports by OECD countries. Section 4 presents annual time series data on world oil production and oil stocks, demand, and trade in OECD countries.

  9. NREL: International Activities - Webmaster

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

    Webmaster Please enter your name and email address in the boxes provided, then type your message below. When you are finished, click "Send Message." NOTE: If you enter your e-mail address incorrectly, we will be unable to reply. Your name: Your email address: Your message: Send Message Printable Version International Activities Home Bilateral Partnerships Multilateral Partnerships Assessments & Tools Working with Us Did you find what you needed? Yes 1 No 0 Thank you for your

  10. Polarized internal target apparatus

    DOE Patents [OSTI]

    Holt, Roy J.

    1986-01-01

    A polarized internal target apparatus with a polarized gas target of improved polarization and density achieved by mixing target gas atoms with a small amount of alkali metal gas atoms, and passing a high intensity polarized light source into the mixture to cause the alkali metal gas atoms to become polarized which interact in spin exchange collisions with target gas atoms yielding polarized target gas atoms.

  11. Polarized internal target apparatus

    DOE Patents [OSTI]

    Holt, R.J.

    1984-10-10

    A polarized internal target apparatus with a polarized gas target of improved polarization and density (achieved by mixing target gas atoms with a small amount of alkali metal gas atoms, and passing a high intensity polarized light source into the mixture to cause the alkali metal gas atoms to become polarized which interact in spin exchange collisions with target gas atoms yielding polarized target gas atoms) is described.

  12. International energy outlook 2006

    SciTech Connect (OSTI)

    2006-06-15

    This report presents international energy projections through 2030, prepared by the Energy Information Administration. After a chapter entitled 'Highlights', the report begins with a review of world energy and economic outlook, followed by energy consumption by end-use sector. The next chapter is on world oil markets. Natural gas, world coal market and electricity consumption and supply are then discussed. The final chapter covers energy-related carbon dioxide emissions.

  13. Internal Program Review

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

    American Synchrophasor Initiative (NASPI) and Advanced Applications Research & Development (AARD) Internal Program Review 27-28 June 2013 Washington, DC Joe Eto Lawrence Berkeley National Lab DOE/OE Transmission Reliability Program 2 Management Review Topics  Project objective  Major technical accomplishments that will be completed this year  Deliverables and schedule for activities to be completed under FY13 funding  Risk factors affecting timely completion of planned activities

  14. International Subcommittee Report

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

    Dr. Regis A. Matzie, Chair NEAC Meeting December 10, 2014 1 Externalities of Nuclear Power Important International Considerations  Safety - because of the potential impact that severe accidents can have globally  Energy security - particularly in countries with little domestic energy resources  Reduction of green house gases - impact on global warming, severe weather, and flooding of coastal areas  Proliferation - particularly as it relates to the construction of sensitive nuclear

  15. International Cooperation Holiday Cheer

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

    Administration International Atomic Energy Agency Secretary Moniz awards Hutcheon memorial nonproliferation fellowship to Thomas Gray Energy Secretary Ernest Moniz (second from bottom left, clockwise) and Anne Harrington, NNSA deputy administrator for Defense Nuclear Nonproliferation (sitting next to Moniz), discuss Ian Hutcheon's legacy with his wife Nancy (across from Harrington) and daughter Dana Hutcheon Gordon. Energy... DOE/NNSA's Nonproliferation Experts Lead First Workshop on the

  16. Method of using infrared radiation for assembling a first component with a second component

    DOE Patents [OSTI]

    Sikka, Vinod K.; Whitson, Barry G.; Blue, Craig A.

    1999-01-01

    A method of assembling a first component for assembly with a second component involves a heating device which includes an enclosure having a cavity for inserting a first component. An array of infrared energy generators is disposed within the enclosure. At least a portion of the first component is inserted into the cavity, exposed to infrared energy and thereby heated to a temperature wherein the portion of the first component is sufficiently softened and/or expanded for assembly with a second component.

  17. International petroleum statistics report

    SciTech Connect (OSTI)

    1997-07-01

    The International Petroleum Statistics Report is a monthly publication that provides current international data. The report presents data on international oil production, demand, imports, and stocks. The report has four sections. Section 1 contains time series data on world oil production, and on oil demand and stocks in the Organization for Economic Cooperation and Development (OECD). This section contains annual data beginning in 1985, and monthly data for the most recent two years. Section 2 presents an oil supply/demand balance for the world. This balance is presented in quarterly intervals for the most recent two years. Section 3 presents data on oil imports by OECD countries. This section contains annual data for the most recent year, quarterly data for the most recent two quarters, and monthly data for the most recent 12 months. Section 4 presents annual time series data on world oil production and oil stocks, demand, and trade in OECD countries. World oil production and OECD demand data are for the years 1970 through 1996; OECD stocks from 1973 through 1996; and OECD trade from 1986 through 1996.

