Sample records for analysis core analysis

  1. HTTF Core Stress Analysis

    SciTech Connect (OSTI)

    Brian D. Hawkes; Richard Schultz

    2012-07-01T23:59:59.000Z

    In accordance with the need to determine whether cracking of the ceramic core disks which will be constructed and used in the High Temperature Test Facility (HTTF) for heatup and cooldown experiments, a set of calculation were performed using Abaqus to investigate the thermal stresses levels and likelihood for cracking. The calculations showed that using the material properties provided for the Greencast 94F ceramic, cracking is predicted to occur. However, this modeling does not predict the size or length of the actual cracks. It is quite likely that cracks will be narrow with rough walls which would impede the flow of coolant gases entering the cracks. Based on data recorded at Oregon State University using Greencast 94F samples that were heated and cooled at prescribed rates, it was concluded that the likelihood that the cracks would be detrimental to the experimental objectives is small.

  2. Core analysis workstation development and verification

    SciTech Connect (OSTI)

    Mays, C.W.; Kochendarfer, R.A.; Mays, B.E.

    1987-01-01T23:59:59.000Z

    An engineering workstation utilizing a three-dimensional reactor simulator along with a series of auxiliary programs has been developed for use in predicting core reactivity and power distributions. This workstation can be used by both core analysis and core operations personnel. Expected applications are power distribution analyses, technical specification limit verification, and various types of reactivity analyses. Reactor operations personnel can quickly simulate load follow or other reactor maneuvers and, through the interactive graphics capability of the personal computer, the reactor responses, such as power distribution and control rod position, can be displayed and understood by operations personnel.

  3. Core Analysis | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump|Information Dobson, EtCore

  4. Overview on Hydrate Coring, Handling and Analysis

    SciTech Connect (OSTI)

    Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

    2003-06-30T23:59:59.000Z

    Gas hydrates are crystalline, ice-like compounds of gas and water molecules that are formed under certain thermodynamic conditions. Hydrate deposits occur naturally within ocean sediments just below the sea floor at temperatures and pressures existing below about 500 meters water depth. Gas hydrate is also stable in conjunction with the permafrost in the Arctic. Most marine gas hydrate is formed of microbially generated gas. It binds huge amounts of methane into the sediments. Worldwide, gas hydrate is estimated to hold about 1016 kg of organic carbon in the form of methane (Kvenvolden et al., 1993). Gas hydrate is one of the fossil fuel resources that is yet untapped, but may play a major role in meeting the energy challenge of this century. In June 2002, Westport Technology Center was requested by the Department of Energy (DOE) to prepare a ''Best Practices Manual on Gas Hydrate Coring, Handling and Analysis'' under Award No. DE-FC26-02NT41327. The scope of the task was specifically targeted for coring sediments with hydrates in Alaska, the Gulf of Mexico (GOM) and from the present Ocean Drilling Program (ODP) drillship. The specific subjects under this scope were defined in 3 stages as follows: Stage 1: Collect information on coring sediments with hydrates, core handling, core preservation, sample transportation, analysis of the core, and long term preservation. Stage 2: Provide copies of the first draft to a list of experts and stakeholders designated by DOE. Stage 3: Produce a second draft of the manual with benefit of input from external review for delivery. The manual provides an overview of existing information available in the published literature and reports on coring, analysis, preservation and transport of gas hydrates for laboratory analysis as of June 2003. The manual was delivered as draft version 3 to the DOE Project Manager for distribution in July 2003. This Final Report is provided for records purposes.

  5. Power excursion analysis for high burnup cores

    SciTech Connect (OSTI)

    Diamond, D.J.; Neymotin, L.; Kohut, P. [Brookhaven National Lab., Upton, NY (United States)

    1996-02-01T23:59:59.000Z

    A study was undertaken of power excursions in high burnup cores. There were three objectives in this study. One was to identify boiling water reactor (BWR) and pressurized water reactor (PWR) transients in which there is significant energy deposition in the fuel. Another was to analyze the response of BWRs to the rod drop accident (RDA) and other transients in which there is a power excursion. The last objective was to investigate the sources of uncertainty in the RDA analysis. In a boiling water reactor, the events identified as having significant energy deposition in the fuel were a rod drop accident, a recirculation flow control failure, and the overpressure events; in a pressurized water reactor, they were a rod ejection accident and boron dilution events. The RDA analysis was done with RAMONA-4B, a computer code that models the space- dependent neutron kinetics throughout the core along with the thermal hydraulics in the core, vessel, and steamline. The results showed that the calculated maximum fuel enthalpy in high burnup fuel will be affected by core design, initial conditions, and modeling assumptions. The important uncertainties in each of these categories are discussed in the report.

  6. Geologic analysis of Devonian Shale cores

    SciTech Connect (OSTI)

    none,

    1982-02-01T23:59:59.000Z

    Cleveland Cliffs Iron Company was awarded a DOE contract in December 1977 for field retrieval and laboratory analysis of cores from the Devonian shales of the following eleven states: Michigan, Illinois, Indiana, Ohio, New York, Pennsylvania, West Virginia, Maryland, Kentucky, Tennessee and Virginia. The purpose of this project is to explore these areas to determine the amount of natural gas being produced from the Devonian shales. The physical properties testing of the rock specimens were performed under subcontract at Michigan Technological University (MTU). The study also included LANDSAT information, geochemical research, structural sedimentary and tectonic data. Following the introduction, and background of the project this report covers the following: field retrieval procedures; laboratory procedures; geologic analysis (by state); references and appendices. (ATT)

  7. Core Analysis At Long Valley Caldera Geothermal Area (Pribnow...

    Open Energy Info (EERE)

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Long Valley Caldera Geothermal Area (Pribnow, Et Al., 2003) Exploration Activity...

  8. Core Analysis At Valles Caldera - Sulphur Springs Geothermal...

    Open Energy Info (EERE)

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area (Ito & Tanaka, 1995) Exploration...

  9. Core Analysis At Fenton Hill HDR Geothermal Area (Brookins &...

    Open Energy Info (EERE)

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Fenton Hill HDR Geothermal Area (Brookins & Laughlin, 1983) Exploration Activity...

  10. Core Analysis At Geysers Area (Boitnott, 2003) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area (Boitnott, 2003) Jump to:

  11. Core Analysis At Raft River Geothermal Area (1976) | Open Energy

    Open Energy Info (EERE)

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  12. Core Analysis At Raft River Geothermal Area (1981) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area (Boitnott,Information

  13. Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area(Armstrong, Et Al., 1995) |

  14. Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area(Armstrong, Et Al., 1995)

  15. Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area (Morgan,

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area(Armstrong, Et Al.,Et Al.,

  16. Application of Covariances to Fast Reactor Core Analysis

    SciTech Connect (OSTI)

    Ishikawa, M. [Japan Atomic Energy Agency (JAEA), O-arai, Ibaraki, 311-1393 (Japan)], E-mail: ishikawa.makoto@jaea.go.jp

    2008-12-15T23:59:59.000Z

    In the present paper, the current status of covariance applications to fast reactor analysis and design is summarized with actual examples. The covariance applications are classified into three fields. First, covariances are used to quantify the uncertainty of nuclear core parameters such as criticality, control rod worth, reaction rate ratio, power distribution, sodium void reactivity, etc. The special features of the Japanese case are to include both the burnup-related parameters such as burnup reactivity loss or fuel composition changes, and the temperature-related parameter, that is, the Doppler reactivity. Second, covariances are used to select the important nuclides, reactions and energy ranges which are dominant to the uncertainty of core parameters, and to give nuclear scientists recommendations to improve the accuracy of the data. Finally, covariances are used to improve the accuracy of core design values by adopting the integral data such as the critical experiments and the power reactor operation data. The way toward improvement is classified into the conventional E/C (Experiment/Calculation) bias method and the more comprehensive cross section adjustment based on the Bayesian theorem and the generalized least square method. In Japan, an adjusted group-constant set, ADJ2000R, is now being used in the design work for future fast reactors.

  17. Technique for continuous high-resolution analysis of trace substances in firn and ice cores

    SciTech Connect (OSTI)

    Roethlisberger, R.; Bigler, M.; Hutterli, M.; Sommer, S.; Stauffer, B.; Junghans, H.G.; Wagenbach, D.

    2000-01-15T23:59:59.000Z

    The very successful application of a CFA (Continuous flow analysis) system in the GRIP project (Greenland Ice Core Project) for high-resolution ammonium, calcium, hydrogen peroxide, and formaldehyde measurements along a deep ice core led to further development of this analysis technique. The authors included methods for continuous analysis technique. The authors included methods for continuous analysis of sodium, nitrate, sulfate, and electrolytical conductivity, while the existing methods have been improved. The melting device has been optimized to allow the simultaneous analysis of eight components. Furthermore, a new melter was developed for analyzing firn cores. The system has been used in the frame of the European Project for Ice Coring in Antarctica (EPICA) for in-situ analysis of several firn cores from Dronning Maud Land, Antarctica, and for the new ice core drilled at Dome C, Antarctica.

  18. Criticality safety analysis on fissile materials in Fukushima reactor cores

    SciTech Connect (OSTI)

    Liu, Xudong; Lemaitre-Xavier, E.; Ahn, Joonhong [Department of Nuclear Engineering, University of California, Berkeley, Berkeley, CA 94720 (United States); Hirano, Fumio [Japan Atomic Energy Agency, Geological Isolation Research and Development Directorate, Tokai-mura, Ibaraki 319-1194 (Japan)

    2013-07-01T23:59:59.000Z

    The present study focuses on the criticality analysis for geological disposal of damaged fuels from Fukushima reactor cores. Starting from the basic understanding of behaviors of plutonium and uranium, a scenario sequence for criticality event is considered. Due to the different mobility of plutonium and uranium in geological formations, the criticality safety is considered in two parts: (1) near-field plutonium system and (2) far-field low enriched uranium (LEU) system. For the near-field plutonium system, a mathematical analysis for pure-solute transport was given, assuming a particular buffer material and waste form configuration. With the transport and decay of plutonium accounted, the critical mass of plutonium was compared with the initial load of a single canister. Our calculation leads us to the conclusion that our system with the initial loading being the average mass of plutonium in an assembly just before the accident is very unlikely to become critical over time. For the far-field LEU system, due to the uncertainties in the geological and geochemical conditions, calculations were made in a parametric space that covers the variation of material compositions and different geometries. Results show that the LEU system could not remain sub-critical within the entire parameter space assumed, although in the iron-rich rock, the neutron multiplicity is significantly reduced.

  19. Core Analysis At Blue Mountain Geothermal Area (U.S. Geological...

    Open Energy Info (EERE)

    Blue Mountain Geothermal Area (U.S. Geological Survey, 2009) Exploration Activity Details Location Blue Mountain Geothermal Area Exploration Technique Core Analysis Activity Date...

  20. 100-KE REACTOR CORE REMOVAL PROJECT ALTERNATIVE ANALYSIS WORKSHOP REPORT

    SciTech Connect (OSTI)

    HARRINGTON RA

    2010-01-15T23:59:59.000Z

    On December 15-16, 2009, a 100-KE Reactor Core Removal Project Alternative Analysis Workshop was conducted at the Washington State University Consolidated Information Center, Room 214. Colburn Kennedy, Project Director, CH2M HILL Plateau Remediation Company (CHPRC) requested the workshop and Richard Harrington provided facilitation. The purpose of the session was to select the preferred Bio Shield Alternative, for integration with the Thermal Shield and Core Removal and develop the path forward to proceed with project delivery. Prior to this workshop, the S.A. Robotics (SAR) Obstruction Removal Alternatives Analysis (565-DLV-062) report was issued, for use prior to and throughout the session, to all the team members. The multidisciplinary team consisted ofrepresentatives from 100-KE Project Management, Engineering, Radcon, Nuclear Safety, Fire Protection, Crane/Rigging, SAR Project Engineering, the Department of Energy Richland Field Office, Environmental Protection Agency, Washington State Department of Ecology, Defense Nuclear Facility Safety Board, and Deactivation and Decommission subject matter experts from corporate CH2M HILL and Lucas. Appendix D contains the workshop agenda, guidelines and expectations, opening remarks, and attendance roster going into followed throughout the workshop. The team was successful in selecting the preferred alternative and developing an eight-point path forward action plan to proceed with conceptual design. Conventional Demolition was selected as the preferred alternative over two other alternatives: Diamond Wire with Options, and Harmonic Delamination with Conventional Demolition. The teams preferred alternative aligned with the SAR Obstruction Removal Alternative Analysis report conclusion. However, the team identified several Path Forward actions, in Appendix A, which upon completion will solidify and potentially enhance the Conventional Demolition alternative with multiple options and approaches to achieve project delivery. In brief, the Path Forward was developed to reconsider potential open air demolition areas; characterize to determine if any zircaloy exists, evaluate existing concrete data to determine additional characterization needs, size the new building to accommodate human machine interface and tooling, consider bucket thumb and use ofshape-charges in design, and finally to utilize complex-wide and industry explosive demolition lessons learned in the design approach. Appendix B documents these results from the team's use ofValue Engineering process tools entitled Weighted Analysis Alternative Matrix, Matrix Conclusions, Evaluation Criteria, and Alternative Advantages and Disadvantages. These results were further supported with the team's validation of parking-lot information sheets: memories (potential ideas to consider), issues/concerns, and assumptions, contained in Appendix C. Appendix C also includes the recorded workshop flipchart notes taken from the SAR Alternatives and Project Overview presentations. The SAR workshop presentations, including a 3-D graphic illustration demonstration video have been retained in the CHPRC project file, and were not included in this report due to size limitations. The workshop concluded with a round robin close-out where each member was engaged for any last minute items and meeting utility. In summary, the team felt the session was value added and looked forward to proceeding with the recommended actions and conceptual design.

  1. ANALYSIS OF THE SALT FEED TANK CORE SAMPLE

    SciTech Connect (OSTI)

    Reigel, M.; Cheng, W.

    2012-01-26T23:59:59.000Z

    The Saltstone Production Facility (SPF) immobilizes and disposes of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site (SRS). Low-level waste (LLW) streams from processes at SRS are stored in Tank 50 until the LLW can be transferred to the SPF for treatment and disposal. The Salt Feed Tank (SFT) at the Saltstone Production Facility (SPF) holds approximately 6500 gallons of low level waste from Tank 50 as well as drain water returned from the Saltstone Disposal Facility (SDF) vaults. Over the past several years, Saltstone Engineering has noted the accumulation of solids in the SFT. The solids are causing issues with pump performance, agitator performance, density/level monitoring, as well as taking up volume in the tank. The tank has been sounded at the same location multiple times to determine the level of the solids. The readings have been 12, 25 and 15 inches. The SFT is 8.5 feet high and 12 feet in diameter, therefore the solids account for approximately 10 % of the tank volume. Saltstone Engineering has unsuccessfully attempted to obtain scrape samples of the solids for analysis. As a result, Savannah River National Laboratory (SRNL) was tasked with developing a soft core sampler to obtain a sample of the solids and to analyze the core sample to aid in determining a path forward for removing the solids from the SFT. The source of the material in the SFT is the drain water return system where excess liquid from the Saltstone disposal vaults is pumped back to the SFT for reprocessing. It has been shown that fresh grout from the vault enter the drain water system piping. Once these grout solids return to the SFT, they settle in the tank, set up, and can't be reprocessed, causing buildup in the tank over time. The composition of the material indicates that it is potentially toxic for chromium and mercury and the primary radionuclide is cesium-137. Qualitative measurements show that the material is not cohesive and will break apart with some force.

  2. Core analysis in a low permeability sandstone reservoir: Results from the Multiwell Experiment

    SciTech Connect (OSTI)

    Sattler, A.R.

    1989-04-01T23:59:59.000Z

    Over 4100 ft (1100 ft oriented) of Mesaverde core was taken during the drilling of the three Multiwell Experiment (MWX) wells, for study in a comprehensive core analysis program. This core traversed five separate depositional environments (shoreline/marine, coastal, paludal, fluvial, and paralic), and almost every major sand in the Mesaverde at the site was sampled. This paper summarizes MWX core analysis and describes the petrophysical properties at the MWX site; reservoir parameters, including permeabilities of naturally fractured core; and mechanical rock properties including stress-related measurements. Some correlations are made between reservoir properties and mineralogy/petrology data. Comparisons are made between the properties of lenticular and blanket sandstone morphologies existing at the site. This paper provides an overview of a complete core analysis in a low-permeability sandstone reservoir. 66 refs., 17 figs. , 9 tabs.

  3. Thermal hydraulic performance analysis of a small integral pressurized water reactor core

    E-Print Network [OSTI]

    Blair, Stuart R. (Stuart Ryan), 1972-

    2003-01-01T23:59:59.000Z

    A thermal hydraulic analysis of the International Reactor Innovative and Secure (IRIS) core has been performed. Thermal margins for steady state and a selection of Loss Of Flow Accidents have been assessed using three ...

  4. CO2 & global temperature: Analysis of ice core and marine sediment data in

    E-Print Network [OSTI]

    Sengun, Mehmet Haluk

    CO2 & global temperature: Analysis of ice core and marine sediment data in combination with modeling of marine reservoir ages Gerrit Lohmann & Martin Butzin #12;Deglaciation CO2 vs. global temperature Ice cores: Temperature leads CO2 People (mainly outside the scientific comunity) use

  5. System Level Analysis of Fast, Per-Core DVFS using On-Chip Switching Regulators

    E-Print Network [OSTI]

    Brooks, David

    -level application of the regulator. In this paper, we describe and model these costs, and perform a comprehensive workloads found in modern systems, motivates the need for fast, per-core DVFS control. Voltage regulatorsSystem Level Analysis of Fast, Per-Core DVFS using On-Chip Switching Regulators Wonyoung Kim, Meeta

  6. Analysis of Dynamic Power Management on Multi-Core W. Lloyd Bircher and Lizy K. John

    E-Print Network [OSTI]

    John, Lizy Kurian

    Analysis of Dynamic Power Management on Multi-Core Processors W. Lloyd Bircher and Lizy K. John of Texas at Austin {bircher, ljohn}@ece.utexas.edu ABSTRACT Power management of multi-core processors management according to ACPI (Advanced Power and Configurations Interface) specifications is the common

  7. Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake, Madagascar)

    E-Print Network [OSTI]

    Boyer, Edmond

    Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake, Université d'Orléans, BP 6759, 45067 Orléans Cedex 2, France Abstract Seven samples from a 1 m long peat core targets because of their dominant or even exclusive OM content, peat deposits have received relatively

  8. Core Analysis At Valles Caldera - Sulphur Springs Geothermal...

    Open Energy Info (EERE)

    of the Valles caldera system. Notes Core samples were waxed upon retrieval to reduce drying and atmospheric alteration, and thermal conductivities were measured at a mean...

  9. Core Analysis At Valles Caldera - Sulphur Springs Geothermal...

    Open Energy Info (EERE)

    References Giday WoldeGabriel, Fraser Goff (1992) K-Ar Dates Of Hydrothermal Clays From Core Hole Vc-2B, Valles Caldera, New Mexico And Their Relation To Alteration In A...

  10. analysis identifies core: Topics by E-print Network

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

    not only from rotating core-collapse and bounce, the subsequent ring down of the proto-neutron star (PNS) as previously identified, but also from the formation of...

  11. Application of an artificial neural network to reactor core analysis

    SciTech Connect (OSTI)

    Seung Hwan Seong; Un Chul Lee [Seoul National Univ. (Korea, Republic of)

    1995-12-31T23:59:59.000Z

    To analyze three-dimensional reactor core behaviors, the finite difference or the finite element method have generally been used. Nodal method is adopted as another tool for analyzing transient core characteristics. These methods, however, require much calculation time to solve very complicated iterations for better convergence. Especially when the transient states are to be predicted, none of these methods can meet the requirements within the time span in which the operator can react. To overcome these difficulties, a new analytic model based on the artificial neural networks (ANNs) is suggested. Because trained ANNs are capable of modeling the input/output relationships of a nonlinear system without complex analogy, they are able to map the power distributions and calculate the eigenvalue corresponding to the core conditions in a short time and utilize the previous results by updating the weights of inter-connection between input and output patterns. To confirm the accuracy and capability, daily load-follow operation in a pressurized water reactor (PWR) is simulated using the new analytic model.

  12. Experimental ferrite core circuit analysis and design applied to an analog/digital converter

    E-Print Network [OSTI]

    Hughes, Robert William

    1965-01-01T23:59:59.000Z

    EXPKRflIENTAL FERRITE CORE CIRCUIT ANALYSIS A/4i) CESIGN APPLI ED' TO AN ANALOG+I QITAL -CCWERTER I I 'O' Thaaka RCSERT, NI. LL'I AN HQQAKS:-. , ";, , '. . :. . '. -:. '"":, , ':-. ', . -' ". ' t, . I I I' I, ' . Sobalttad, ta tb ~ Qra... , Na'fir. Sabjaat& ' Eiaktr leal EnCInaaring . EXPERIIIENTAL FERRITE CORE CIRCUIT ANALYSIS AND DESIGN APPLIED TO 'AN AMALGG/DIGITAL CONVERTER f 1 A, . Thea I'a t ROBERT Wl LI. I Al'Jl. HUGHES (Goober, ) ' (Me@bar) ' A'yprived . a'o . . to a4...

  13. Development of flow network analysis code for block type VHTR core by linear theory method

    SciTech Connect (OSTI)

    Lee, J. H.; Yoon, S. J. [Dept. of Nuclear Engr., Seoul National Univ., Daehak-dong, Gwanak-gu, Seoul, 151-742 (Korea, Republic of); Park, J. W. [Dept. of Nuclear and Energy Engr, Dongguk Univ., Seokjang-Dong, Gyeongju, Gyeongsangbuk-Do, 780-714 (Korea, Republic of); Park, G. C. [Dept. of Nuclear Engr., Seoul National Univ., Daehak-dong, Gwanak-gu, Seoul, 151-742 (Korea, Republic of)

    2012-07-01T23:59:59.000Z

    VHTR (Very High Temperature Reactor) is high-efficiency nuclear reactor which is capable of generating hydrogen with high temperature of coolant. PMR (Prismatic Modular Reactor) type reactor consists of hexagonal prismatic fuel blocks and reflector blocks. The flow paths in the prismatic VHTR core consist of coolant holes, bypass gaps and cross gaps. Complicated flow paths are formed in the core since the coolant holes and bypass gap are connected by the cross gap. Distributed coolant was mixed in the core through the cross gap so that the flow characteristics could not be modeled as a simple parallel pipe system. It requires lot of effort and takes very long time to analyze the core flow with CFD analysis. Hence, it is important to develop the code for VHTR core flow which can predict the core flow distribution fast and accurate. In this study, steady state flow network analysis code is developed using flow network algorithm. Developed flow network analysis code was named as FLASH code and it was validated with the experimental data and CFD simulation results. (authors)

  14. Full Core Reactor Analysis: Running Denovo on Jaguar

    SciTech Connect (OSTI)

    Jarrell, Joshua J [ORNL] [ORNL; Godfrey, Andrew T [ORNL] [ORNL; Evans, Thomas M [ORNL] [ORNL; Davidson, Gregory G [ORNL] [ORNL

    2013-01-01T23:59:59.000Z

    Fully-consistent, full-core, 3D, deterministic neutron transport simulations using the orthogonal mesh code Denovo were run on the massively parallel computing architecture Jaguar XT5. Using energy and spatial parallelization schemes, Denovo was able to efficiently scale to more than 160k processors. Cell-homogenized cross sections were used with step-characteristics, linear-discontinuous finite element, and trilinear-discontinuous finite element spatial methods. It was determined that using the finite element methods gave considerably more accurate eigenvalue solutions for large-aspect ratio meshes than using step-characteristics.

  15. Continuous Flow Analysis of Total Organic Carbon in Polar Ice Cores

    E-Print Network [OSTI]

    Stocker, Thomas

    Continuous Flow Analysis of Total Organic Carbon in Polar Ice Cores U R S F E D E R E R , * , , P, University of Bern, Bern, Switzerland, Oeschger Centre for Climate Change Research, University of Bern, Bern, Switzerland, and British Antarctic Survey, Cambridge, United Kingdom Received May 6, 2008. Revised manuscript

  16. Stability analysis of a nonlinear coupled-core reactor control system

    SciTech Connect (OSTI)

    Tsay, T.S.; Han, K.W.

    1987-12-01T23:59:59.000Z

    In this paper, stability-equation method is applied to the analysis of a large coupled-core reactor control system having multiple nonlinearities and adjustable parameters. The characteristics of the limit-cycle and the asymptotically stable regions can be easily defined in a parameter plane. A numerical example is given and comparisons with other methods in current literature are made.

  17. 1.2 CORE INTERPRETATION AND SEDIMENTOLOGICAL ANALYSIS 1.2.1 Generalized Core Description

    E-Print Network [OSTI]

    Schechter, David S.

    reservoir quality. Carbonate rocks are not very common in the analyzed cores. Lithofacies L2: Shales. Shale infrequently; the black color of these shales is a function of their high organic carbon content. Organics siltstone. This lithofacies is characterized by alternations of light and dark colored fine laminae, each

  18. PWR core design, neutronics evaluation and fuel cycle analysis for thorium-uranium breeding recycle

    SciTech Connect (OSTI)

    Bi, G.; Liu, C.; Si, S. [Shanghai Nuclear Engineering Research and Design Inst., No. 29, Hongcao Road, Shanghai, 200233 (China)

    2012-07-01T23:59:59.000Z

    This paper was focused on core design, neutronics evaluation and fuel cycle analysis for Thorium-Uranium Breeding Recycle in current PWRs, without any major change to the fuel lattice and the core internals, but substituting the UOX pellet with Thorium-based pellet. The fuel cycle analysis indicates that Thorium-Uranium Breeding Recycle is technically feasible in current PWRs. A 4-loop, 193-assembly PWR core utilizing 17 x 17 fuel assemblies (FAs) was taken as the model core. Two mixed cores were investigated respectively loaded with mixed reactor grade Plutonium-Thorium (PuThOX) FAs and mixed reactor grade {sup 233}U-Thorium (U{sub 3}ThOX) FAs on the basis of reference full Uranium oxide (UOX) equilibrium-cycle core. The UOX/PuThOX mixed core consists of 121 UOX FAs and 72 PuThOX FAs. The reactor grade {sup 233}U extracted from burnt PuThOX fuel was used to fabrication of U{sub 3}ThOX for starting Thorium-. Uranium breeding recycle. In UOX/U{sub 3}ThOX mixed core, the well designed U{sub 3}ThOX FAs with 1.94 w/o fissile uranium (mainly {sup 233}U) were located on the periphery of core as a blanket region. U{sub 3}ThOX FAs remained in-core for 6 cycles with the discharged burnup achieving 28 GWD/tHM. Compared with initially loading, the fissile material inventory in U{sub 3}ThOX fuel has increased by 7% via 1-year cooling after discharge. 157 UOX fuel assemblies were located in the inner of UOX/U{sub 3}ThOX mixed core refueling with 64 FAs at each cycle. The designed UOX/PuThOX and UOX/U{sub 3}ThOX mixed core satisfied related nuclear design criteria. The full core performance analyses have shown that mixed core with PuThOX loading has similar impacts as MOX on several neutronic characteristic parameters, such as reduced differential boron worth, higher critical boron concentration, more negative moderator temperature coefficient, reduced control rod worth, reduced shutdown margin, etc.; while mixed core with U{sub 3}ThOX loading on the periphery of core has no visible impacts on neutronic characteristics compared with reference full UOX core. The fuel cycle analysis has shown that {sup 233}U mono-recycling with U{sub 3}ThOX fuel could save 13% of natural uranium resource compared with UOX once through fuel cycle, slightly more than that of Plutonium single-recycling with MOX fuel. If {sup 233}U multi-recycling with U{sub 3}ThOX fuel is implemented, more natural uranium resource would be saved. (authors)

  19. Development of integrated core disruptive accident analysis code for FBR - ASTERIA-FBR

    SciTech Connect (OSTI)

    Ishizu, T.; Endo, H.; Tatewaki, I.; Yamamoto, T. [Japan Nuclear Energy Safety Organization JNES, Toranomon Towers Office, 4-1-28, Toranomon, Minato-ku, Tokyo (Japan); Shirakawa, N. [Inst. of Applied Energy IAE, Shimbashi SY Bldg., 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo (Japan)

    2012-07-01T23:59:59.000Z

    The evaluation of consequence at the severe accident is the most important as a safety licensing issue for the reactor core of liquid metal cooled fast breeder reactor (LMFBR), since the LMFBR core is not in an optimum condition from the viewpoint of reactivity. This characteristics might induce a super-prompt criticality due to the core geometry change during the core disruptive accident (CDA). The previous CDA analysis codes have been modeled in plural phases dependent on the mechanism driving a super-prompt criticality. Then, the following event is calculated by connecting different codes. This scheme, however, should introduce uncertainty and/or arbitrary to calculation results. To resolve the issues and obtain the consistent calculation results without arbitrary, JNES is developing the ASTERIA-FBR code for the purpose of providing the cross-check analysis code, which is another required scheme to confirm the validity of the evaluation results prepared by applicants, in the safety licensing procedure of the planned high performance core of Monju. ASTERIA-FBR consists of the three major calculation modules, CONCORD, dynamic-GMVP, and FEMAXI-FBR. CONCORD is a three-dimensional thermal-hydraulics calculation module with multi-phase, multi-component, and multi-velocity field model. Dynamic-GMVP is a space-time neutronics calculation module. FEMAXI-FBR calculates the fuel pellet deformation behavior and fuel pin failure behavior. This paper describes the needs of ASTERIA-FBR development, major module outlines, and the model validation status. (authors)

  20. Experimental investigation and CFD analysis on cross flow in the core of PMR200

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

    Lee, Jeong-Hun; Yoon, Su-Jong; Cho, Hyoung-Kyu; Jae, Moosung; Park, Goon-Cherl

    2015-09-01T23:59:59.000Z

    The Prismatic Modular Reactor (PMR) is one of the major Very High Temperature Reactor (VHTR) concepts, which consists of hexagonal prismatic fuel blocks and reflector blocks made of nuclear gradegraphite. However, the shape of the graphite blocks could be easily changed by neutron damage duringthe reactor operation and the shape change can create gaps between the blocks inducing the bypass flow.In the VHTR core, two types of gaps, a vertical gap and a horizontal gap which are called bypass gap and cross gap, respectively, can be formed. The cross gap complicates the flow field in the reactor core by connectingmore »the coolant channel to the bypass gap and it could lead to a loss of effective coolant flow in the fuel blocks. Thus, a cross flow experimental facility was constructed to investigate the cross flow phenomena in the core of the VHTR and a series of experiments were carried out under varying flow rates and gap sizes. The results of the experiments were compared with CFD (Computational Fluid Dynamics) analysis results in order to verify its prediction capability for the cross flow phenomena. Fairly good agreement was seen between experimental results and CFD predictions and the local characteristics of the cross flow was discussed in detail. Based on the calculation results, pressure loss coefficient across the cross gap was evaluated, which is necessary for the thermo-fluid analysis of the VHTR core using a lumped parameter code.« less

  1. The Neutronics Design and Analysis of a 200-MW(electric) Simplified Boiling Water Reactor Core

    SciTech Connect (OSTI)

    Tinkler, Daniel R.; Downar, Thomas J. [Purdue University (United States)

    2003-06-15T23:59:59.000Z

    A 200-MW(electric) simplified boiling water reactor (SBWR) was designed and analyzed under sponsorship of the U.S. Department of Energy Nuclear Energy Research Initiative program. The compact size of a 200-MW(electric) reactor makes it attractive for countries with a less well developed engineering infrastructure, as well as for developed countries seeking to tailor generation capacity more closely to the growth of their electricity demand. The 200-MW(electric) core design reported here is based on the 600-MW(electric) General Electric SBWR core, which was first analyzed in the work performed here in order to qualify the computer codes used in the analysis. Cross sections for the 8 x 8 fuel assembly design were generated with the HELIOS lattice physics code, and core simulation was performed with the U.S. Nuclear Regulatory Commission codes RELAP5/PARCS. In order to predict the critical heat flux, the Hench-Gillis correlation was implemented in the RELAP5 code. An equilibrium cycle was designed for the 200-MW(electric) core, which provided a cycle length of more than 2 yr and satisfied the minimum critical power ratio throughout the core life.

  2. Analysis of core damage frequency from internal events: Peach Bottom, Unit 2

    SciTech Connect (OSTI)

    Kolaczkowski, A.M.; Lambright, J.A.; Ferrell, W.L.; Cathey, N.G.; Najafi, B.; Harper, F.T.

    1986-10-01T23:59:59.000Z

    This document contains the internal event initiated accident sequence analyses for Peach Bottom, Unit 2; one of the reference plants being examined as part of the NUREG-1150 effort by the Nuclear Regulatory Commission. NUREG-1150 will document the risk of a selected group of nuclear power plants. As part of that work, this report contains the overall core damage frequency estimate for Peach Bottom, Unit 2, and the accompanying plant damage state frequencies. Sensitivity and uncertainty analyses provided additional insights regarding the dominant contributors to the Peach Bottom core damage frequency estimate. The mean core damage frequency at Peach Bottom was calculated to be 8.2E-6. Station blackout type accidents (loss of all ac power) were found to dominate the overall results. Anticipated Transient Without Scram accidents were also found to be non-negligible contributors. The numerical results are largely driven by common mode failure probability estimates and to some extent, human error. Because of significant data and analysis uncertainties in these two areas (important, for instance, to the most dominant scenario in this study), it is recommended that the results of the uncertainty and sensitivity analyses be considered before any actions are taken based on this analysis.

  3. TRACE/PARCS Core Modeling of a BWR/5 for Accident Analysis of ATWS Events

    SciTech Connect (OSTI)

    Cuadra A.; Baek J.; Cheng, L.; Aronson, A.; Diamond, D.; Yarsky, P.

    2013-11-10T23:59:59.000Z

    The TRACE/PARCS computational package [1, 2] isdesigned to be applicable to the analysis of light water reactor operational transients and accidents where the coupling between the neutron kinetics (PARCS) and the thermal-hydraulics and thermal-mechanics (TRACE) is important. TRACE/PARCS has been assessed for itsapplicability to anticipated transients without scram(ATWS) [3]. The challenge, addressed in this study, is to develop a sufficiently rigorous input model that would be acceptable for use in ATWS analysis. Two types of ATWS events were of interest, a turbine trip and a closure of main steam isolation valves (MSIVs). In the first type, initiated by turbine trip, the concern is that the core will become unstable and large power oscillations will occur. In the second type,initiated by MSIV closure,, the concern is the amount of energy being placed into containment and the resulting emergency depressurization. Two separate TRACE/PARCS models of a BWR/5 were developed to analyze these ATWS events at MELLLA+ (maximum extended load line limit plus)operating conditions. One model [4] was used for analysis of ATWS events leading to instability (ATWS-I);the other [5] for ATWS events leading to emergency depressurization (ATWS-ED). Both models included a large portion of the nuclear steam supply system and controls, and a detailed core model, presented henceforth.

  4. Analysis of core damage frequency: Peach Bottom, Unit 2 internal events appendices

    SciTech Connect (OSTI)

    Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L. (Science Applications International Corp., Albuquerque, NM (USA); Sandia National Labs., Albuquerque, NM (USA))

    1989-08-01T23:59:59.000Z

    This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. The mean core damage frequency is 4.5E-6 with 5% and 95% uncertainty bounds of 3.5E-7 and 1.3E-5, respectively. Station blackout type accidents (loss of all ac power) contributed about 46% of the core damage frequency with Anticipated Transient Without Scram (ATWS) accidents contributing another 42%. The numerical results are driven by loss of offsite power, transients with the power conversion system initially available operator errors, and mechanical failure to scram. 13 refs., 345 figs., 171 tabs.

  5. Analysis of volume distribution of power loss in ferrite cores M. LoBue, V. Loyau, and F. Mazaleyrat

    E-Print Network [OSTI]

    Boyer, Edmond

    Analysis of volume distribution of power loss in ferrite cores M. LoBue, V. Loyau, and F the section of ferrite cores under AC excitation. The technique is based on two distinct calorimetric methods the procedure to an industrial sample of Mn-Zn ferrite under controlled sinusoidal excitation with a peak

  6. Low time resolution analysis of polar ice cores cannot detect impulsive nitrate events

    E-Print Network [OSTI]

    Smart, D F; Melott, A L; Laird, C M

    2015-01-01T23:59:59.000Z

    Ice cores are archives of climate change and possibly large solar proton events (SPEs). Wolff et al. (2012) used a single event, a nitrate peak in the GISP2-H core, which McCracken et al. (2001a) time associated with the poorly quantified 1859 Carrington event, to discredit SPE-produced, impulsive nitrate deposition in polar ice. This is not the ideal test case. We critique the Wolff et al. analysis and demonstrate that the data they used cannot detect impulsive nitrate events because of resolution limitations. We suggest re-examination of the top of the Greenland ice sheet at key intervals over the last two millennia with attention to fine resolution and replicate sampling of multiple species. This will allow further insight into polar depositional processes on a sub-seasonal scale, including atmospheric sources, transport mechanisms to the ice sheet, post-depositional interactions, and a potential SPE association.

  7. Determination of power distribution in the VVER-440 core on the basis of data from in-core monitors by means of a metric analysis

    SciTech Connect (OSTI)

    Kryanev, A. V.; Udumyan, D. K. [National Research Nuclear University “MEPHI,” (Russian Federation); Kurchenkov, A. Yu., E-mail: s327@vver.kiae.ru; Gagarinskiy, A. A. [National Research Center Kurchatov Institute (Russian Federation)

    2014-12-15T23:59:59.000Z

    Problems associated with determining the power distribution in the VVER-440 core on the basis of a neutron-physics calculation and data from in-core monitors are considered. A new mathematical scheme is proposed for this on the basis of a metric analysis. In relation to the existing mathematical schemes, the scheme in question improves the accuracy and reliability of the resulting power distribution.

  8. BOLD VENTURE COMPUTATION SYSTEM for nuclear reactor core analysis, Version III

    SciTech Connect (OSTI)

    Vondy, D.R.; Fowler, T.B.; Cunningham, G.W. III.

    1981-06-01T23:59:59.000Z

    This report is a condensed documentation for VERSION III of the BOLD VENTURE COMPUTATION SYSTEM for nuclear reactor core analysis. An experienced analyst should be able to use this system routinely for solving problems by referring to this document. Individual reports must be referenced for details. This report covers basic input instructions and describes recent extensions to the modules as well as to the interface data file specifications. Some application considerations are discussed and an elaborate sample problem is used as an instruction aid. Instructions for creating the system on IBM computers are also given.

  9. Core Analysis At Geysers Area (Lambert & Epstein, 1992) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area (Boitnott, 2003) Jump

  10. Core Analysis At Kilauea East Rift Geothermal Area (Quane, Et Al., 2003) |

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area (Boitnott, 2003) JumpOpen

  11. Core Analysis At Long Valley Caldera Geothermal Area (Sorey, Et Al., 1991)

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area (Boitnott, 2003) JumpOpen|

  12. Core Analysis At Newberry Caldera Area (Carothers, Et Al., 1987) | Open

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area (Boitnott, 2003)

  13. Core Analysis At U.S. West Region (Laney, 2005) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area

  14. Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area (Ito &

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area(Armstrong, Et Al.,

  15. Core Analysis For The Development And Constraint Of Physical Models Of

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|Core Analysis At Geysers Area(Armstrong, Et Al.,Et

  16. Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling

    SciTech Connect (OSTI)

    Kneafsey, Timothy J.; Lu, Hailong; Winters, William; Boswell, Ray; Hunter, Robert; Collett, Timothy S.

    2009-09-01T23:59:59.000Z

    Collecting and preserving undamaged core samples containing gas hydrates from depth is difficult because of the pressure and temperature changes encountered upon retrieval. Hydrate-bearing core samples were collected at the BPXA-DOE-USGS Mount Elbert Gas Hydrate Stratigraphic Test Well in February 2007. Coring was performed while using a custom oil-based drilling mud, and the cores were retrieved by a wireline. The samples were characterized and subsampled at the surface under ambient winter arctic conditions. Samples thought to be hydrate bearing were preserved either by immersion in liquid nitrogen (LN), or by storage under methane pressure at ambient arctic conditions, and later depressurized and immersed in LN. Eleven core samples from hydrate-bearing zones were scanned using x-ray computed tomography to examine core structure and homogeneity. Features observed include radial fractures, spalling-type fractures, and reduced density near the periphery. These features were induced during sample collection, handling, and preservation. Isotopic analysis of the methane from hydrate in an initially LN-preserved core and a pressure-preserved core indicate that secondary hydrate formation occurred throughout the pressurized core, whereas none occurred in the LN-preserved core, however no hydrate was found near the periphery of the LN-preserved core. To replicate some aspects of the preservation methods, natural and laboratory-made saturated porous media samples were frozen in a variety of ways, with radial fractures observed in some LN-frozen sands, and needle-like ice crystals forming in slowly frozen clay-rich sediments. Suggestions for hydrate-bearing core preservation are presented.