  18. Expandable Metal Liner For Downhole Components

    DOE Patents [OSTI]

    Hall, David R.; Fox, Joe R.

    2004-10-05

    A liner for an annular downhole component is comprised of an expandable metal tube having indentations along its surface. The indentations are formed in the wall of the tube either by drawing the tube through a die, by hydroforming, by stamping, or roll forming and may extend axially, radially, or spirally along its wall. The indentations accommodate radial and axial expansion of the tube within the downhole component. The tube is inserted into the annular component and deformed to match an inside surface of the component. The tube may be expanded using a hydroforming process or by drawing a mandrel through the tube. The tube may be expanded in such a manner so as to place it in compression against the inside wall of the component. The tube is useful for improving component hydraulics, shielding components from contamination, inhibiting corrosion, and preventing wear to the downhole component during use. It may also be useful for positioning conduit and insulated conductors within the component. An insulating material may be disposed between the tube and the component in order to prevent galvanic corrosion of the downhole component.

  19. Plasma Facing Components Generic Facilities Review Panel (PFC-GFRP): Final report

    SciTech Connect (OSTI)

    McGrath, R.; Allen, S.; Hill, D.; Brooks, J.; Mattas, R.; Davis, J.; Lipschultz, B.; Ulrickson, M.

    1993-10-01

    The Plasma Facing Components (PFC) Facilities Review Panel was chartered by the US Department of Energy, Office of Fusion Energy, ITER (International Thermonuclear Experimental Reactor) and Technology Division, to outline the program plan and identify the supporting test facilities that lead to reliable, long-lived plasma facing components for ITER. This report summarizes the panel`s findings and identifies the necessary and sufficient set of test facilities required for ITER PFC development.

  20. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges

    Broader source: Energy.gov [DOE]

    The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR...

  1. INTERNAL REPAIR OF PIPELINES

    SciTech Connect (OSTI)

    Robin Gordon; Bill Bruce; Ian Harris; Dennis Harwig; Nancy Porter; Mike Sullivan; Chris Neary

    2004-04-12

    The two broad categories of deposited weld metal repair and fiber-reinforced composite liner repair technologies were reviewed for potential application for internal repair of gas transmission pipelines. Both are used to some extent for other applications and could be further developed for internal, local, structural repair of gas transmission pipelines. Preliminary test programs were developed for both deposited weld metal repair and for fiber-reinforced composite liner repair. Evaluation trials have been conducted using a modified fiber-reinforced composite liner provided by RolaTube and pipe sections without liners. All pipe section specimens failed in areas of simulated damage. Pipe sections containing fiber-reinforced composite liners failed at pressures marginally greater than the pipe sections without liners. The next step is to evaluate a liner material with a modulus of elasticity approximately 95% of the modulus of elasticity for steel. Preliminary welding parameters were developed for deposited weld metal repair in preparation of the receipt of Pacific Gas & Electric's internal pipeline welding repair system (that was designed specifically for 559 mm (22 in.) diameter pipe) and the receipt of 559 mm (22 in.) pipe sections from Panhandle Eastern. The next steps are to transfer welding parameters to the PG&E system and to pressure test repaired pipe sections to failure. A survey of pipeline operators was conducted to better understand the needs and performance requirements of the natural gas transmission industry regarding internal repair. Completed surveys contained the following principal conclusions: (1) Use of internal weld repair is most attractive for river crossings, under other bodies of water, in difficult soil conditions, under highways, under congested intersections, and under railway crossings. (2) Internal pipe repair offers a strong potential advantage to the high cost of horizontal direct drilling (HDD) when a new bore must be created to

  2. Internal absorber solar collector

    DOE Patents [OSTI]

    Sletten, Carlyle J.; Herskovitz, Sheldon B.; Holt, F. S.; Sletten, E. J.

    1981-01-01

    Thin solar collecting panels are described made from arrays of small rod collectors consisting of a refracting dielectric rod lens with an absorber imbedded within it and a reflecting mirror coated on the back side of the dielectric rod. Non-tracking collector panels on vertical walls or roof tops receive approximately 90% of solar radiation within an acceptance zone 60.degree. in elevation angle by 120.degree. or more in the azimuth sectors with a collector concentration ratio of approximately 3.0. Miniaturized construction of the circular dielectric rods with internal absorbers reduces the weight per area of glass, plastic and metal used in the collector panels. No external parts or insulation are needed as heat losses are low due to partial vacuum or low conductivity gas surrounding heated portions of the collector. The miniature internal absorbers are generally made of solid copper with black selective surface and the collected solar heat is extracted at the collector ends by thermal conductivity along the absorber rods. Heat is removed from end fittings by use of liquid circulants. Several alternate constructions are provided for simplifying collector panel fabrication and for preventing the thermal expansion and contraction of the heated absorber or circulant tubes from damaging vacuum seals. In a modified version of the internal absorber collector, oil with temperature dependent viscosity is pumped through a segmented absorber which is now composed of closely spaced insulated metal tubes. In this way the circulant is automatically diverted through heated portions of the absorber giving higher collector concentration ratios than theoretically possible for an unsegmented absorber.