  17. Partial Safety Analysis for a Reduced Uranium Enrichment Core for the High Flux Isotope Reactor

    SciTech Connect (OSTI)

    Primm, Trent [ORNL; Gehin, Jess C [ORNL

    2009-04-01T23:59:59.000Z

    A computational model of the reactor core of the High Flux Isotope Rector (HFIR) was developed in order to analyze non-destructive accidents caused by transients during reactor operation. The reactor model was built for the latest version of the nuclear analysis software package called Program for the Analysis of Reactor Transients (PARET). Analyses performed with the model constructed were compared with previous data obtained with other tools in order to benchmark the code. Finally, the model was used to analyze the behavior of the reactor under transients using a different nuclear fuel with lower enrichment of uranium (LEU) than the fuel currently used, which has a high enrichment of uranium (HEU). The study shows that the presence of fertile isotopes in LEU fuel, which increases the neutron resonance absorption, reduces the impact of transients on the fuel and enhances the negative reactivity feedback, thus, within the limitations of this study, making LEU fuel appear to be a safe alternative fuel for the reactor core.

  18. Coupling the core analysis program DeCART to the fuel performance application BISON

    SciTech Connect (OSTI)

    Gleicher, F. N.; Spencer, B.; Novascone, S.; Williamson, R.; Martineau, R. C. [Idaho National Laboratory, 2525 N. Fremont Avenue, Idaho Falls, ID 83415 (United States); Rose, M.; Downar, T. J.; Collins, B. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, MI 48105 (United States)

    2013-07-01T23:59:59.000Z

    The 3D neutron transport and core analysis program DeCART was coupled to the fuels performance application BISON to provide a higher fidelity tool for fuel performance simulation. This project is motivated by the desire to couple a high fidelity core analysis program (based on the method of characteristics) to a high fidelity fuel performance program, both of which can simulate 3D problems. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during burnup or a fast transient. BISON implicitly solves coupled thermomechanical equations for the fuel on a sub-millimeter level finite element mesh. A method was developed for mapping the fission rate density and fast neutron flux from DeCART to BISON. Multiple depletion cases were run with one-way data transfer from DeCART to BISON. The one-way data transfer of fission rate density is shown to agree with the fission rate density obtained from an internal Lassman-style model in BISON. One-way data transfer was also demonstrated in a 3D case in which azimuthal asymmetry was induced in the fission rate density profile of a fuel rod modeled in DeCART. Two-way data transfer was established by mapping the temperature distribution from BISON to DeCART. A Picard iterative algorithm was developed for the loose coupling with two-way data transfer. (authors)

  19. Thermal hydraulic method for whole core design analysis of an HTGR

    SciTech Connect (OSTI)

    Huning, A. J.; Garimella, S. [George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA (United States)

    2013-07-01T23:59:59.000Z

    A new thermal hydraulic method and initial results are presented for core-wide steady state analysis of prismatic High Temperature Gas-Cooled Reactors (HTGR). The method allows for the complete solution of temperature and coolant mass flow distribution by solving quasi-steady energy balances for the discretized core. Assembly blocks are discretized into unit cells for which the average temperature of each unit cell is determined. Convective heat removal is coupled to the unit cell energy balances by a 1-D axial flow model. The flow model uses established correlations for friction factor and Nusselt number. Bypass flow is explicitly calculated by using an initial guess for mass flow distribution and determining the exit pressure of each flow channel. The mass flow distribution is updated until a uniform core exit pressure condition is reached. Results are obtained for the MHTGR-350 with emphasis on the change in thermal hydraulic parameters due to various steady state power profiles and bypass gap widths. Steady state temperature distribution and its variations are discussed. (authors)

  20. Near Real-time Data Analysis of Core-Collapse Supernova Simulations With Bellerophon

    SciTech Connect (OSTI)

    Lingerfelt, Eric J [ORNL] [ORNL; Messer, Bronson [ORNL] [ORNL; Desai, Sharvari S [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Holt, Chastity A [Appalachian State University] [Appalachian State University; Lentz, Eric J [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK)

    2014-01-01T23:59:59.000Z

    We present an overview of a software system, Bellerophon, built to support a production-level HPC application called CHIMERA, which simulates core-collapse supernova events at the petascale. Developed over the last four years, Bellerophon enables CHIMERA s geographically dispersed team of collaborators to perform data analysis in near real-time. Its n-tier architecture provides an encapsulated, end-to-end software solution that enables the CHIMERA team to quickly and easily access highly customizable animated and static views of results from anywhere in the world via a web-deliverable, cross-platform desktop application. In addition, Bellerophon addresses software engineering tasks for the CHIMERA team by providing an automated mechanism for performing regression testing on a variety of supercomputing platforms. Elements of the team s workflow management needs are met with software tools that dynamically generate code repository statistics, access important online resources, and monitor the current status of several supercomputing resources.

  1. Analysis of core-concrete interaction event with flooding for the Advanced Neutron Source reactor

    SciTech Connect (OSTI)

    Kim, S.H.; Taleyarkhan, R.P.; Georgevich, V.; Navarro-Valenti, S.

    1993-11-01T23:59:59.000Z

    This paper discusses salient aspects of the methodology, assumptions, and modeling of various features related to estimation of source terms from an accident involving a molten core-concrete interaction event (with and without flooding) in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for this postulated severe accident. Several design features (such as rupture disks) are examined to study containment response during this severe accident. Also, thermal-hydraulic response of the containment and radionuclide transport and retention in the containment are studied. The results are described as transient variations of source terms, which are then used for studying off-site radiological consequences and health effects for the support of the Conceptual Safety Analysis Report for ANS. The results are also to be used to examine the effectiveness of subpile room flooding during this type of severe accident.

  2. Analysis on fuel breeding capability of FBR core region based on minor actinide recycling doping

    SciTech Connect (OSTI)

    Permana, Sidik; Novitrian,; Waris, Abdul [Nuclear Physics and Biophysics Research Division, Physics Department, Institut Teknologi Bandung (Indonesia); Ismail [Center for Technical Assessment of Nuclear Installation and Materials, Indonesian Nuclear Energy Regulatory (Indonesia); Suzuki, Mitsutoshi [Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA) (Japan); Saito, Masaki [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology (Japan)

    2014-09-30T23:59:59.000Z

    Nuclear fuel breeding based on the capability of fuel conversion capability can be achieved by conversion ratio of some fertile materials into fissile materials during nuclear reaction processes such as main fissile materials of U-233, U-235, Pu-239 and Pu-241 and for fertile materials of Th-232, U-238, and Pu-240 as well as Pu-238. Minor actinide (MA) loading option which consists of neptunium, americium and curium will gives some additional contribution from converted MA into plutonium such as conversion Np-237 into Pu-238 and it's produced Pu-238 converts to Pu-239 via neutron capture. Increasing composition of Pu-238 can be used to produce fissile material of Pu-239 as additional contribution. Trans-uranium (TRU) fuel (Mixed fuel loading of MOX (U-Pu) and MA composition) and mixed oxide (MOX) fuel compositions are analyzed for comparative analysis in order to show the effect of MA to the plutonium productions in core in term of reactor criticality condition and fuel breeding capability. In the present study, neptunium (Np) nuclide is used as a representative of MAin trans-uranium (TRU) fuel composition as Np-MOX fuel type. It was loaded into the core region gives significant contribution to reduce the excess reactivity in comparing to mixed oxide (MOX) fuel and in the same time it contributes to increase nuclear fuel breeding capability of the reactor. Neptunium fuel loading scheme in FBR core region gives significant production of Pu-238 as fertile material to absorp neutrons for reducing excess reactivity and additional contribution for fuel breeding.

  3. Documented Safety Analysis Addendum for the Neutron Radiography Reactor Facility Core Conversion

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2009-05-01T23:59:59.000Z

    The Neutron Radiography Reactor Facility (NRAD) is a Training, Research, Isotope Production, General Atomics (TRIGA) reactor which was installed in the Idaho National Laboratory (INL) Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) in the mid 1970s. The facility provides researchers the capability to examine both irradiated and non-irradiated materials in support of reactor fuel and components programs through non-destructive neutron radiography examination. The facility has been used in the past as one facet of a suite of reactor fuels and component examination facilities available to researchers at the INL and throughout the DOE complex. The facility has also served various commercial research activities in addition to the DOE research and development support. The reactor was initially constructed using Fuel Lifetime Improvement Program (FLIP)- type highly enriched uranium (HEU) fuel obtained from the dismantled Puerto Rico Nuclear Center (PRNC) reactor. In accordance with international non-proliferation agreements, the NRAD core will be converted to a low enriched uranium (LEU) fuel and will continue to utilize the PRNC control rods, control rod drives, startup source, and instrument console as was previously used with the HEU core. The existing NRAD Safety Analysis Report (SAR) was created and maintained in the preferred format of the day, combining sections of both DOE-STD-3009 and Nuclear Regulatory Commission Regulatory Guide 1.70. An addendum was developed to cover the refueling and reactor operation with the LEU core. This addendum follows the existing SAR format combining required formats from both the DOE and NRC. This paper discusses the project to successfully write a compliant and approved addendum to the existing safety basis documents.

  4. Paleoclimate and Glaciological Reconstruction in Central Asia Through The Collection and Analysis of Ice Cores and Instrumental Data From the Tien Shan

    SciTech Connect (OSTI)

    Cameron P. Wake; Vladimir Aizen; Karl Kreutz

    2001-05-30T23:59:59.000Z

    Paleoclimate and Glaciological Reconstruction in Central Asis Through The Collection And Analysis of Ice Cores and Instrumental Data From The Tien Shan

  5. Measurement and analysis of fractures in vertical, slant, and horizontal core, with examples from the Mesaverde formation

    SciTech Connect (OSTI)

    Lorenz, J.C. (Sandia National Labs., Albuquerque, NM (United States)); Hill, R.E. (CER Corp., Las Vegas, NV (United States))

    1991-01-01T23:59:59.000Z

    Optimum analysis of natural fracture characteristics and distributions in reservoirs requires conscientious supervision of coring operations, on-site core processing, careful layout and marketing of the core, and detailed measurement of fracture characteristics. Natural fractures provide information on the in situ permeability system, and coring-induced fractures provide data on the in situ stresses. Fracture data derived from vertical core should include fracture height, type and location of fracture terminations with respect to lithologic heterogeneity, fracture planatary and roughness, and distribution with depth. Fractures in core from either a vertical or a deviated well will yield information on dip, dip azimuth, strike, mineralization, and the orientation of fractures relative to the in situ stresses. Only measurements of fractures in core from a deviated/horizontal well will provide estimates of fracture spacing and porosity. These data can be graphed and cross-plotted to yield semi-quantitative fracture characteristics for reservoir models. Data on the orientations of fractures relative to each other in unoriented core can be nearly as useful as the absolute orientations of fractures. A deviated pilot hole is recommended for fracture assessment prior to a drilling horizontal production well because it significantly enhances the chances of fracture intersection, and therefore of fracture characterization. 35 refs., 20 figs., 2 tabs.

  6. Analysis of core damage frequency due to external events at the DOE (Department of Energy) N-Reactor

    SciTech Connect (OSTI)

    Lambright, J.A.; Bohn, M.P.; Daniel, S.L. (Sandia National Labs., Albuquerque, NM (USA)); Baxter, J.T. (Westinghouse Hanford Co., Richland, WA (USA)); Johnson, J.J.; Ravindra, M.K.; Hashimoto, P.O.; Mraz, M.J.; Tong, W.H.; Conoscente, J.P. (EQE, Inc., San Francisco, CA (USA)); Brosseau, D.A. (ERCE, Inc., Albuquerque, NM (USA))

    1990-11-01T23:59:59.000Z

    A complete external events probabilistic risk assessment has been performed for the N-Reactor power plant, making full use of all insights gained during the past ten years' developments in risk assessment methodologies. A detailed screening analysis was performed which showed that all external events had negligible contribution to core damage frequency except fires, seismic events, and external flooding. A limited scope analysis of the external flooding risk indicated that it is not a major risk contributor. Detailed analyses of the fire and seismic risks resulted in total (mean) core damage frequencies of 1.96E-5 and 4.60E-05 per reactor year, respectively. Detailed uncertainty analyses were performed for both fire and seismic risks. These results show that the core damage frequency profile for these events is comparable to that found for existing commercial power plants if proposed fixes are completed as part of the restart program. 108 refs., 85 figs., 80 tabs.

  7. Evaluation of Counter-Based Dynamic Load Balancing Schemes for Massive Contingency Analysis on Over 10,000 Cores

    SciTech Connect (OSTI)

    Chen, Yousu; Huang, Zhenyu; Rice, Mark J.

    2012-12-27T23:59:59.000Z

    Contingency analysis studies are necessary to assess the impact of possible power system component failures. The results of the contingency analysis are used to ensure the grid reliability, and in power market operation for the feasibility test of market solutions. Currently, these studies are performed in real time based on the current operating conditions of the grid with a set of pre-selected contingency list, which might result in overlooking some critical contingencies caused by variable system status. To have a complete picture of a power grid, more contingencies need to be studied to improve grid reliability. High-performance computing techniques hold the promise of being able to perform the analysis for more contingency cases within a much shorter time frame. This paper evaluates the performance of counter-based dynamic load balancing schemes for a massive contingency analysis program on 10,000+ cores. One million N-2 contingency analysis cases with a Western Electricity Coordinating Council power grid model have been used to demonstrate the performance. The speedup of 3964 with 4096 cores and 7877 with 10240 cores are obtained. This paper reports the performance of the load balancing scheme with a single counter and two counters, describes disk I/O issues, and discusses other potential techniques for further improving the performance.

  8. High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor

    SciTech Connect (OSTI)

    Francesco Venneri; Chang-Keun Jo; Jae-Man Noh; Yonghee Kim; Claudio Filippone; Jonghwa Chang; Chris Hamilton; Young-Min Kim; Ji-Su Jun; Moon-Sung Cho; Hong-Sik Lim; MIchael A. Pope; Abderrafi M. Ougouag; Vincent Descotes; Brian Boer

    2010-09-01T23:59:59.000Z

    The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450MWth DB-HTRs. The TRISO fuel microanalysis covers the gas pressure buildup in a coated fuel particle including helium production, the thermo-mechanical behavior of a CFP, the failure probabilities of CFPs, the temperature distribution in a CPF, and the fission product (FP) transport in a CFP and a graphite. In Chapter VIII, it contains the core design and analysis of sodium cooled fast reactor (SFR) with deep burn HTR reactor. It considers a synergistic combination of the DB-MHR and an SFR burner for a safe and efficient transmutation of the TRUs from LWRs. Chapter IX describes the design and analysis results of the self-cleaning (or self-recycling) HTR core. The analysis is considered zero and 5-year cooling time of the spent LWR fuels.

  9. Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake, Madagascar): diagenesis appraisal and consequences for palaeoenvironmental

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake and petrographical work [2], we applied such an approach to the analysis of a peat core section to get additional (saturated and unsaturated n-FAs, plus i-C16) at the surface of the peat sequence and low amounts

  10. EVALUATION OF CORE PHYSICS ANALYSIS METHODS FOR CONVERSION OF THE INL ADVANCED TEST REACTOR TO LOW-ENRICHMENT FUEL

    SciTech Connect (OSTI)

    Mark DeHart; Gray S. Chang

    2012-04-01T23:59:59.000Z

    Computational neutronics studies to support the possible conversion of the ATR to LEU are underway. Simultaneously, INL is engaged in a physics methods upgrade project to put into place modern computational neutronics tools for future support of ATR fuel cycle and experiment analysis. A number of experimental measurements have been performed in the ATRC in support of the methods upgrade project, and are being used to validate the new core physics methods. The current computational neutronics work is focused on performance of scoping calculations for the ATR core loaded with a candidate LEU fuel design. This will serve as independent confirmation of analyses that have been performed previously, and will evaluate some of the new computational methods for analysis of a candidate LEU fuel for ATR.

  11. Developing Fully Coupled Dynamical Reactor Core Isolation System Models in RELAP-7 for Extended Station Black-Out Analysis

    SciTech Connect (OSTI)

    Haihua Zhao; Ling Zou; Hongbin Zhang; David Andrs; Richard Martineau

    2014-04-01T23:59:59.000Z

    The reactor core isolation cooling (RCIC) system in a boiling water reactor (BWR) provides makeup water to the reactor vessel for core cooling when the main steam lines are isolated and the normal supply of water to the reactor vessel is lost. It was one of the very few safety systems still available during the Fukushima Daiichi accidents after the tsunamis hit the plants and the system successfully delayed the core meltdown for a few days for unit 2 & 3. Therefore, detailed models for RCIC system components are indispensable to understand extended station black-out accidents (SBO) for BWRs. As part of the effort to develop the new generation reactor system safety analysis code RELAP-7, major components to simulate the RCIC system have been developed. This paper describes the models for those components such as turbine, pump, and wet well. Selected individual component test simulations and a simplified SBO simulation up to but before core damage is presented. The successful implementation of the simplified RCIC and wet well models paves the way to further improve the models for safety analysis by including more detailed physical processes in the near future.

  12. ESPP Functional Genomics and Imaging Core: Cell wide analysis of Metal-Reducing Bacteria

    E-Print Network [OSTI]

    Mukhopadhyay, Aindrila

    2014-01-01T23:59:59.000Z

    and Environmental Research, Genomics:GTL Program throughESPP Functional Genomics and Imaging Core: Cell widemetals. The Functional Genomics and Imaging Core (FGIC)

  13. Time-resolved characterization and energy balance analysis of implosion core in shock-ignition experiments at OMEGA

    SciTech Connect (OSTI)

    Florido, R., E-mail: ricardo.florido@ulpgc.es; Mancini, R. C.; Nagayama, T. [Department of Physics, University of Nevada, Reno, Nevada 89557 (United States); Tommasini, R. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Delettrez, J. A.; Regan, S. P. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)

    2014-10-15T23:59:59.000Z

    Time-resolved temperature and density conditions in the core of shock-ignition implosions have been determined for the first time. The diagnostic method relies on the observation, with a streaked crystal spectrometer, of the signature of an Ar tracer added to the deuterium gas fill. The data analysis confirms the importance of the shell attenuation effect previously noted on time-integrated spectroscopic measurements of thick-wall targets [R. Florido et al., Phys. Rev. E 83, 066408 (2011)]. This effect must be taken into account in order to obtain reliable results. The extracted temperature and density time-histories are representative of the state of the core during the implosion deceleration and burning phases. As a consequence of the ignitor shock launched by the sharp intensity spike at the end of the laser pulse, observed average core electron temperature and mass density reach T???1100?eV and ????2?g/cm{sup 3}; then temperature drops to T???920?eV while density rises to ????3.4?g/cm{sup 3} about the time of peak compression. Compared to 1D hydrodynamic simulations, the experiment shows similar maximum temperatures and smaller densities. Simulations do not reproduce all observations. Differences are noted in the heating dynamics driven by the ignitor shock and the optical depth time-history of the compressed shell. Time-histories of core conditions extracted from spectroscopy show that the implosion can be interpreted as a two-stage polytropic process. Furthermore, an energy balance analysis of implosion core suggests an increase in total energy greater than what 1D hydrodynamic simulations predict. This new methodology can be implemented in other ICF experiments to look into implosion dynamics and help to understand the underlying physics.

  14. Analysis of core damage frequency: Peach Bottom, Unit 2 internal events

    SciTech Connect (OSTI)

    Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L. (Science Applications International Corp., Albuquerque, NM (USA); Sandia National Labs., Albuquerque, NM (USA))

    1989-08-01T23:59:59.000Z

    This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. 58 refs., 58 figs., 52 tabs.

  15. ABWR start-up test analysis using BWR core simulator with three-dimensional direct response matrix method

    SciTech Connect (OSTI)

    Mitsuyasu, T.; Ishii, K.; Hino, T.; Aoyama, M. [Hitachi, Ltd., Hitachi Research Laboratory, 2-1 Omika-cho 7-chome, Hitachi-shi Ibaraki-ken, 319-1221 (Japan)

    2012-07-01T23:59:59.000Z

    The ABWR start-up test analysis has been done with the BWR core simulator using the three--dimensional direct response matrix (3D-DRM) method. The Monte Carlo code VMONT made the sub-response matrices for the 3D-DRM method. Each boundary surface was subdivided by 4 x 4 for transverse segments, by 4 for angular segments and by 4 for axial zones in a node. For the calculation speedup, the 3D-DRM code used the divided sub-response matrices data set. The code used the MPI and OpenMP for the parallelized method. The median value is set as the average critical eigenvalues. The changes from the maximum value to the minimum value are 0.34 %{Delta}k with the spectral history method and 0.40 %{Delta}k without it, and the respective standard deviations were 0.12 % and 0.14 %. Using the spectral history method decreased the variation by 0.06 %{Delta}k. The root mean square differences of the axial power distribution were about 6 % between the analysis results and the plant data. Using the currents which converged in the previous exposure step reduced the number of iterations when the CR pattern changed only slightly. The averaged calculation time for each exposure step was about 5 hours on 12 PC Linux cluster servers with Core 2 Quad 3 GHz. (authors)

  16. Analysis of fuel options for the breakeven core configuration of the Advanced Recycling Reactor

    SciTech Connect (OSTI)

    Stauff, N.E.; Klim, T.K.; Taiwo, T.A. [Argonne National Laboratory, Argonne, IL (United States); Fiorina, C. [Politecnico di Milano, Milan (Italy); Franceschini, F. [Westinghouse Electric Company LLC., Cranberry Township, Pennsylvania (United States)

    2013-07-01T23:59:59.000Z

    A trade-off study is performed to determine the impacts of various fuel forms on the core design and core physics characteristics of the sodium-cooled Toshiba- Westinghouse Advanced Recycling Reactor (ARR). The fuel forms include oxide, nitride, and metallic forms of U and Th. The ARR core configuration is redesigned with driver and blanket regions in order to achieve breakeven fissile breeding performance with the various fuel types. State-of-the-art core physics tools are used for the analyses. In addition, a quasi-static reactivity balance approach is used for a preliminary comparison of the inherent safety performances of the various fuel options. Thorium-fueled cores exhibit lower breeding ratios and require larger blankets compared to the U-fueled cores, which is detrimental to core compactness and increases reprocessing and manufacturing requirements. The Th cores also exhibit higher reactivity swings through each cycle, which penalizes reactivity control and increases the number of control rods required. On the other hand, using Th leads to drastic reductions in void and coolant expansion coefficients of reactivity, with the potential for enhancing inherent core safety. Among the U-fueled ARR cores, metallic and nitride fuels result in higher breeding ratios due to their higher heavy metal densities. On the other hand, oxide fuels provide a softer spectrum, which increases the Doppler effect and reduces the positive sodium void worth. A lower fuel temperature is obtained with the metallic and nitride fuels due to their higher thermal conductivities and compatibility with sodium bonds. This is especially beneficial from an inherent safety point of view since it facilitates the reactor cool-down during loss of power removal transients. The advantages in terms of inherent safety of nitride and metallic fuels are maintained when using Th fuel. However, there is a lower relative increase in heavy metal density and in breeding ratio going from oxide to metallic or nitride Th fuels relative to the U counterpart fuels. (authors)

  17. Modeling analysis of core-shell Si/SiGe nanowires

    E-Print Network [OSTI]

    Tang, Ming Y., 1979-

    2004-01-01T23:59:59.000Z

    (cont.) a composition that results in a high mobility has a very promising thermoelectric performance. Lastly, the thermoelectric-related transport properties for a Si/SiGe core-shell nanowire are compared with the related ...

  18. Development of optimized core design and analysis methods for high power density BWRs

    E-Print Network [OSTI]

    Shirvan, Koroush

    2013-01-01T23:59:59.000Z

    Increasing the economic competitiveness of nuclear energy is vital to its future. Improving the economics of BWRs is the main goal of this work, focusing on designing cores with higher power density, to reduce the BWR ...

  19. A statistical analysis of avalanching heat transport in stationary enhanced core confinement regimes

    SciTech Connect (OSTI)

    Tokunaga, S.; Jhang, Hogun; Kim, S. S. [WCI Center for Fusion Theory, National Fusion Research Institute, 52, Yeoeun-dong, Yusung-Gu, Daejon (Korea, Republic of); Diamond, P. H. [WCI Center for Fusion Theory, National Fusion Research Institute, 52, Yeoeun-dong, Yusung-Gu, Daejon (Korea, Republic of); Center for Astrophysics and Space Sciences and Department of Physics, University of California San Diego, La Jolla, California 92093-0429 (United States)

    2012-09-15T23:59:59.000Z

    We present a statistical analysis of heat transport in stationary enhanced confinement regimes obtained from flux-driven gyrofluid simulations. The probability density functions of heat flux in improved confinement regimes, characterized by the Nusselt number, show significant deviation from Gaussian, with a markedly fat tail, implying the existence of heat avalanches. Two types of avalanching transport are found to be relevant to stationary states, depending on the degree of turbulence suppression. In the weakly suppressed regime, heat avalanches occur in the form of quasi-periodic (QP) heat pulses. Collisional relaxation of zonal flow is likely to be the origin of these QP heat pulses. This phenomenon is similar to transient limit cycle oscillations observed prior to edge pedestal formation in recent experiments. On the other hand, a spectral analysis of heat flux in the strongly suppressed regime shows the emergence of a 1/f (f is the frequency) band, suggesting the presence of self-organized criticality (SOC)-like episodic heat avalanches. This episodic 1/f heat avalanches have a long temporal correlation and constitute the dominant transport process in this regime.

  20. WIMS/PANTHER analysis of UO{sub 2}/MOX cores using embedded super-cells

    SciTech Connect (OSTI)

    Knight, M.; Bryce, P. [EDF Energy, Barnett Way, Barnwood, Gloucester (United Kingdom); Hall, S. [Advanced Modelling and Computation Group, Imperial College, London (United Kingdom)

    2012-07-01T23:59:59.000Z

    This paper describes a method of analysing PWR UO{sub 2}MOX cores with WIMS/PANTHER. Embedded super-cells, run within the reactor code, are used to correct the standard methodology of using 2-group smeared data from single assembly lattice calculations. In many other codes the weakness of this standard approach has been improved for MOX by imposing a more realistic environment in the lattice code, or by improving the sophistication of the reactor code. In this approach an intermediate set of calculations is introduced, leaving both lattice and reactor calculations broadly unchanged. The essence of the approach is that the whole core is broken down into a set of 'embedded' super-cells, each extending over just four quarter assemblies, with zero leakage imposed at the assembly mid-lines. Each supercell is solved twice, first with a detailed multi-group pin-by-pin solution, and then with the standard single assembly approach. Correction factors are defined by comparing the two solutions, and these can be applied in whole core calculations. The restriction that all such calculations are modelled with zero leakage means that they are independent of each other and of the core-wide flux shape. This allows parallel pre-calculation for the entire cycle once the loading pattern has been determined, in much the same way that single assembly lattice calculations can be pre-calculated once the range of fuel types is known. Comparisons against a whole core pin-by-pin reference demonstrates that the embedding process does not introduce a significant error, even after burnup and refuelling. Comparisons against a WIMS reference demonstrate that a pin-by-pin multi-group diffusion solution is capable of capturing the main interface effects. This therefore defines a practical approach for achieving results close to lattice code accuracy, but broadly at the cost of a standard reactor calculation. (authors)

  1. MATADOR: a computer code for the analysis of radionuclide behavior during degraded core accidents in light water reactors

    SciTech Connect (OSTI)

    Baybutt, P.; Raghuram, S.; Avci, H.I.

    1985-04-01T23:59:59.000Z

    A new computer code called MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) has been developed to replace the CORRAL computer code which was written for the Reactor Safety Study (WASH-1400). This report contains a detailed description of the models used in MATADOR. MATADOR is intended for use in system risk studies to analyze radionuclide transport and deposition in reactor containments. The principal output of the code is information on the timing and magnitude of radionuclide releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containment and their removal by natural deposition and the operation of engineered safety systems such as sprays. The code requires input data on the source term from the primary system, the geometry of the containment, and the thermal-hydraulic conditions in the containment.

  2. Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling

    E-Print Network [OSTI]

    Kneafsey, Timothy J.

    2010-01-01T23:59:59.000Z

    Mount Elbert Well) during drilling and coring operationsWell in February 2007. Coring was performed while using a custom oil-based drillingWell, pressure coring was not used, thus the core was depressurized upon ascent. Drilling

  3. Analysis of MSE Cores Tuba City, Arizona, Site | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO Overview OCHCOSystemsProgram OverviewAdvocate -Amir Roth About UsLaboratoryMSE Cores Tuba

  4. Core Analysis At Fish Lake Valley Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew| ExplorationCooperstown,Terrace,Lakes,transfer1983)Core

  5. Core Analysis At Mcgee Mountain Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump| Open EnergyOpenEnergy2003)Core

  6. Benchmark analysis of high temperature engineering test reactor core using McCARD code

    SciTech Connect (OSTI)

    Jeong, Chang Joon; Jo, Chang Keun; Lee, Hyun Chul; Noh, Jae Man [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong, Daejeon, 305-353 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

    A benchmark calculation has been performed for a startup core physics test of Japan's High Temperature Engineering Test Reactor (HTTR). The calculation is carried out by the McCARD code, which adopts the Monte Carlo method. The cross section library is ENDF-B/VII.0. The fuel cell is modeled by the reactivity-equivalent physical transform (RPT) method. Effective multiplication factors with different numbers of fuel columns have been analyzed. The calculation shows that the HTTR becomes critical with 19 fuel columns with an excess reactivity of 0.84% ?k/k. The discrepancies between the measurements and Monte Carlo calculations are 2.2 and 1.4 % ?k/k for 24 and 30 columns, respectively. The reasons for the discrepancy are thought to be the current version of cross section library and the impurity in the graphite which is represented by the boron concentration. In the future, the depletion results will be proposed for further benchmark calculations. (authors)

  7. SIMMER-II: A computer program for LMFBR disrupted core analysis

    SciTech Connect (OSTI)

    Bohl, W.R.; Luck, L.B.

    1990-06-01T23:59:59.000Z

    SIMMER-2 (Version 12) is a computer program to predict the coupled neutronic and fluid-dynamics behavior of liquid-metal fast reactors during core-disruptive accident transients. The modeling philosophy is based on the use of general, but approximate, physics to represent interactions of accident phenomena and regimes rather than a detailed representation of specialized situations. Reactor neutronic behavior is predicted by solving space (r,z), energy, and time-dependent neutron conservation equations (discrete ordinates transport or diffusion). The neutronics and the fluid dynamics are coupled via temperature- and background-dependent cross sections and the reactor power distribution. The fluid-dynamics calculation solves multicomponent, multiphase, multifield equations for mass, momentum, and energy conservation in (r,z) or (x,y) geometry. A structure field with nine density and five energy components; a liquid field with eight density and six energy components; and a vapor field with six density and on energy component are coupled by exchange functions representing a modified-dispersed flow regime with a zero-dimensional intra-cell structure model.

  8. Analysis of Advanced Fuel Assemblies and Core Designs for the Current and Next Generations of LWRs

    SciTech Connect (OSTI)

    Ragusa, Jean; Vierow, Karen

    2011-09-01T23:59:59.000Z

    The objective of the project is to design and analyze advanced fuel assemblies for use in current and future light water reactors and to assess their ability to reduce the inventory of transuranic elements, while preserving operational safety. The reprocessing of spent nuclear fuel can delay or avoid the need for a second geological repository in the US. Current light water reactor fuel assembly designs under investigation could reduce the plutonium inventory of reprocessed fuel. Nevertheless, these designs are not effective in stabilizing or reducing the inventory of minor actinides. In the course of this project, we developed and analyzed advanced fuel assembly designs with improved thermal transmutation capability regarding transuranic elements and especially minor actinides. These designs will be intended for use in thermal spectrum (e.g., current and future fleet of light water reactors in the US). We investigated various fuel types, namely high burn-up advanced mixed oxides and inert matrix fuels, in various geometrical designs that are compliant with the core internals of current and future light water reactors. Neutronic/thermal hydraulic effects were included. Transmutation efficiency and safety parameters were used to rank and down-select the various designs.

  9. Paleo-Climate and Glaciological Reconstruction in Central Asia through the Collection and Analysis of Ice Cores and Instrumental Data from the Tien Shan

    SciTech Connect (OSTI)

    Vladimir Aizen; Donald Bren; Karl Kreutz; Cameron Wake

    2001-05-30T23:59:59.000Z

    While the majority of ice core investigations have been undertaken in the polar regions, a few ice cores recovered from carefully selected high altitude/mid-to-low latitude glaciers have also provided valuable records of climate variability in these regions. A regional array of high resolution, multi-parameter ice core records developed from temperate and tropical regions of the globe can be used to document regional climate and environmental change in the latitudes which are home to the vase majority of the Earth's human population. In addition, these records can be directly compared with ice core records available from the polar regions and can therefore expand our understanding of inter-hemispheric dynamics of past climate changes. The main objectives of our paleoclimate research in the Tien Shan mountains of middle Asia combine the development of detailed paleoenvironmental records via the physical and chemical analysis of ice cores with the analysis of modern meteorological and hydrological data. The first step in this research was the collection of ice cores from the accumulation zone of the Inylchek Glacier and the collection of meteorological data from a variety of stations throughout the Tien Shan. The research effort described in this report was part of a collaborative effort with the United State Geological Survey's (USGS) Global Environmental Research Program which began studying radionuclide deposition in mid-latitude glaciers in 1995.

  10. High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor With Results from FY-2011 Activities

    SciTech Connect (OSTI)

    Michael A. Pope

    2011-10-01T23:59:59.000Z

    The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450MWth DB-HTRs. The TRISO fuel microanalysis covers the gas pressure buildup in a coated fuel particle including helium production, the thermo-mechanical behavior of a CFP, the failure probabilities of CFPs, the temperature distribution in a CPF, and the fission product (FP) transport in a CFP and a graphite. In Chapter VIII, it contains the core design and analysis of sodium cooled fast reactor (SFR) with deep burn HTR reactor. It considers a synergistic combination of the DB-MHR and an SFR burner for a safe and efficient transmutation of the TRUs from LWRs. Chapter IX describes the design and analysis results of the self-cleaning (or self-recycling) HTR core. The analysis is considered zero and 5-year cooling time of the spent LWR fuels.

  11. Postgraduate Studies Business Analysis & Consulting

    E-Print Network [OSTI]

    Strathclyde, University of

    and Business Analysis 7 Core Unit 2: MS922 Quantitative Business Analysis 8 Core Unit 3: MS923 Managing: MS929 Performance Measurement and Management 11 Optional Unit 3: MS927 Risk Analysis and Management1 Postgraduate Studies Business Analysis & Consulting STUDENT HANDBOOK 2014-15 The information

  12. Formation and Collapse of Nonaxisymmetric Protostellar Cores in Planar Magnetic Interstellar Clouds: Formulation of the Problem and Linear Analysis

    E-Print Network [OSTI]

    Glenn E. Ciolek; Shantanu Basu

    2006-07-27T23:59:59.000Z

    We formulate the problem of the formation and collapse of nonaxisymmetric protostellar cores in weakly ionized, self-gravitating, magnetic molecular clouds. In our formulation, molecular clouds are approximated as isothermal, thin (but with finite thickness) sheets. We present the governing dynamical equations for the multifluid system of neutral gas and ions, including ambipolar diffusion, and also a self-consistent treatment of thermal pressure, gravitational, and magnetic (pressure and tension) forces. The dimensionless free parameters characterizing model clouds are discussed. The response of cloud models to linear perturbations is also examined, with particular emphasis on length and time scales for the growth of gravitational instability in magnetically subcritical and supercritical clouds. We investigate their dependence on a cloud's initial mass-to-magnetic-flux ratio (normalized to the critical value for collapse), the dimensionless initial neutral-ion collision time, and also the relative external pressure exerted on a model cloud. Among our results, we find that nearly-critical model clouds have significantly larger characteristic instability lengthscales than do more distinctly sub- or supercritical models. Another result is that the effect of a greater external pressure is to reduce the critical lengthscale for instability. Numerical simulations showing the evolution of model clouds during the linear regime of evolution are also presented, and compared to the results of the dispersion analysis. They are found to be in agreement with the dispersion results, and confirm the dependence of the characteristic length and time scales on parameters such as the initial mass-to-flux ratio and relative external pressure.

  13. The JCMT Gould Belt Survey: First results from the SCUBA-2 observations of the Ophiuchus molecular cloud and a virial analysis of its prestellar core population

    E-Print Network [OSTI]

    Pattle, K; Kirk, J M; White, G J; Drabek-Maunder, E; Buckle, J; Beaulieu, S F; Berry, D S; Broekhoven-Fiene, H; Currie, M J; Fich, M; Hatchell, J; Kirk, H; Jenness, T; Johnstone, D; Mottram, J C; Nutter, D; Pineda, J E; Quinn, C; Salji, C; Tisi, S; Walker-Smith, S; Di Francesco, J; Hogerheijde, M R; André, Ph; Bastien, P; Bresnahan, D; Butner, H; Chen, M; Chrysostomou, A; Coude, S; Davis, C J; Duarte-Cabral, A; Fiege, J; Friberg, P; Friesen, R; Fuller, G A; Graves, S; Greaves, J; Gregson, J; Griffin, M J; Holland, W; Joncas, G; Knee, L B G; Könyves, V; Mairs, S; Marsh, K; Matthews, B C; Moriarty-Schieven, G; Rawlings, J; Richer, J; Robertson, D; Rosolowsky, E; Rumble, D; Sadavoy, S; Spinoglio, L; Thomas, H; Tothill, N; Viti, S; Wouterloot, J; Yates, J; Zhu, M

    2015-01-01T23:59:59.000Z

    In this paper we present the first observations of the Ophiuchus molecular cloud performed as part of the James Clerk Maxwell Telescope (JCMT) Gould Belt Survey (GBS) with the SCUBA-2 instrument. We demonstrate methods for combining these data with previous HARP CO, Herschel, and IRAM N$_{2}$H$^{+}$ observations in order to accurately quantify the properties of the SCUBA-2 sources in Ophiuchus. We produce a catalogue of all of the sources found by SCUBA-2. We separate these into protostars and starless cores. We list all of the starless cores and perform a full virial analysis, including external pressure. This is the first time that external pressure has been included in this level of detail. We find that the majority of our cores are either bound or virialised. Gravitational energy and external pressure are on average of a similar order of magnitude, but with some variation from region to region. We find that cores in the Oph A region are gravitationally bound prestellar cores, while cores in the Oph C and ...

  14. Direct chemical analysis of frozen ice cores by UV-laser ablation ICPMS Wolfgang Muller,*a

    E-Print Network [OSTI]

    Royal Holloway, University of London

    mm long ice (b, c); its `tongue-like' extension through the cell door has a Peltier element clamped DOI: 10.1039/c1ja10242g Cryo-cell UV-LA-ICPMS is a new technique for direct chemical analysis analysis at cell UV-LA-ICPMS setup used

  15. Please cite this article in press as: Shuffler, C., et al., Thermal hydraulic analysis for grid supported pressurized water reactor cores. Nucl. Eng. Des. (2009), doi:10.1016/j.nucengdes.2008.12.028

    E-Print Network [OSTI]

    Malen, Jonathan A.