  3. International petroleum statistics report

    SciTech Connect (OSTI)

    1998-01-01

    This monthly publication provides international oil data for January 1998. The report presents data on oil production, demand, imports, and stocks in four sections. Section 1 containes time series data on world oil production, and on oil demand and stocks in the Organization for Economic Cooperation and Development (OECD). Section 2 presents an oil supply/demand balance for the world. This balance is presented in quarterly intervals for the most recent two years. section 3 presents data on oil imports by OECD countries. Section 4 containes annual time series data on world oil production and oil stocks, demand, and trade in OECD countries.

  4. International energy annual 1995

    SciTech Connect (OSTI)

    1996-12-01

    The International Energy Annual presents information and trends on world energy production and consumption for petroleum, natural gas, coal, and electricity. Production and consumption data are reported in standard units as well as British thermal units (Btu). Trade and reserves are shown for petroleum, natural gas, and coal. Data are provided on crude oil refining capacity and electricity installed capacity by type. Prices are included for selected crude oils and for refined petroleum products in selected countries. Population and Gross Domestic Product data are also provided.

  5. International energy annual, 1993

    SciTech Connect (OSTI)

    1995-05-08

    This document presents an overview of key international energy trends for production, consumption, imports, and exports of primary energy commodities in over 200 countries, dependencies, and areas of special sovereignty. Also included are population and gross domestic product data, as well as prices for crude oil and petroleum products in selected countries. Renewable energy includes hydroelectric, geothermal, solar and wind electric power and alcohol for fuel. The data were largely derived from published sources and reports from US Embassy personnel in foreign posts. EIA also used data from reputable secondary sources, industry reports, etc.

  6. International energy outlook 2005

    SciTech Connect (OSTI)

    2005-07-01

    This report presents international energy projections through 2025, prepared by the Energy Information Administration. The outlooks for major energy fuels are discussed, along with electricity, transportation, and environmental issues. After a chapter entitled 'Highlights', the report begins with a review of world energy and an economic outlook. The IEO2005 projections cover a 24 year period. The next chapter is on world oil markets. Natural gas and coal reserves and resources, consumption and trade discussed. The chapter on electricity deals with primary fuel use for electricity generation, and regional developments. The final section is entitled 'Energy-related greenhouse gas emissions'.

  7. Foley elected ASM International Fellow

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

    Foley elected ASM International Fellow Foley elected ASM International Fellow James Foley is the 10th ASM Fellow from LANL. July 8, 2014 James Foley James Foley The Society...

  8. International Surface Pressure Databank (ISPDv2) 1768 to 2010

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

    The International Surface Pressure Databank (ISPD) is the world's largest collection of pressure observations. It has been gathered through international cooperation and is part of the Twentieth Century Reanalysis Project that uses resources of NERSC and ORNL. The ISPD version 2 consists of three components: station, marine, and tropical cyclone best track pressure observations. The station component is a blend of many national and international collections. Related resources can be found at the NOAA ESRL 20th Century Reanalysis Homepage (http://www.esrl.noaa.gov/psd/data/20thC_Rean/). Maps displaying the locations of ISPD observations in a selected year are available at (http://www.esrl.noaa.gov/psd/data/ISPD/v2.0/)[Taken and edited from http://rda.ucar.edu/datasets/ds132.0/

  9. Uranium Weapons Components Successfully Dismantled | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Uranium Weapons Components Successfully Dismantled Uranium Weapons Components Successfully Dismantled Oak Ridge, TN Continuing its efforts to reduce the size of the U.S. nuclear weapons stockpile, the National Nuclear Security Administration announced that uranium components from two major nuclear weapons systems formerly deployed on U.S. Air Force missiles and aircraft have been dismantled at the Y-12 National Security Complex in Oak Ridge, TN. Y-12 workers

  10. Solid tags for identifying failed reactor components

    DOE Patents [OSTI]

    Bunch, Wilbur L.; Schenter, Robert E.

    1987-01-01

    A solid tag material which generates stable detectable, identifiable, and measurable isotopic gases on exposure to a neutron flux to be placed in a nuclear reactor component, particularly a fuel element, in order to identify the reactor component in event of its failure. Several tag materials consisting of salts which generate a multiplicity of gaseous isotopes in predetermined ratios are used to identify different reactor components.