    2009-01-01T23:59:59.000Z

    Please cite this article in press as: Shuffler, C., et al., Thermal hydraulic analysis for grid.elsevier.com/locate/nucengdes Thermal hydraulic analysis for grid supported pressurized water reactor cores C. Shuffler , J. Trant, J online xxx a b s t r a c t This paper presents the methodology and results for thermal hydraulic analysis

  16. Prognostic Importance of Gleason 7 Disease Among Patients Treated With External Beam Radiation Therapy for Prostate Cancer: Results of a Detailed Biopsy Core Analysis

    SciTech Connect (OSTI)

    Spratt, Daniel E.; Zumsteg, Zach; Ghadjar, Pirus; Pangasa, Misha; Pei, Xin [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)] [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States); Fine, Samson W. [Department of Pathology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)] [Department of Pathology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States); Yamada, Yoshiya; Kollmeier, Marisa [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)] [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States); Zelefsky, Michael J., E-mail: zelefskm@mskcc.org [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)

    2013-04-01T23:59:59.000Z

    Purpose: To analyze the effect of primary Gleason (pG) grade among a large cohort of Gleason 7 prostate cancer patients treated with external beam radiation therapy (EBRT). Methods and Materials: From May 1989 to January 2011, 1190 Gleason 7 patients with localized prostate cancer were treated with EBRT at a single institution. Of these patients, 613 had a Gleason 7 with a minimum of a sextant biopsy with nonfragmented cores and full biopsy core details available, including number of cores of cancer involved, percentage individual core involvement, location of disease, bilaterality, and presence of perineural invasion. Median follow-up was 6 years (range, 1-16 years). The prognostic implication for the following outcomes was analyzed: biochemical recurrence-free survival (bRFS), distant metastasis-free survival (DMFS), and prostate cancer-specific mortality (PCSM). Results: The 8-year bRFS rate for pG3 versus pG4 was 77.6% versus 61.3% (P<.0001), DMFS was 96.8% versus 84.3% (P<.0001), and PCSM was 3.7% versus 8.1% (P=.002). On multivariate analysis, pG4 predicted for significantly worse outcome in all parameters. Location of disease (apex, base, mid-gland), perineural involvement, maximum individual core involvement, and the number of Gleason 3+3, 3+4, or 4+3 cores did not predict for distant metastases. Conclusions: Primary Gleason grade 4 independently predicts for worse bRFS, DMFS, and PCSM among Gleason 7 patients. Using complete core information can allow clinicians to utilize pG grade as a prognostic factor, despite not having the full pathologic details from a prostatectomy specimen. Future staging and risk grouping should investigate the incorporation of primary Gleason grade when complete biopsy core information is used.

  17. Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion

    E-Print Network [OSTI]

    Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology

    2008-01-01T23:59:59.000Z

    The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density monolithic UMo fuel. The design of an optimum LEU core for the ...

  18. Behavior of an heterogeneous annular FBR core during an unprotected loss of flow accident: Analysis of the primary phase with SAS-SFR

    SciTech Connect (OSTI)

    Massara, S.; Schmitt, D.; Bretault, A.; Lemasson, D.; Darmet, G.; Verwaerde, D. [EDF R and D, 1, Avenue du General de Gaulle, 92141 Clamart (France); Struwe, D.; Pfrang, W.; Ponomarev, A. [Karlsruher Institut fuer Technologie KIT, Institut fuer Neutronenphysik und Reaktortechnik INR, Hermann-von-Helmholtz-Platz 1, Gebaude 521, 76344 Eggenstein-Leopoldshafen (Germany)

    2012-07-01T23:59:59.000Z

    In the framework of a substantial improvement on FBR core safety connected to the development of a new Gen IV reactor type, heterogeneous core with innovative features are being carefully analyzed in France since 2009. At EDF R and D, the main goal is to understand whether a strong reduction of the Na-void worth - possibly attempting a negative value - allows a significant improvement of the core behavior during an unprotected loss of flow accident. Also, the physical behavior of such a core is of interest, before and beyond the (possible) onset of Na boiling. Hence, a cutting-edge heterogeneous design, featuring an annular shape, a Na-plena with a B{sub 4}C plate and a stepwise modulation of fissile core heights, was developed at EDF by means of the SDDS methodology, with a total Na-void worth of -1 $. The behavior of such a core during the primary phase of a severe accident, initiated by an unprotected loss of flow, is analyzed by means of the SAS-SFR code. This study is carried-out at KIT and EDF, in the framework of a scientific collaboration on innovative FBR severe accident analyses. The results show that the reduction of the Na-void worth is very effective, but is not sufficient alone to avoid Na-boiling and, hence, to prevent the core from entering into the primary phase of a severe accident. Nevertheless, the grace time up to boiling onset is greatly enhanced in comparison to a more traditional homogeneous core design, and only an extremely low fraction of the fuel (<0.1%) enters into melting at the end of this phase. A sensitivity analysis shows that, due to the inherent neutronic characteristics of such a core, the gagging scheme plays a major role on the core behavior: indeed, an improved 4-zones gagging scheme, associated with an enhanced control rod drive line expansion feed-back effect, finally prevents the core from entering into sodium boiling. This major conclusion highlights both the progress already accomplished and the need for more detailed future analyses, particularly concerning: the neutronic burn-up scheme, the modeling of the diagrid effect and the control rod drive line expansion feed-backs, as well as the primary/secondary systems thermal-hydraulics behavior. (authors)

  19. TITAN : an advanced three dimensional coupled neutronicthermal-hydraulics code for light water nuclear reactor core analysis

    E-Print Network [OSTI]

    Griggs, D. P.

    1984-01-01T23:59:59.000Z

    The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hydraulics and feedback be included. A number of coupled neutronics/thermal-hydraulics codes have been developed for this ...

  20. An investigation of the correlation of core analysis data with original core saturations in the Kelly-Snyder Field, Scurry County, Texas

    E-Print Network [OSTI]

    Van Meter, Orville Everett, Jr

    1952-01-01T23:59:59.000Z

    " . . . . . . . ? . *. . . . ~ . . ~ 1$ III, Summary of Mud Propertiee ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ t ~ ~ ~ 4 ~ t ~ ~ Io 16 XV. Sample Permeability Caloulationsi ~ . . . ~ . ~ ~ ~ ~ ~ i ~ ~ i ~ 26 V. Basic Data on Canyon Reef Cores'. ~ . ". i ~ . ~ . i. . i. . 27 VI & Summary of Oi 1... kpparatus?~~ Capillary Pressure Curves on Carxyon Reef Cores Nos 1 end No ~ 2 ~ ~ ~ o ~ ~ ~ ~ ~ t o 1 e ~ ~ ~ ~ ~ ~ i ~ ~ ~ i ~ ~ ~ ~ ~ 11 4 ~ 17 i ~ 1$ ~ ~ 22 5. 10+ Sohematio Drawing of Cell Connected for Permeability Neasurementsoo...

  1. CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor

    E-Print Network [OSTI]

    Wang, Huhu 1985-

    2012-12-13T23:59:59.000Z

    if the large portion of the coolant flows into bypass gaps instead of coolant channels in which the cooling efficiency is much higher. A preliminary three dimensional steady-state CFD analysis was performed with commercial code STARCCM+ 6.04 to investigate...

  2. Development code for sensitivity and uncertainty analysis of input on the MCNPX for neutronic calculation in PWR core

    SciTech Connect (OSTI)

    Hartini, Entin, E-mail: entin@batan.go.id; Andiwijayakusuma, Dinan, E-mail: entin@batan.go.id [Center for Development of Nuclear Informatics - National Nuclear Energy Agency, PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia)

    2014-09-30T23:59:59.000Z

    This research was carried out on the development of code for uncertainty analysis is based on a statistical approach for assessing the uncertainty input parameters. In the butn-up calculation of fuel, uncertainty analysis performed for input parameters fuel density, coolant density and fuel temperature. This calculation is performed during irradiation using Monte Carlo N-Particle Transport. The Uncertainty method based on the probabilities density function. Development code is made in python script to do coupling with MCNPX for criticality and burn-up calculations. Simulation is done by modeling the geometry of PWR terrace, with MCNPX on the power 54 MW with fuel type UO2 pellets. The calculation is done by using the data library continuous energy cross-sections ENDF / B-VI. MCNPX requires nuclear data in ACE format. Development of interfaces for obtaining nuclear data in the form of ACE format of ENDF through special process NJOY calculation to temperature changes in a certain range.

  3. Modeling and analysis framework for core damage propagation during flow-blockage-initiated accidents in the Advanced Neutron Source Reactor at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

    1995-09-01T23:59:59.000Z

    This paper describes modeling and analysis to evaluate the extent of core damage during flow blockage events in the Advanced Neutron Source (ANS) reactor planned to be built at the Oak Ridge National Laboratory (ORNL). Damage propagation is postulated to occur from thermal conduction between damaged and undamaged plates due to direct thermal contact. Such direct thermal contact may occur because of fuel plate swelling during fission product vapor release or plate buckling. Complex phenomena of damage propagation were modeled using a one-dimensional heat transfer model. A scoping study was conducted to learn what parameters are important for core damage propagation, and to obtain initial estimates of core melt mass for addressing recriticality and steam explosion events. The study included investigating the effects of the plate contact area, the convective heat transfer coefficient, thermal conductivity upon fuel swelling, and the initial temperature of the plate being contacted by the damaged plate. Also, the side support plates were modeled to account for their effects on damage propagation. The results provide useful insights into how various uncertain parameters affect damage propagation.

  4. CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor 

    E-Print Network [OSTI]

    Wang, Huhu 1985-

    2012-12-13T23:59:59.000Z

    Very High Temperature Rector (VHTR) had been designated as one of those promising reactors for the Next Generation (IV) Nuclear Plant (NGNP). For a prismatic core VHTR, one of the most crucial design considerations is the bypass flow and crossflow...

  5. Independent analysis of selected core-concrete interaction and fission product release experiments with CORCON-MOD2 and VANESA

    SciTech Connect (OSTI)

    Greene, G.A.; Sanborn, Y.

    1986-01-01T23:59:59.000Z

    The discrepancies between experimental findings and the Reactor Safety Study predictions, as well as the rapidly developing data base enabling phenomenological modeling of core-concrete interactions and ex-vessel fission product release, have prompted the development of several new computer models of core-concrete interactions and fission product release during severe accidents. Two such models are the CORCON-MOD2 model of core-concrete interactions and the VANESA model of ex-vessel aerosol and fission product release during core-concrete interactions. The final judge on the adequacy of the development of models of core debris-concrete interactions is, of course, comparison of the model predictions with the results of experiments. The research into ex-vessel core debris behavior differs from research into many aspects of reactor accidents in that there are many experimental results for comparison. Comparisons of code predictions with results of tests using realistic temperatures and conditions should provide an indication of the progress that has been made and, with appropriately chosen tests, an indication of work that needs to be done. 9 refs., 6 figs., 5 tabs.

  6. Hydrogen Analysis

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

    A H2A: Hydrogen Analysis Margaret K. Mann DOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29, 2004 Washington, D.C. H2A Charter...

  7. CORCON-MOD3: An integrated computer model for analysis of molten core-concrete interactions. User`s manual

    SciTech Connect (OSTI)

    Bradley, D.R.; Gardner, D.R.; Brockmann, J.E.; Griffith, R.O. [Sandia National Labs., Albuquerque, NM (United States)

    1993-10-01T23:59:59.000Z

    The CORCON-Mod3 computer code was developed to mechanistically model the important core-concrete interaction phenomena, including those phenomena relevant to the assessment of containment failure and radionuclide release. The code can be applied to a wide range of severe accident scenarios and reactor plants. The code represents the current state of the art for simulating core debris interactions with concrete. This document comprises the user`s manual and gives a brief description of the models and the assumptions and limitations in the code. Also discussed are the input parameters and the code output. Two sample problems are also given.

  8. Results of transient /accident analysis for the HEU, first mixed HEU-LEU and for the first full LEU cores of the WWR-SM reactor at INP AS RUZ

    SciTech Connect (OSTI)

    Baytelesov, S.A.; Dosimbaev, A.A.; Kungurov, F.R.; Salikhbaev, U.S. [Institute of Nuclear Physics, Ulugbek, 100214 Tashkent (Uzbekistan)

    2008-07-15T23:59:59.000Z

    The WWR-SM reactor in Uzbekistan is preparing for the conversion from HEU (36%) fuel to LEU (19.8%) fuel. During this conversion, the HEU fuel assemblies (IRT-3M FA) being discharged at the end of each cycle will be replaced by LEU fuel assemblies (IRT-4M FA); this gradual conversion requires 9 cycles. The safety analysis report for this conversion process has been prepared. This paper presents selected results for postulated transient/accidents during this conversion process; results for transient analysis for the HEU core, the 1st mixed (HEU-LEU) core, and for the first full LEU core are presented for the following initiators: control rod motion (2 cases), loss of power, and FA blockage. These results show that safety is maintained for all transients analyzed and that the behavior of all the analyzed cores is essentially the same. (author)

  9. SAFETY ANALYSIS QUANTITATIVE ANALYSIS ON

    E-Print Network [OSTI]

    Wang, Yinhai

    1 TOPIC C2 SAFETY ANALYSIS AND POLICY QUANTITATIVE ANALYSIS ON ANGLE-ACCIDENT RISK AT SIGNALIZED-2700 Tel: (206) 543-9639 Fax: (206) 543-5965 Email: nihan@u.washington.edu #12;2 Quantitative Analysis on Angle-Accident Risk at Signalized Intersections Abstract: This paper demonstrates how a new modeling

  10. Very High Temperature Reactor (VHTR) Deep Burn Core and Fuel Analysis -- Complete Design Selection for the Pebble Bed Reactor

    SciTech Connect (OSTI)

    B. Boer; A. M. Ougouag

    2010-09-01T23:59:59.000Z

    The Deep-Burn (DB) concept focuses on the destruction of transuranic nuclides from used light water reactor fuel. These transuranic nuclides are incorporated into TRISO coated fuel particles and used in gas-cooled reactors with the aim of a fractional fuel burnup of 60 to 70% in fissions per initial metal atom (FIMA). This high performance is expected through the use of multiple recirculation passes of the fuel in pebble form without any physical or chemical changes between passes. In particular, the concept does not call for reprocessing of the fuel between passes. In principle, the DB pebble bed concept employs the same reactor designs as the presently envisioned low-enriched uranium core designs, such as the 400 MWth Pebble Bed Modular Reactor (PBMR-400). Although it has been shown in the previous Fiscal Year (2009) that a PuO2 fueled pebble bed reactor concept is viable, achieving a high fuel burnup, while remaining within safety-imposed prescribed operational limits for fuel temperature, power peaking and temperature reactivity feedback coefficients for the entire temperature range, is challenging. The presence of the isotopes 239-Pu, 240-Pu and 241-Pu that have resonances in the thermal energy range significantly modifies the neutron thermal energy spectrum as compared to a ”standard,” UO2-fueled core. Therefore, the DB pebble bed core exhibits a relatively hard neutron energy spectrum. However, regions within the pebble bed that are near the graphite reflectors experience a locally softer spectrum. This can lead to power and temperature peaking in these regions. Furthermore, a shift of the thermal energy spectrum with increasing temperature can lead to increased absorption in the resonances of the fissile Pu isotopes. This can lead to a positive temperature reactivity coefficient for the graphite moderator under certain operating conditions. The effort of this task in FY 2010 has focused on the optimization of the core to maximize the pebble discharge burnup level, while retaining its inherent safety characteristics. Using generic pebble bed reactor cores, this task will perform physics calculations to evaluate the capabilities of the pebble bed reactor to perform utilization and destruction of LWR used-fuel transuranics. The task will use established benchmarked models, and will introduce modeling advancements appropriate to the nature of the fuel considered (high TRU content and high burn-up).

  11. Environmental Analysis & Policy: Sample Pathway

    E-Print Network [OSTI]

    Goldberg, Bennett

    Environmental Analysis & Policy: Sample Pathway Semester I Semester II Freshman Year CGS Core CGS Sustainable Development OR Spring GE 425 U.S. Environmental Policy (Senior) GE 309 Intermediate Env Analysis (Fall) EAP Elective Summer Environmental Internship Senior Year GE 420 Env Policy Analysis 4 th Semester

  12. Characterization of core debris/concrete interactions for the Advanced Neutron Source. ANS Severe Accident Analysis Program

    SciTech Connect (OSTI)

    Hyman, C.R.; Taleyarkhan, R.P.

    1992-02-01T23:59:59.000Z

    This report provides the results of a recent study conducted to explore the molten core/concrete interaction (MCCI) issue for the Advanced Neutron Source (ANS). The need for such a study arises from the potential threats to reactor system integrity posed by MCCI. These threats include direct attack of the concrete basemat of the containment; generation and release of large quantities of gas that can pressurize the containment; the combustion threat of these gases; and the potential generation, release, and transport of radioactive aerosols to the environment.

  13. Core - Corona Model analysis of the Low Energy Beam Scan at RHIC (Relativistic Heavy Ion Collider) in Brookhaven (USA)

    E-Print Network [OSTI]

    M. Gemard; J. Aichelin

    2014-02-02T23:59:59.000Z

    The centrality dependence of spectra of identified particles in collisions between ultrarelativistic heavy ions with a center of mass energy ($\\sqrt{s}$) of 39 and 11.5 $AGeV$ is analyzed in the core - corona model. We show that at these energies the spectra can be well understood assuming that they are composed of two components whose relative fraction depends on the centrality of the interaction: The core component which describes an equilibrated quark gluon plasma and the corona component which is caused by nucleons close to the surface of the interaction zone which scatter only once and which is identical to that observed in proton-proton collisions. The success of this approach at 39 and 11.5 $AGeV$ shows that the physics does not change between this energy and $\\sqrt{s}=200~ AGeV$ for which this model has been developed (Aichelin 2008). This presents circumstantial evidence that a quark gluon plasma is also created at center of mass energies as low as 11.5 $AGeV$.

  14. Image Analysis

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

    Recognition Image Analysis and Recognition Snapshot1498121slicesqResedison Fibers permeating imaged material (Courtesy: Bale, Loring, Perciano and Ushizima) Imagery coming from...

  15. OIL ANALYSIS LAB TRIVECTOR ANALYSIS

    E-Print Network [OSTI]

    OIL ANALYSIS LAB TRIVECTOR ANALYSIS This test method is a good routine test for the overall condition of the oil, the cleanliness, and can indicate the presence of wear metals that could be coming of magnetic metal particles within the oil. This may represent metals being worn from components (i

  16. Financial Analysis

    Broader source: Energy.gov [DOE]

    The first step in financing a street lighting retrofit is a detailed financial analysis. Because street lighting systems are designed to last ten or twenty years, or even longer, all aspects of first costs, ongoing expenses, and long-term savings are important. While a preliminary or first-level analysis can be used to determine such things as simple payback, rate of return, and cost of light, the results may neglect a number of important economic considerations, such as the time value of money, additional savings and expenses and their relative timing, and future energy price escalations. Hence a first-level analysis does not typically provide the end user with sufficient details to make a fully informed decision. For this reason, the Illuminating Engineering Society (IES) recommends a full life cycle cost/benefit analysis (LCCBA).

  17. Multi-core Performance Analysis

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighandSWPA / SPRA /Ml'.SolarUS Dept ofActing Chiefof InksScaling on

  18. Multi-core Performance Analysis

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighandSWPA / SPRA /Ml'.SolarUS Dept ofActing Chiefof InksScaling oncore

  19. Multi-core Performance Analysis

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighandSWPA / SPRA /Ml'.SolarUS Dept ofActing Chiefof InksScaling

  20. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal floods during mid-loop operations. Volume 4

    SciTech Connect (OSTI)

    Kohut, P. [Brookhaven National Lab., Upton, NY (United States)

    1994-07-01T23:59:59.000Z

    The major objective of the Surry internal flood analysis was to provide an improved understanding of the core damage scenarios arising from internal flood-related events. The mean core damage frequency of the Surry plant due to internal flood events during mid-loop operations is 4.8E-06 per year, and the 5th and 95th percentiles are 2.2E-07 and 1.8E-05 per year, respectively. Some limited sensitivity calculations were performed on three plant improvement options. The most significant result involves modifications of intake-level structure on the canal, which reduced core damage frequency contribution from floods in mid-loop by about 75%.

  1. Economic analysis

    SciTech Connect (OSTI)

    None

    1980-06-01T23:59:59.000Z

    The Energy Policy and Conservation Act (EPCA) mandated that minimum energy efficiency standards be established for classes of refrigerators and refrigerator-freezers, freezers, clothes dryers, water heaters, room air conditioners, home heating equipment, kitchen ranges and ovens, central air conditioners, and furnaces. EPCA requires that standards be designed to achieve the maximum improvement in energy efficiency that is technologically feasible and economically justified. Following the introductory chapter, Chapter Two describes the methodology used in the economic analysis and its relationship to legislative criteria for consumer product efficiency assessment; details how the CPES Value Model systematically compared and evaluated the economic impacts of regulation on the consumer, manufacturer and Nation. Chapter Three briefly displays the results of the analysis and lists the proposed performance standards by product class. Chapter Four describes the reasons for developing a baseline forecast, characterizes the baseline scenario from which regulatory impacts were calculated and summarizes the primary models, data sources and assumptions used in the baseline formulations. Chapter Five summarizes the methodology used to calculate regulatory impacts; describes the impacts of energy performance standards relative to the baseline discussed in Chapter Four. Also discussed are regional standards and other program alternatives to performance standards. Chapter Six describes the procedure for balancing consumer, manufacturer, and national impacts to select standard levels. Details of models and data bases used in the analysis are included in Appendices A through K.

  2. Economic Analysis of Policy Effects Analysis Platform

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

    Economic Analysis of Policy Effects Analysis Platform March 24, 2015 Jason Hansen, PhD Idaho National Laboratory This presentation does not contain any proprietary, confidential,...

  3. Data Analysis

    SciTech Connect (OSTI)

    Powell, Danny H [ORNL] [ORNL; Elwood Jr, Robert H [ORNL] [ORNL

    2011-01-01T23:59:59.000Z

    Analysis of the material protection, control, and accountability (MPC&A) system is necessary to understand the limits and vulnerabilities of the system to internal threats. A self-appraisal helps the facility be prepared to respond to internal threats and reduce the risk of theft or diversion of nuclear material. The material control and accountability (MC&A) system effectiveness tool (MSET) fault tree was developed to depict the failure of the MPC&A system as a result of poor practices and random failures in the MC&A system. It can also be employed as a basis for assessing deliberate threats against a facility. MSET uses fault tree analysis, which is a top-down approach to examining system failure. The analysis starts with identifying a potential undesirable event called a 'top event' and then determining the ways it can occur (e.g., 'Fail To Maintain Nuclear Materials Under The Purview Of The MC&A System'). The analysis proceeds by determining how the top event can be caused by individual or combined lower level faults or failures. These faults, which are the causes of the top event, are 'connected' through logic gates. The MSET model uses AND-gates and OR-gates and propagates the effect of event failure using Boolean algebra. To enable the fault tree analysis calculations, the basic events in the fault tree are populated with probability risk values derived by conversion of questionnaire data to numeric values. The basic events are treated as independent variables. This assumption affects the Boolean algebraic calculations used to calculate results. All the necessary calculations are built into the fault tree codes, but it is often useful to estimate the probabilities manually as a check on code functioning. The probability of failure of a given basic event is the probability that the basic event primary question fails to meet the performance metric for that question. The failure probability is related to how well the facility performs the task identified in that basic event over time (not just one performance or exercise). Fault tree calculations provide a failure probability for the top event in the fault tree. The basic fault tree calculations establish a baseline relative risk value for the system. This probability depicts relative risk, not absolute risk. Subsequent calculations are made to evaluate the change in relative risk that would occur if system performance is improved or degraded. During the development effort of MSET, the fault tree analysis program used was SAPHIRE. SAPHIRE is an acronym for 'Systems Analysis Programs for Hands-on Integrated Reliability Evaluations.' Version 1 of the SAPHIRE code was sponsored by the Nuclear Regulatory Commission in 1987 as an innovative way to draw, edit, and analyze graphical fault trees primarily for safe operation of nuclear power reactors. When the fault tree calculations are performed, the fault tree analysis program will produce several reports that can be used to analyze the MPC&A system. SAPHIRE produces reports showing risk importance factors for all basic events in the operational MC&A system. The risk importance information is used to examine the potential impacts when performance of certain basic events increases or decreases. The initial results produced by the SAPHIRE program are considered relative risk values. None of the results can be interpreted as absolute risk values since the basic event probability values represent estimates of risk associated with the performance of MPC&A tasks throughout the material balance area (MBA). The RRR for a basic event represents the decrease in total system risk that would result from improvement of that one event to a perfect performance level. Improvement of the basic event with the greatest RRR value produces a greater decrease in total system risk than improvement of any other basic event. Basic events with the greatest potential for system risk reduction are assigned performance improvement values, and new fault tree calculations show the improvement in total system risk. The ope

  4. NREL: Energy Analysis - Market Analysis

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Saleshttp://www.fnal.gov/directorate/nalcal/nalcal02_07_05_files/nalcal.gifNRELPower SystemsDebbieJessicaLiz TorresMarket Analysis

  5. Research Associate Position Defense Analysis Department

    E-Print Network [OSTI]

    in analyzing social network data as well as geospatial, temporal, and standard statistical analysis of largeResearch Associate Position Defense Analysis Department Naval Postgraduate School, Monterey, CA Research Associate The Department of Defense Analysis is home to the CORE (Common Operational Research

  6. Flow instabilities in the core and the coolant circuit of advances low-boiling light water reacto: classification of causes and development of simulator for the future analysis

    E-Print Network [OSTI]

    Rezvyi, Aleksey

    2002-01-01T23:59:59.000Z

    . . 1. 3. Analysis method determination. 2. THEORETICAL ASPECTS OF DIFFERENT TYPES OF THE THERMO-HYDRAULIC INSTABILITIES. . 2. 1. Static instability of loading charactenstic. . . . . . . . . . . . . . . . . . . . . . . 2. 2. Resonance instability... in the 1C L-BWR during heat-up process. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Diagram of components hierarchy of the Thermo-Hydraulic instabilities phenomenon. . The steam generating heating channels instability area, mass flow vs...

  7. Hazard Analysis Database report

    SciTech Connect (OSTI)

    Niemi, B.J.

    1997-08-12T23:59:59.000Z

    This document describes and defines the Hazard Analysis Database for the Tank Waste Remediation System Final Safety Analysis Report.

  8. Hazard analysis results report

    SciTech Connect (OSTI)

    Niemi, B.J., Westinghouse Hanford

    1996-09-30T23:59:59.000Z

    This document describes and defines the Hazard Analysis Results for the Tank Waste Remediation System Final Safety Analysis Report.

  9. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 5: Analysis of core damage frequency from seismic events for plant operational state 5 during a refueling outage

    SciTech Connect (OSTI)

    Budnitz, R.J. [Future Resources Associates, Inc., Berkeley, CA (United States); Davis, P.R. [PRD Consulting (United States); Ravindra, M.K.; Tong, W.H. [EQE International, Inc., Irvine, CA (United States)

    1994-08-01T23:59:59.000Z

    In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Sandia National Laboratories studying a boiling water reactor (Grand Gulf), and the other at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1). Both the Sandia and Brookhaven projects have examined only accidents initiated by internal plant faults---so-called ``internal initiators.`` This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling outage conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Grand Gulf. All of the many systems modeling assumptions, component non-seismic failure rates, and human effort rates that were used in the internal-initiator study at Grand Gulf have been adopted here, so that the results of the study can be as comparable as possible. Both the Sandia study and this study examine only one shutdown plant operating state (POS) at Grand Gulf, namely POS 5 representing cold shutdown during a refueling outage. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POS 5. The results of the analysis are that the core-damage frequency for earthquake-initiated accidents during refueling outages in POS 5 is found to be quite low in absolute terms, less than 10{sup {minus}7}/year.

  10. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1. Volume 5: Analysis of core damage frequency from seismic events during mid-loop operations

    SciTech Connect (OSTI)

    Budnitz, R.J. [Future Resources Associates, Inc., Berkeley, CA (United States); Davis, P.R. [PRD Consulting (United States); Ravindra, M.K.; Tong, W.H. [EQE International, Inc., Irvine, CA (United States)

    1994-08-01T23:59:59.000Z

    In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1) and the other at Sandia National Laboratories studying a boiling water reactor (Grand Gulf). Both the Brookhaven and Sandia projects have examined only accidents initiated by internal plant faults--so-called ``internal initiators.`` This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling shutdown conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Surry Unit 1. All of the many systems modeling assumptions, component non-seismic failure rates, and human error rates that were used in the internal-initiator study at Surry have been adopted here, so that the results of the two studies can be as comparable as possible. Both the Brookhaven study and this study examine only two shutdown plant operating states (POSs) during refueling outages at Surry, called POS 6 and POS 10, which represent mid-loop operation before and after refueling, respectively. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POSs 6 and 10. The results of the analysis are that the core-damage frequency of earthquake-initiated accidents during refueling outages in POS 6 and POS 10 is found to be low in absolute terms, less than 10{sup {minus}6}/year.

  11. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix E (Sections E.9-E.16), Volume 2, Part 3B

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Wong, S.M. [Brookhaven National Lab., Upton, NY (United States); Bley, D.; Johnson, D. [PLG Inc., Newport Beach, CA (United States)] [and others

    1994-06-01T23:59:59.000Z

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis.

  12. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendices F-H, Volume 2, Part 4

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J. [Brookhaven National Lab., Upton, NY (United States); Bley, D.; Johnson, D. [PLG Inc., Newport Beach, CA (United States); Holmes, B. [AEA Technology, Dorset (United Kingdom)] [and others

    1994-06-01T23:59:59.000Z

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis.

  13. Uncertainty analysis

    SciTech Connect (OSTI)

    Thomas, R.E.

    1982-03-01T23:59:59.000Z

    An evaluation is made of the suitability of analytical and statistical sampling methods for making uncertainty analyses. The adjoint method is found to be well-suited for obtaining sensitivity coefficients for computer programs involving large numbers of equations and input parameters. For this purpose the Latin Hypercube Sampling method is found to be inferior to conventional experimental designs. The Latin hypercube method can be used to estimate output probability density functions, but requires supplementary rank transformations followed by stepwise regression to obtain uncertainty information on individual input parameters. A simple Cork and Bottle problem is used to illustrate the efficiency of the adjoint method relative to certain statistical sampling methods. For linear models of the form Ax=b it is shown that a complete adjoint sensitivity analysis can be made without formulating and solving the adjoint problem. This can be done either by using a special type of statistical sampling or by reformulating the primal problem and using suitable linear programming software.

  14. Robustness Analysis Michael Weisberg

    E-Print Network [OSTI]

    Weisberg, Michael

    Robustness Analysis Michael Weisberg University of Pennsylvania September 14, 2005 Abstract Modelers often rely on robustness analysis, the search for predic- tions common to several independent models. Robustness analysis has been characterized and championed by Richard Levins and William Wimsatt

  15. Introduction Some quantitative analysis

    E-Print Network [OSTI]

    Maume-Deschamps, Véronique

    Introduction Some quantitative analysis Simulations Conclusion, further work Risk indicators Simulations Conclusion, further work Plan 1 Introduction Context Risk indicators 2 Some quantitative analysis;Introduction Some quantitative analysis Simulations Conclusion, further work Context Risk indicators

  16. Clean Energy Policy Analysis: Impact Analysis of Potential Clean...

    Energy Savers [EERE]

    Clean Energy Policy Analysis: Impact Analysis of Potential Clean Energy Policy Options for the Hawaii Clean Energy Initiative Clean Energy Policy Analysis: Impact Analysis of...

  17. chemical analysis | EMSL

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

    chemical analysis chemical analysis Leads No leads are available at this time. Microstructure and Cs Behavior of Ba-Doped Aluminosilicate Pollucite Irradiated with F+ Ions....

  18. Planning, Budget, and Analysis

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

    Analysis (Revised) Philip Patterson (Economist) and Jeff Dowd (Economist) DOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29,...

  19. analysis reveals permanent: Topics by E-print Network

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

    Index 21 Design and analysis aspects of radial flux air-cored permanent magnet wind generator system for direct battery charging applications. Open Access Theses and...

  20. Engineering Analysis | ornl.gov

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

    Home | Science & Discovery | Supercomputing and Computation | Research Areas | Engineering Analysis SHARE Engineering Analysis Engineering analysis involves the application...

  1. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix I, Volume 2, Part 5

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J. [Brookhaven National Lab., Upton, NY (United States); Bley, D.; Johnson, D. [PLG Inc., Newport Beach, CA (United States); Holmes, B. [AEA Technology, Dorset (United Kingdom)] [and others

    1994-06-01T23:59:59.000Z

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Lab. (BNL) and Sandia National Labs. (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this volume of the report is to document the approach utilized in the level-1 internal events PRA for the Surry plant, and discuss the results obtained. A phased approach was used in the level-1 program. In phase 1, which was completed in Fall 1991, a coarse screening analysis examining accidents initiated by internal events (including internal fire and flood) was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis.

  2. Statistical Analysis and Geologic Evaluation of Laboratory-Derived Physical Property Data for Selected Nevada Test Site Core Samples of Non-Zeolitized Tuffs

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-04-20T23:59:59.000Z

    A statistical analysis and geologic evaluation of recently acquired laboratory-derived physical property data are being performed to better understand and more precisely correlate physical properties with specific geologic parameters associated with non-zeolitized tuffs at the Nevada Test Site. Physical property data include wet and dry bulk density, grain density (i.e., specific gravity), total porosity, and effective porosity. Geologic parameters utilized include degree of welding, lithology, stratigraphy, geographic area, and matrix mineralogy (i.e., vitric versus devitrified). Initial results indicate a very good correlation between physical properties and geologic parameters such as degree of welding, lithology, and matrix mineralogy. However, physical properties appear to be independent of stratigraphy and geographic area, suggesting that the data are transferrable with regards to these two geologic parameters. Statistical analyses also indicate that the assumed grain density of 2.65 grams per cubic centimeter used to calculate porosity in some samples is too high. This results in corresponding calculated porosity values approximately 5 percent too high (e.g., 45 percent versus 40 percent), which can be significant in the lower porosity rocks. Similar analyses and evaluations of zeolitic tuffs and carbonate rock physical properties data are ongoing as well as comparisons to geophysical log values.

  3. K Basin Hazard Analysis

    SciTech Connect (OSTI)

    PECH, S.H.

    2000-08-23T23:59:59.000Z

    This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Final Safety Analysis Report. This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

  4. K Basins Hazard Analysis

    SciTech Connect (OSTI)

    WEBB, R.H.

    1999-12-29T23:59:59.000Z

    This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Safety Analysis Report (HNF-SD-WM-SAR-062, Rev.4). This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

  5. Comparative Analysis of the 15.5kD Box C/D snoRNP Core Protein in the Primitive Eukaryote Giardia lamblia Reveals Unique Structural and Functional Features

    SciTech Connect (OSTI)

    Biswas, Shyamasri; Buhrman, Greg; Gagnon, Keith; Mattos, Carla; Brown, II, Bernard A.; Maxwell, E. Stuart (NCSU); (UTSMC)

    2012-07-11T23:59:59.000Z

    Box C/D ribonucleoproteins (RNP) guide the 2'-O-methylation of targeted nucleotides in archaeal and eukaryotic rRNAs. The archaeal L7Ae and eukaryotic 15.5kD box C/D RNP core protein homologues initiate RNP assembly by recognizing kink-turn (K-turn) motifs. The crystal structure of the 15.5kD core protein from the primitive eukaryote Giardia lamblia is described here to a resolution of 1.8 {angstrom}. The Giardia 15.5kD protein exhibits the typical {alpha}-{beta}-{alpha} sandwich fold exhibited by both archaeal L7Ae and eukaryotic 15.5kD proteins. Characteristic of eukaryotic homologues, the Giardia 15.5kD protein binds the K-turn motif but not the variant K-loop motif. The highly conserved residues of loop 9, critical for RNA binding, also exhibit conformations similar to those of the human 15.5kD protein when bound to the K-turn motif. However, comparative sequence analysis indicated a distinct evolutionary position between Archaea and Eukarya. Indeed, assessment of the Giardia 15.5kD protein in denaturing experiments demonstrated an intermediate stability in protein structure when compared with that of the eukaryotic mouse 15.5kD and archaeal Methanocaldococcus jannaschii L7Ae proteins. Most notable was the ability of the Giardia 15.5kD protein to assemble in vitro a catalytically active chimeric box C/D RNP utilizing the archaeal M. jannaschii Nop56/58 and fibrillarin core proteins. In contrast, a catalytically competent chimeric RNP could not be assembled using the mouse 15.5kD protein. Collectively, these analyses suggest that the G. lamblia 15.5kD protein occupies a unique position in the evolution of this box C/D RNP core protein retaining structural and functional features characteristic of both archaeal L7Ae and higher eukaryotic 15.5kD homologues.

  6. Analysis of a rod withdrawal in a PWR core with the neutronic- thermalhydraulic coupled code RELAP/PARCS and RELAP/VALKIN

    SciTech Connect (OSTI)

    Miro, R.; Maggini, F.; Barrachina, T.; Verdu, G. [Departamento de Ingenieria Quimica y Nuclear, Universidad Politecnica de Valencia, Camino de Vera, 14, 46022, Valencia (Spain); Gomez, A.; Ortego, A. [IBERINCO, Avenida de Burgos, Madrid (Spain); Murillo, J. C. [CNAT, Av. Manoteras, Madrid (Spain)

    2006-07-01T23:59:59.000Z

    The Reactor Ejection Accident (REA) belongs to the Reactor Initiated Accidents (RIA) category of accidents and it is part of the licensing basis accident analyses required for pressure water reactors (PWR). The REA at hot zero power (HZP) is characterized by a single rod ejection from a core position with a very low power level. The evolution consists basically of a continuous reactivity insertion. The main feature limiting the consequences of the accident in a PWR is the Doppler Effect. To check the performance of the coupled code RELAP5/PARCS2.5 and RELAP5/VALKIN a REA in Trillo NPP is simulated. These analyses will allow knowing more accurately the PWR real plant phenomenology in the RIA most limiting conditions. (authors)

  7. Strategic Analysis and Modeling

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

    analysis, NREL-Market and Policy Impact Analysis, NREL-SI, NREL-VT, ORNL, PNNL * Industry: Celanese, ExxonMobil, Linde, Proterro, SABIC, U.S. DRIVE * Government Agencies:...

  8. Systems Analysis Workshop Purpose

    Broader source: Energy.gov [DOE]

    Presentation on SAW purpose to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  9. Hydrogen Analysis Group

    SciTech Connect (OSTI)

    Not Available

    2008-03-01T23:59:59.000Z

    NREL factsheet that describes the general activites of the Hydrogen Analysis Group within NREL's Hydrogen Technologies and Systems Center.

  10. Analysis Models and Tools: Systems Analysis of Hydrogen and Fuel...

    Office of Environmental Management (EM)

    and Fuel Cells Analysis Models and Tools: Systems Analysis of Hydrogen and Fuel Cells The Fuel Cell Technologies Office's systems analysis program uses a consistent set of models...

  11. REAL ANALYSIS: DRIPPED VERSION

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    i ELEMENTARY REAL ANALYSIS: DRIPPED VERSION -------------------------- thomson·bruckner2 -------------------------- Brian S. Thomson Judith B. Bruckner Andrew M. Bruckner www.classicalrealanalysis.com (2008) ClassicalRealAnalysis.com [TBB-Dripped] Elementary Real Analysis - Dripped Version Thomson*Bruckner*Bruckner #12;ii D

  12. Fusion neutronics experiments and analysis

    SciTech Connect (OSTI)

    Abdou, M.A.

    1991-06-01T23:59:59.000Z

    This report discusses the following topics: Tritium breeding measurements and analysis; induced radioactivity measurements and analysis; and nuclear heating measurements and analysis. (LSP)

  13. Transportation Analysis | Clean Energy | ORNL

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

    Transportation Analysis SHARE Transportation Analysis Transportation Analysis efforts at Oak Ridge National Laboratory contribute to the efficient, safe, and free movement of...

  14. Hydrogen Delivery Infrastructure Option Analysis

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

    Infrastructure Hydrogen Delivery Infrastructure Option Analysis Option Analysis DOE and FreedomCAR & Fuel Partnership Hydrogen Delivery and On-Board Storage Analysis Workshop...

  15. ACCIDENT ANALYSIS AND HAZARD ANALYSIS FOR HUMAN AND ORGANIZATIONAL FACTORS

    E-Print Network [OSTI]

    Leveson, Nancy

    culpable. An accident analysis method is needed that will guide the work, aid in the analysis of the role

  16. HAZARD ANALYSIS SOFTWARE

    SciTech Connect (OSTI)

    Sommer, S; Tinh Tran, T

    2008-04-08T23:59:59.000Z

    Washington Safety Management Solutions, LLC developed web-based software to improve the efficiency and consistency of hazard identification and analysis, control selection and classification, and to standardize analysis reporting at Savannah River Site. In the new nuclear age, information technology provides methods to improve the efficiency of the documented safety analysis development process which includes hazard analysis activities. This software provides a web interface that interacts with a relational database to support analysis, record data, and to ensure reporting consistency. A team of subject matter experts participated in a series of meetings to review the associated processes and procedures for requirements and standard practices. Through these meetings, a set of software requirements were developed and compiled into a requirements traceability matrix from which software could be developed. The software was tested to ensure compliance with the requirements. Training was provided to the hazard analysis leads. Hazard analysis teams using the software have verified its operability. The software has been classified as NQA-1, Level D, as it supports the analysis team but does not perform the analysis. The software can be transported to other sites with alternate risk schemes. The software is being used to support the development of 14 hazard analyses. User responses have been positive with a number of suggestions for improvement which are being incorporated as time permits. The software has enforced a uniform implementation of the site procedures. The software has significantly improved the efficiency and standardization of the hazard analysis process.

  17. Hydrogen Analysis | Department of Energy

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

    Hydrogen Analysis Hydrogen Analysis Presentation on Hydrogen Analysis to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of...

  18. PROCESS ANALYSIS What is it?

    E-Print Network [OSTI]

    Boonstra, Rudy

    PROCESS ANALYSIS What is it? Process analysis answers the question: "How?" Process analysis of events occurred. There are two kinds of process analysis: directional and informational. Directional, or prescriptive, process analysis asks: How do you do it? This kind of analysis examines how to do something

  19. Data Collection and Analysis

    Energy Savers [EERE]

    DataCollecGon&Analysis MarloweKulley PortlandBureauofPlanning&Sustainability DOEConference|May20,2011|Arlington,VA 2...

  20. EMSL - chemical analysis

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

    chemical-analysis en Microstructure and Cs Behavior of Ba-Doped Aluminosilicate Pollucite Irradiated with F+ Ions. http:www.emsl.pnl.govemslwebpublications...

  1. Sandia National Laboratories: Analysis

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

    Infrastructure Security, News, News & Events, Partnership, Renewable Energy, SMART Grid, Systems Analysis, Transmission Grid Integration, Wind Energy The U.S. Department...

  2. harmonic analysis and geometry

    E-Print Network [OSTI]

    Faculty listing for "harmonic analysis and geometry". vCard of Nicola Garofalo Garofalo, Nicola [bio] [homepage] Adjunct Professor of Mathematics

  3. Modeling and Analysis

    Broader source: Energy.gov [DOE]

    DOE modeling and analysis activities focus on reducing uncertainties and improving transparency in photovoltaics (PV) and concentrating solar power (CSP) performance modeling. The overall goal of...

  4. Hazard Analysis Database Report

    SciTech Connect (OSTI)

    GRAMS, W.H.

    2000-12-28T23:59:59.000Z

    The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for U S . Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for HNF-SD-WM-SAR-067, Tank Farms Final Safety Analysis Report (FSAR). The FSAR is part of the approved Authorization Basis (AB) for the River Protection Project (RPP). This document describes, identifies, and defines the contents and structure of the Tank Farms FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The Hazard Analysis Database supports the preparation of Chapters 3 ,4 , and 5 of the Tank Farms FSAR and the Unreviewed Safety Question (USQ) process and consists of two major, interrelated data sets: (1) Hazard Analysis Database: Data from the results of the hazard evaluations, and (2) Hazard Topography Database: Data from the system familiarization and hazard identification.

  5. Asset Protection Analysis Guide

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

    2008-08-21T23:59:59.000Z

    The Guide provides examples of the application of as set protection analysis to several common problems. Canceled by DOE N 251.80.

  6. Core length testable reactor concept neutronic analysis

    SciTech Connect (OSTI)

    Hanan, N.A.; Bhattacharyya, S.K.

    1992-09-01T23:59:59.000Z

    Development work on thermionic reactor systems has been ongoing in the US since the early 1950s. While significant successes were achieved, progress has been hampered by frequent changes in direction and funding instabilities (as has been true for many high technology initiatives). The recent Air Force thermionics initiative (1991) represents the latest in thermionics reactor development in the US. This Air Force initiative called for the development of thermionics reactors with the output power of about 40 kWe, and which incorporated the features of testability, fabricability, low development cost, high level of safety and reliability, and survivability. Several concepts were analyzed to define a design that would meet all the requirements set forth by the Air Force. This report describes the methodology used, the different designs analyzed and reasons for the evolution of the design, and presents the results for the different concepts.

  7. Category:Core Analysis | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, click here. Category:Conceptual Model Add.png Add a newpage? For detailed

  8. Analysis of Hydrologic Properties Data

    SciTech Connect (OSTI)

    L. Pan

    2004-10-04T23:59:59.000Z

    This analysis report describes the methods used to determine hydrologic properties based on the available field data from the unsaturated zone (UZ) at Yucca Mountain, Nevada. The technical scope, content, and management of this analysis report are described in the planning document ''Technical Work Plan for: Unsaturated Zone Flow Analysis and Model Report Integration'' (BSC 2004 [DIRS 169654], Sections 2, 4, and 8). Fracture and matrix properties are developed by analyzing available survey data from the Exploratory Studies Facility (ESF), the Enhanced Characterization of Repository Block (ECRB) Cross-Drift, and/or boreholes; air-injection testing data from surface boreholes and from boreholes in the ESF; and data from laboratory testing of core samples. In addition, the report ''Geologic Framework Model'' (GFM2000) (BSC 2004 [DIRS 170029]) also serves as a source report by providing the geological framework model of the site. This report is a revision of the model report under the same title (BSC 2003 [DIRS 161773]), which in turn superceded the analysis report under the same title. The principal purpose of this work is to provide representative uncalibrated estimates of fracture and matrix properties for use in the model report Calibrated Properties Model. The term ''uncalibrated'' is used to distinguish the properties or parameters estimated in this report from those obtained from the inversion modeling used in ''Calibrated Properties Model''. The present work also provides fracture geometry properties for generating dual-permeability grids as documented in the scientific analyses report, ''Development of Numerical Grids for UZ Flow and Transport Modeling''.

  9. Supply Chain Analysis Center for Transportation Analysis

    E-Print Network [OSTI]

    , Distribution network configuration, Reverse logistics, and Inventory levels and positioning. Integration configuration of the supply chain? What should be the modal configuration for the distribution network? How operations of the Defense Distribution Center. The analysis included a review of suppliers, distribution

  10. Frequency Measurement & Analysis Service

    E-Print Network [OSTI]

    Magee, Joseph W.

    NIST Frequency Measurement & Analysis Service #12;A Complete Solution To All Frequency Measurement & Calibration Problems The NIST Frequency Measurement and Analysis Service makes it easy to measure and calibrate any quartz, rubidium, or cesium frequency standard. All measurements are made automatically

  11. The Bitcoin Backbone Protocol: Analysis and Applications

    E-Print Network [OSTI]

    The Bitcoin Backbone Protocol: Analysis and Applications Juan A. Garay Yahoo Labs garay.leonardos@gmail.com November 16, 2014 Abstract Bitcoin is the first and most popular decentralized cryptocurrency to date. In this work, we extract and analyze the core of the Bitcoin protocol, which we term the Bitcoin backbone

  12. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16T23:59:59.000Z

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  13. Decision Support:Decision Support: Decision AnalysisDecision Analysis

    E-Print Network [OSTI]

    Bohanec, Marko

    -Making under Risk · Expected Value · Sensitivity Analysis Decision Analysis Decision Analysis: Applied Decision Decision-Making Process Source: Decision Analysis ­ A Tool to Deal with Uncertainty, http Succeed Fail Decision Trees OR/MS · Multi-Criteria Optimisation · Risk Analysis and Simulation · Bayesian

  14. Attached sunspace design analysis

    SciTech Connect (OSTI)

    Jones, R.W.; McFarland, R.D.

    1981-01-01T23:59:59.000Z

    An introduction to new design analysis information for attached sunspaces is presented. The 28 sunspace reference designs are described. Note is taken of those designs (the semi-enclosed geometries) analyzed more recently than the previously published reports. The role of sensitivity studies is discussed, and some sample plots of sunspace performance sensitivity to key design parameters are presented. The monthly solar load ratio (SLR) correlations are reviewed with emphasis on the modified SLR used in the sunspace analysis. The application of the sunspace SLR correlations to monthly design analysis is outlined.

  15. Analysis of Pebble-Bed VHTR Spectrum Shifting Capabilities for Advanced Fuel Cycles

    E-Print Network [OSTI]

    Pritchard, Megan

    2006-07-11T23:59:59.000Z

    (Very High Temperature Reactor) configurations by utilizing minor actinides as a fuel component. The present analysis takes into consideration and compares capabilities of pebble-bed core designs with various core and reflector configuration to allow...

  16. Analysis of the Pebble-Bed VHTR Spectrum Shifting Capabilities for Advanced Fuel Cycles

    E-Print Network [OSTI]

    Pritchard, Megan; Tsvetkov, Pavel

    2009-09-30T23:59:59.000Z

    (Very High Temperature Reactor) configurations by utilizing minor actinides as a fuel component. The present analysis takes into consideration and compares capabilities of pebble-bed core designs with various core and reflector configuration to allow...

  17. The Tariff Analysis Project: A Database and Analysis Platform...

    Open Energy Info (EERE)

    search Tool Summary LAUNCH TOOL Name: The Tariff Analysis Project: A Database and Analysis Platform for Electricity Tariffs Focus Area: Renewable Energy Topics: Policy...

  18. On Field Constraint Analysis

    E-Print Network [OSTI]

    Wies, Thomas

    2005-11-03T23:59:59.000Z

    We introduce field constraint analysis, a new technique for verifying data structure invariants. A field constraint for a field is a formula specifying a set of objects to which the field can point. Field constraints ...

  19. Fluid Inclusion Gas Analysis

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

    Dilley, Lorie

    Fluid inclusion gas analysis for wells in various geothermal areas. Analyses used in developing fluid inclusion stratigraphy for wells and defining fluids across the geothermal fields. Each sample has mass spectrum counts for 180 chemical species.

  20. Fluid Inclusion Gas Analysis

    SciTech Connect (OSTI)

    Dilley, Lorie

    2013-01-01T23:59:59.000Z

    Fluid inclusion gas analysis for wells in various geothermal areas. Analyses used in developing fluid inclusion stratigraphy for wells and defining fluids across the geothermal fields. Each sample has mass spectrum counts for 180 chemical species.

  1. Supervisory Program Analysis Officer

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will be responsible for the program analysis and evaluation of all activities which fall within the purview of the Office. The incumbent directs a moderate...

  2. Energy Sector Market Analysis

    SciTech Connect (OSTI)

    Arent, D.; Benioff, R.; Mosey, G.; Bird, L.; Brown, J.; Brown, E.; Vimmerstedt, L.; Aabakken, J.; Parks, K.; Lapsa, M.; Davis, S.; Olszewski, M.; Cox, D.; McElhaney, K.; Hadley, S.; Hostick, D.; Nicholls, A.; McDonald, S.; Holloman, B.

    2006-10-01T23:59:59.000Z

    This paper presents the results of energy market analysis sponsored by the Department of Energy's (DOE) Weatherization and International Program (WIP) within the Office of Energy Efficiency and Renewable Energy (EERE). The analysis was conducted by a team of DOE laboratory experts from the National Renewable Energy Laboratory (NREL), Oak Ridge National Laboratory (ORNL), and Pacific Northwest National Laboratory (PNNL), with additional input from Lawrence Berkeley National Laboratory (LBNL). The analysis was structured to identify those markets and niches where government can create the biggest impact by informing management decisions in the private and public sectors. The analysis identifies those markets and niches where opportunities exist for increasing energy efficiency and renewable energy use.

  3. Production, Storage, and FC Analysis

    Broader source: Energy.gov [DOE]

    Presentation on Production, Storage, and FC Analysis to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  4. Cogeneration Project Analysis Update

    E-Print Network [OSTI]

    Robinson, A. M.; Garcia, L. N.

    diverse factors, such as, but no limited to: Fuel Considerations, Heat System Analysis, Electric Power Considerations, Key Technical Project Considerations, and Economic Analysis. INTRODUCTION The cogeneration systems being developed for industrial... power marched upward at a higher rate than fuel, capital equipment cost, and the prime interest rate. Typical Cogeneration System One system has been chosen as typical. This is one of the cogeneration systems which have proliferated over the past...

  5. Statistical Hot Channel Analysis for the NBSR

    SciTech Connect (OSTI)

    Cuadra A.; Baek J.

    2014-05-27T23:59:59.000Z

    A statistical analysis of thermal limits has been carried out for the research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The objective of this analysis was to update the uncertainties of the hot channel factors with respect to previous analysis for both high-enriched uranium (HEU) and low-enriched uranium (LEU) fuels. Although uncertainties in key parameters which enter into the analysis are not yet known for the LEU core, the current analysis uses reasonable approximations instead of conservative estimates based on HEU values. Cumulative distribution functions (CDFs) were obtained for critical heat flux ratio (CHFR), and onset of flow instability ratio (OFIR). As was done previously, the Sudo-Kaminaga correlation was used for CHF and the Saha-Zuber correlation was used for OFI. Results were obtained for probability levels of 90%, 95%, and 99.9%. As an example of the analysis, the results for both the existing reactor with HEU fuel and the LEU core show that CHFR would have to be above 1.39 to assure with 95% probability that there is no CHF. For the OFIR, the results show that the ratio should be above 1.40 to assure with a 95% probability that OFI is not reached.

  6. Distributed analysis in ATLAS

    E-Print Network [OSTI]

    Dewhurst, Alastair; The ATLAS collaboration

    2015-01-01T23:59:59.000Z

    The ATLAS experiment accumulated more than 140 PB of data during the first run of the Large Hadron Collider (LHC) at CERN. The analysis of such an amount of data for the distributed physics community is a challenging task. The Distributed Analysis (DA) system of the ATLAS experiment is an established and stable component of the ATLAS distributed computing operations. About half a million user jobs are daily running on DA resources, submitted by more than 1500 ATLAS physicists. The reliability of the DA system during the first run of the LHC and the following shutdown period has been high thanks to the continuous automatic validation of the distributed analysis sites and the user support provided by a dedicated team of expert shifters. During the LHC shutdown, the ATLAS computing model has undergone several changes to improve the analysis workflows, including the re-design of the production system, a new analysis data format and event model, and the development of common reduction and analysis frameworks. We r...

  7. ORISE: Data Collection and Analysis

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

    interview Surveys and questionnaires Media analysis and monitoring Content analysis Case studies Participant observation Message and concept testing Usability testing These...

  8. ORISE: Media Analysis and Monitoring

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

    Media Analysis and Monitoring The Oak Ridge Institute for Science and Education (ORISE) uses comprehensive media analysis and monitoring tools to define media interest and the...

  9. Sandia National Laboratories: Modeling & Analysis

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

    Sandia Study Shows Large LNG Fires Hotter but Smaller Than Expected On December 6, 2011, in Analysis, Energy Assurance, Infrastructure Security, Modeling, Modeling & Analysis,...

  10. Tools for Surface Analysis | EMSL

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

    surface analysis - Because of the importance of clear and unambiguous communications, ISO definitions and concepts related to surface chemical analysis are now freely available....

  11. Planning, Budget, and Analysis | Department of Energy

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

    Planning, Budget, and Analysis Planning, Budget, and Analysis Presentation on Planning, Budget, and Analysis to the DOE Systems Analysis Workshop held in Washington, D.C. July...

  12. Advanced application of the discrete generalized multigroup method and recondensation to reactor analysis

    E-Print Network [OSTI]

    Everson, Matthew S

    2014-01-01T23:59:59.000Z

    Fine-group whole-core reactor analysis remains one of the long sought goals of the reactor physics community. Such a detailed analysis is typically too computationally expensive to be realized on anything except the largest ...

  13. Figure 2 Analysis Tool Interface Level-1 / PBBT Analysis Tool

    E-Print Network [OSTI]

    Figure 2 ­ Analysis Tool Interface Level-1 / PBBT Analysis Tool Introduction The Level-1/PBBT Analysis Tool (LPAT) was designed to assist in the analysis of North American Standard Level-1 Inspection. The data incorporated into the tool includes the results of Level-1 inspections with accompanying PBBT test

  14. Power electronics reliability analysis.

    SciTech Connect (OSTI)

    Smith, Mark A.; Atcitty, Stanley

    2009-12-01T23:59:59.000Z

    This report provides the DOE and industry with a general process for analyzing power electronics reliability. The analysis can help with understanding the main causes of failures, downtime, and cost and how to reduce them. One approach is to collect field maintenance data and use it directly to calculate reliability metrics related to each cause. Another approach is to model the functional structure of the equipment using a fault tree to derive system reliability from component reliability. Analysis of a fictitious device demonstrates the latter process. Optimization can use the resulting baseline model to decide how to improve reliability and/or lower costs. It is recommended that both electric utilities and equipment manufacturers make provisions to collect and share data in order to lay the groundwork for improving reliability into the future. Reliability analysis helps guide reliability improvements in hardware and software technology including condition monitoring and prognostics and health management.

  15. Foundations of VISAR analysis.

    SciTech Connect (OSTI)

    Dolan, Daniel H.

    2006-06-01T23:59:59.000Z

    The Velocity Interferometer System for Any Reflector (VISAR) is a widely used diagnostic at Sandia National Laboratories. Although the operating principles of the VISAR are well established, recently deployed systems (such as the fast push-pull and air delay VISAR) require more careful consideration, and many common assumptions about VISAR are coming into question. This report presents a comprehensive review of VISAR analysis to address these issues. Detailed treatment of several interferometer configurations is given to identify important aspects of the operation and characterization of VISAR systems. The calculation of velocity from interferometer measurements is also described. The goal is to derive the standard VISAR analysis relationships, indicate when these relationships are valid, and provide alternative methods when the standard analysis fails.

  16. Contamination analysis unit

    DOE Patents [OSTI]

    Gregg, Hugh R. (Livermore, CA); Meltzer, Michael P. (Livermore, CA)

    1996-01-01T23:59:59.000Z

    The portable Contamination Analysis Unit (CAU) measures trace quantifies of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surface by measuring residual hazardous surface contamination, such as tritium and trace organics It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings.

  17. Contamination analysis unit

    DOE Patents [OSTI]

    Gregg, H.R.; Meltzer, M.P.

    1996-05-28T23:59:59.000Z

    The portable Contamination Analysis Unit (CAU) measures trace quantities of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surfaces by measuring residual hazardous surface contamination, such as tritium and trace organics. It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings. 1 fig.

  18. Image texture analysis of elastograms

    E-Print Network [OSTI]

    Hussain, Fasahat

    1999-01-01T23:59:59.000Z

    generated elastograms to obtain effective texture features. Four image analysis techniques, co-occurrence statistics, wavelet decomposition, fractal analysis and granulomeay are used to extract a number of features from each image. The inclusions...-RESOLUTION FRACTAL ANALYSIS . . . . . . E. GRANULOMETRIC FEATURES . . F. DATA NORMALIZATION . G. SEPARABILITY MEASURE 13 13 . . . . . 14 . . . . . 20 . . . . . 29 33 36 36 IV TEXTURE ANALYSIS OF SIMULATED ELASTOGRAMS. . . . . . . . . . . 38 A. SIMULATION...

  19. Numerical Analysis Gordon K. Smyth

    E-Print Network [OSTI]

    Smyth, Gordon K.

    Numerical Analysis Gordon K. Smyth May 1997 Numerical analysis is concerned with the accurate discipline of numer­ ical analysis is almost entirely a product of the period since 1950 during which biostatisticians can benefit from familiarity with numerical analysis. An understanding of the numerical methods

  20. STEP Utility Bill Analysis Report

    Broader source: Energy.gov [DOE]

    STEP Utility Bill Analysis Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  1. Pest Risk Analysis for Hymenoscyphus

    E-Print Network [OSTI]

    Pest Risk Analysis for Hymenoscyphus pseudoalbidus for the UK and the Republic of Ireland #12;2 PRA for Hymenoscyphus pseudoalbidus C.E. Sansford 23rd May 2013 Pest Risk Analysis Pest Risk Analysis for Hymenoscyphus (Kowalski and Holdenrieder, 2009). 1 Please cite this document as: Sansford, CE (2013). Pest Risk Analysis

  2. Cost analysis guidelines

    SciTech Connect (OSTI)

    Strait, R.S.

    1996-01-10T23:59:59.000Z

    The first phase of the Depleted Uranium Hexafluoride Management Program (Program)--management strategy selection--consists of several program elements: Technology Assessment, Engineering Analysis, Cost Analysis, and preparation of an Environmental Impact Statement (EIS). Cost Analysis will estimate the life-cycle costs associated with each of the long-term management strategy alternatives for depleted uranium hexafluoride (UF6). The scope of Cost Analysis will include all major expenditures, from the planning and design stages through decontamination and decommissioning. The costs will be estimated at a scoping or preconceptual design level and are intended to assist decision makers in comparing alternatives for further consideration. They will not be absolute costs or bid-document costs. The purpose of the Cost Analysis Guidelines is to establish a consistent approach to analyzing of cost alternatives for managing Department of Energy`s (DOE`s) stocks of depleted uranium hexafluoride (DUF6). The component modules that make up the DUF6 management program differ substantially in operational maintenance, process-options, requirements for R and D, equipment, facilities, regulatory compliance, (O and M), and operations risk. To facilitate a consistent and equitable comparison of costs, the guidelines offer common definitions, assumptions or basis, and limitations integrated with a standard approach to the analysis. Further, the goal is to evaluate total net life-cycle costs and display them in a way that gives DOE the capability to evaluate a variety of overall DUF6 management strategies, including commercial potential. The cost estimates reflect the preconceptual level of the designs. They will be appropriate for distinguishing among management strategies.

  3. Germanium-76 Sample Analysis

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Engelhard, Mark H.; Zhu, Zihua

    2011-04-01T23:59:59.000Z

    The MAJORANA DEMONSTRATOR is a large array of ultra-low background high-purity germanium detectors, enriched in 76Ge, designed to search for zero-neutrino double-beta decay (0???). The DEMONSTRATOR will utilize 76Ge from Russia, and the first one gram sample was received from the supplier for analysis on April 24, 2011. The Environmental Molecular Sciences facility, a DOE user facility at PNNL, was used to make the required isotopic and chemical purity measurements that are essential to the quality assurance for the MAJORANA DEMONSTRATOR. The results of this first analysis are reported here.

  4. UCF WP TIPOVER ANALYSIS

    SciTech Connect (OSTI)

    Z. Ceylan

    1998-04-28T23:59:59.000Z

    The purpose of this analysis is to determine the structural response of the 21 pressurized water reactor (PWR) uncanistered fuel (UCF) waste package (WP) to a tipover design basis event (DBE) dynamic load; the results will be reported in terms of stress magnitudes. Finite-element solution was performed by making use of the commercially available ANSYS finite-element code. A finite-element model of the waste package was developed and analyzed for a tipover DBE dynamic load. The results of this analysis were provided in tables and were also plotted in terms of the maximum stress contours to determine their locations.

  5. Analysis Preservation in ATLAS

    E-Print Network [OSTI]

    Heinrich, Lukas; The ATLAS collaboration; Jones, Roger; Cranmer, Kyle

    2015-01-01T23:59:59.000Z

    Long before data taking ATLAS established a policy that all analyses need to be preserved. In the initial data-taking period, this has been achieved by various tools and techniques. ATLAS is now reviewing the analysis preservation with the aim to bring coherence and robustness to the process and with a clearer view of the level of reproducibility that is reasonably achievable. The secondary aim is to reduce the load on the analysts. Once complete, this will serve for our internal preservation needs but also provide a basis for any subsequent sharing of analysis results with external parties.

  6. Analysis | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you0 ARRA NewslettersPartnership of the Americas | DepartmentAnalysis Analysis

  7. Understanding Forage Quality Analysis

    E-Print Network [OSTI]

    Stokes, Sandra R.; Prostko, Eric P.

    1998-03-23T23:59:59.000Z

    Understanding Forage Quality Analysis Sandra R. Stokes and Eric P. Prostko* L-5198 3-98 M any dairy producers in Texas do not have the land to grow their own forages. Consequent- ly, they rely on both local and out-of-state farmers for supplies...

  8. Coal systems analysis

    SciTech Connect (OSTI)

    Warwick, P.D. (ed.)

    2005-07-01T23:59:59.000Z

    This collection of papers provides an introduction to the concept of coal systems analysis and contains examples of how coal systems analysis can be used to understand, characterize, and evaluate coal and coal gas resources. Chapter are: Coal systems analysis: A new approach to the understanding of coal formation, coal quality and environmental considerations, and coal as a source rock for hydrocarbons by Peter D. Warwick. Appalachian coal assessment: Defining the coal systems of the Appalachian Basin by Robert C. Milici. Subtle structural influences on coal thickness and distribution: Examples from the Lower Broas-Stockton coal (Middle Pennsylvanian), Eastern Kentucky Coal Field, USA by Stephen F. Greb, Cortland F. Eble, and J.C. Hower. Palynology in coal systems analysis The key to floras, climate, and stratigraphy of coal-forming environments by Douglas J. Nichols. A comparison of late Paleocene and late Eocene lignite depositional systems using palynology, upper Wilcox and upper Jackson Groups, east-central Texas by Jennifer M.K. O'Keefe, Recep H. Sancay, Anne L. Raymond, and Thomas E. Yancey. New insights on the hydrocarbon system of the Fruitland Formation coal beds, northern San Juan Basin, Colorado and New Mexico, USA by W.C. Riese, William L. Pelzmann, and Glen T. Snyder.

  9. Radiative Flux Analysis

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

    Long, Chuck [NOAA

    The Radiative Flux Analysis is a technique for using surface broadband radiation measurements for detecting periods of clear (i.e. cloudless) skies, and using the detected clear-sky data to fit functions which are then used to produce continuous clear-sky estimates. The clear-sky estimates and measurements are then used in various ways to infer cloud macrophysical properties.

  10. Regional Analysis Briefs

    Reports and Publications (EIA)

    2028-01-01T23:59:59.000Z

    Regional Analysis Briefs (RABs) provide an overview of specific regions that play an important role in world energy markets, either directly or indirectly. These briefs cover areas that are currently major producers (Caspian Sea), have geopolitical importance (South China Sea), or may have future potential as producers or transit areas (East Africa, Eastern Mediterranean).

  11. Country Analysis Briefs

    Reports and Publications (EIA)

    2028-01-01T23:59:59.000Z

    An ongoing compilation of country energy profiles. The Energy Information Administration (EIA) maintains Country Analysis Briefs (CABs) for specific countries that are important to world energy markets, including members of the Organization of the Petroleum Exporting Countries (OPEC), major non-OPEC oil producers, major energy transit countries, major energy consumers, and other areas of current interest to energy analysts and policy makers.

  12. Electronic Mail Analysis Capability

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

    2001-01-08T23:59:59.000Z

    Establishes the pilot program to test the Department of Energy (DOE) Electronic Mail Analysis Capability (EMAC), which will be used to monitor and analyze outgoing and incoming electronic mail (e-mail) from the National Nuclear Security Administration (NNSA) and DOE laboratories that are engaged in nuclear weapons design or work involving special nuclear material. No cancellation.

  13. Fourier Analysis Tom Leinster

    E-Print Network [OSTI]

    functions. (For recall that every power series is infinitely differen- tiable inside its disk of convergence . . . . . . . . . . . . . . . . 66 D2 The dual of a finite abelian group . . . . . . . . . . . . . . . . . . 70 D3 Fourier transforms The algebraist thinks: `Analysis is hard. Can we reduce it to algebra?' Idea Use power series. 1 Many functions f

  14. Fourier Analysis Jan Wiegerinck

    E-Print Network [OSTI]

    Wiegerinck, Jan

    Fourier Analysis Jan Wiegerinck version March 12, 2010 Korteweg ­ de Vries Instituut, Universiteit;#12;Contents Chapter 1. Classical Fourier series 1 1.1. Introduction and Reminder 1 1.2. Sine versus Cosine.7. Exercises 11 1.8. Final remarks, notes, and references 12 Chapter 2. Distributions and their Fourier Series

  15. Group Analysis Jean Daunizeau

    E-Print Network [OSTI]

    Daunizeau, Jean

    ) is measurement error True response magnitude is fixed 111 Xy Fixed effect #12;Random effects-sphericity modelling Examples Power and efficiency: summary Overview #12;Group analysis: fixed versus random effects Two RFX methods: Holmes & Friston (HF) approach non-sphericity modelling Examples Power

  16. Cooperative Testing and Analysis

    E-Print Network [OSTI]

    Xie, Tao

    Cooperative Testing and Analysis: Tao Xie Peking University, China (2011-2012) North Carolina State Account for even half the total cost of software development [Beizer 90] Automated testing reduces manual to the user to get her help? Tool Human How does the user help the tool based on the info? Iterations

  17. CHEMISTRY 330 QUANTITATIVE ANALYSIS

    E-Print Network [OSTI]

    Nickrent, Daniel L.

    and evaluation of error, basic chemical equilibria, acid-base equilibria, solubility product constant equilibria of spectrophotometric analysis, atomic absorption spectroscopy, methods of separation, gas and liquid chromatography to develop and apply topics discussed in lecture; short quizzes may be used to assess individual learning

  18. NID Copper Sample Analysis

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Zhu, Zihua

    2011-09-12T23:59:59.000Z

    The current focal point of the nuclear physics program at PNNL is the MAJORANA DEMONSTRATOR, and the follow-on Tonne-Scale experiment, a large array of ultra-low background high-purity germanium detectors, enriched in 76Ge, designed to search for zero-neutrino double-beta decay (0???). This experiment requires the use of germanium isotopically enriched in 76Ge. The MAJORANA DEMONSTRATOR is a DOE and NSF funded project with a major science impact. The DEMONSTRATOR will utilize 76Ge from Russia, but for the Tonne-Scale experiment it is hoped that an alternate technology, possibly one under development at Nonlinear Ion Dynamics (NID), will be a viable, US-based, lower-cost source of separated material. Samples of separated material from NID require analysis to determine the isotopic distribution and impurities. DOE is funding NID through an SBIR grant for development of their separation technology for application to the Tonne-Scale experiment. The Environmental Molecular Sciences facility (EMSL), a DOE user facility at PNNL, has the required mass spectroscopy instruments for making isotopic measurements that are essential to the quality assurance for the MAJORANA DEMONSTRATOR and for the development of the future separation technology required for the Tonne-Scale experiment. A sample of isotopically separated copper was provided by NID to PNNL in January 2011 for isotopic analysis as a test of the NID technology. The results of that analysis are reported here. A second sample of isotopically separated copper was provided by NID to PNNL in August 2011 for isotopic analysis as a test of the NID technology. The results of that analysis are also reported here.

  19. Text analysis methods, text analysis apparatuses, and articles of manufacture

    DOE Patents [OSTI]

    Whitney, Paul D; Willse, Alan R; Lopresti, Charles A; White, Amanda M

    2014-10-28T23:59:59.000Z

    Text analysis methods, text analysis apparatuses, and articles of manufacture are described according to some aspects. In one aspect, a text analysis method includes accessing information indicative of data content of a collection of text comprising a plurality of different topics, using a computing device, analyzing the information indicative of the data content, and using results of the analysis, identifying a presence of a new topic in the collection of text.

  20. Zeta Functional Analysis

    E-Print Network [OSTI]

    Michael A. Idowu

    2014-10-15T23:59:59.000Z

    We intimate deeper connections between the Riemann zeta and gamma functions than often reported and further derive a new formula for expressing the value of $\\zeta(2n+1)$ in terms of zeta at other fractional points. This paper also establishes and presents new expository notes and perspectives on zeta function theory and functional analysis. In addition, a new fundamental result, in form of a new function called omega $\\Omega(s)$, is introduced to analytic number theory for the first time. This new function together with some of its most fundamental properties and other related identities are here disclosed and presented as a new approach to the analysis of sums of generalised harmonic series, related alternating series and polygamma functions associated with Riemann zeta function.

  1. Local entropy generation analysis

    SciTech Connect (OSTI)

    Drost, M.K.; White, M.D.

    1991-02-01T23:59:59.000Z

    Second law analysis techniques have been widely used to evaluate the sources of irreversibility in components and systems of components but the evaluation of local sources of irreversibility in thermal processes has received little attention. While analytical procedures for evaluating local entropy generation have been developed, applications have been limited to fluid flows with analytical solutions for the velocity and temperature fields. The analysis of local entropy generation can be used to evaluate more complicated flows by including entropy generation calculations in a computational fluid dynamics (CFD) code. The research documented in this report consists of incorporating local entropy generation calculations in an existing CFD code and then using the code to evaluate the distribution of thermodynamic losses in two applications: an impinging jet and a magnetic heat pump. 22 refs., 13 figs., 9 tabs.

  2. Residual gas analysis device

    DOE Patents [OSTI]

    Thornberg, Steven M. (Peralta, NM)

    2012-07-31T23:59:59.000Z

    A system is provided for testing the hermeticity of a package, such as a microelectromechanical systems package containing a sealed gas volume, with a sampling device that has the capability to isolate the package and breach the gas seal connected to a pulse valve that can controllably transmit small volumes down to 2 nanoliters to a gas chamber for analysis using gas chromatography/mass spectroscopy diagnostics.

  3. SAMPLING AND ANALYSIS PROTOCOLS

    SciTech Connect (OSTI)

    Jannik, T; P Fledderman, P

    2007-02-09T23:59:59.000Z

    Radiological sampling and analyses are performed to collect data for a variety of specific reasons covering a wide range of projects. These activities include: Effluent monitoring; Environmental surveillance; Emergency response; Routine ambient monitoring; Background assessments; Nuclear license termination; Remediation; Deactivation and decommissioning (D&D); and Waste management. In this chapter, effluent monitoring and environmental surveillance programs at nuclear operating facilities and radiological sampling and analysis plans for remediation and D&D activities will be discussed.

  4. Automated Job Hazards Analysis

    Broader source: Energy.gov [DOE]

    AJHA Program - The Automated Job Hazard Analysis (AJHA) computer program is part of an enhanced work planning process employed at the Department of Energy's Hanford worksite. The AJHA system is routinely used to performed evaluations for medium and high risk work, and in the development of corrective maintenance work packages at the site. The tool is designed to ensure that workers are fully involved in identifying the hazards, requirements, and controls associated with tasks.

  5. Data& Error Analysis 1 DATA and ERROR ANALYSIS

    E-Print Network [OSTI]

    Mukasyan, Alexander

    Data& Error Analysis 1 DATA and ERROR ANALYSIS Performing the experiment and collecting data learned, you might get a better grade.) Data analysis should NOT be delayed until all of the data. This will help one avoid the problem of spending an entire class collecting bad data because of a mistake

  6. Generalized Multicoincidence Analysis Methods

    SciTech Connect (OSTI)

    Warren, Glen A.; Smith, Leon E.; Aalseth, Craig E.; Ellis, J. E.; Valsan, Andrei B.; Mengesha, Wondwosen

    2005-10-01T23:59:59.000Z

    The ability to conduct automated trace radionuclide analysis at or near the sample collection point would provide a valuable tool for emergency response, nuclear forensics and environmental monitoring. Pacific Northwest National Laboratory is developing systems for this purpose based on dual gamma-ray spectrometers, e.g. NaI(TI) or HPGe, combined with thin organic scintillator sensors to detect light charged particles. Translating the coincident signatures recorded by these systems, which include , and , into the concentration of detectable radionuclides in the sample requires generalized multicoincidence analysis tools. The development and validation of the Coincidence Lookup Library, which currently contains the probabilities of single and coincidence signatures from more than 420 isotopes, is described. Also discussed is a method to calculate the probability of observing a coincidence signature which incorporates true coincidence summing effects. These effects are particularly important for high-geometric-efficiency detection systems. Finally, a process for validating the integrated analysis software package is demonstrated using GEANT 4 simulations of the prototype detector systems.

  7. NID Copper Sample Analysis

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Zhu, Zihua

    2011-02-01T23:59:59.000Z

    The current focal point of the nuclear physics program at PNNL is the MAJORANA DEMONSTRATOR, and the follow-on Tonne-Scale experiment, a large array of ultra-low background high-purity germanium detectors, enriched in 76Ge, designed to search for zero-neutrino double-beta decay (0???). This experiment requires the use of germanium isotopically enriched in 76Ge. The DEMONSTRATOR will utilize 76Ge from Russia, but for the Tonne-Scale experiment it is hoped that an alternate technology under development at Nonlinear Ion Dynamics (NID) will be a viable, US-based, lower-cost source of separated material. Samples of separated material from NID require analysis to determine the isotopic distribution and impurities. The MAJORANA DEMONSTRATOR is a DOE and NSF funded project with a major science impact. DOE is funding NID through an SBIR grant for development of their separation technology for application to the Tonne-Scale experiment. The Environmental Molecular Sciences facility (EMSL), a DOE user facility at PNNL, has the required mass spectroscopy instruments for making these isotopic measurements that are essential to the quality assurance for the MAJORANA DEMONSTRATOR and for the development of the future separation technology required for the Tonne-Scale experiment. A sample of isotopically separated copper was provided by NID to PNNL for isotopic analysis as a test of the NID technology. The results of that analysis are reported here.

  8. NREL: Energy Analysis - Sean Esterly

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

    Sean Esterly is a member of the Market and Policy Impact Analysis Group in the Strategic Energy Analysis Center. Analyst On staff since August 2013 Phone number: 303-384-7436...

  9. ROOT CAUSE ANALYSIS PROGRAM MANUAL

    E-Print Network [OSTI]

    Gravois, Melanie C.

    2007-01-01T23:59:59.000Z

    It provides a systematic accident analysis tool to aid inanalysis is valuable in understanding the accident and theAccident or Incident Table 4.2 Method Barrier Analysis When

  10. PORTAL Aggregation Analysis and Documentation

    E-Print Network [OSTI]

    Bertini, Robert L.

    PORTAL Aggregation Analysis and Documentation Kristin A. Tufte Portland State University Introduction This document describes the aggregation procedures for PORTAL . Analysis of different aggregation system. Details on the status values and their descriptions can be found in the SWARM documentation

  11. Petroleum County Secondary Data Analysis

    E-Print Network [OSTI]

    Maxwell, Bruce D.

    Petroleum County Secondary Data Analysis July 23, 2012 1 Community Health Data, MT Dept American Diabetes Association (2012) Region 3 (South Central) ­ Judith Basin, Fergus, Petroleum* #12; Petroleum County Secondary Data Analysis July 23, 2012 2 Socioeconomic Measures1

  12. Fusion Engineering and Design 80 (2006) 161180 ARIES-AT maintenance system definition and analysis

    E-Print Network [OSTI]

    California at San Diego, University of

    2006-01-01T23:59:59.000Z

    Fusion Engineering and Design 80 (2006) 161­180 ARIES-AT maintenance system definition and analysis maintenance of the power core. The short core refurbishment time coupled, with evolutionary improvements; Maintenance; Availability; Power core; Vacuum vessel 1. Introduction The ARIES studies, sponsored by DOE

  13. Sandia National Laboratories: Systems Analysis

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

    Photovoltaic, Photovoltaic Systems Evaluation Laboratory (PSEL), Renewable Energy, Solar, Solar Newsletter, Systems Analysis The PV Performance Modeling Collaborative (PVPMC)...

  14. Sandia National Laboratories: Systems Analysis

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

    Grid Integration, Infrastructure Security, Microgrid, News, News & Events, Renewable Energy, Systems Analysis, Systems Engineering, Transmission Grid Integration A lot that...

  15. Sandia National Laboratories: Uncertainty Analysis

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

    Experimental Testing Phenomenological Modeling Risk and Safety Assessment Cyber-Based Vulnerability Assessments Uncertainty Analysis Transportation Safety Fire Science Human...

  16. Sandia National Laboratories: Modeling & Analysis

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

    On September 19, 2013, in Computational Modeling & Simulation, Distribution Grid Integration, Energy, Facilities, Grid Integration, Modeling, Modeling & Analysis, News, News &...

  17. Ontological Analysis P. B. Ladkin

    E-Print Network [OSTI]

    Ladkin, Peter B.

    such as HAZOP or FMEA cannot answer CQ. Ontological Analysis, OA, is a method for developing safety requirements

  18. Scalable Performance Measurement and Analysis

    SciTech Connect (OSTI)

    Gamblin, T

    2009-10-27T23:59:59.000Z

    Concurrency levels in large-scale, distributed-memory supercomputers are rising exponentially. Modern machines may contain 100,000 or more microprocessor cores, and the largest of these, IBM's Blue Gene/L, contains over 200,000 cores. Future systems are expected to support millions of concurrent tasks. In this dissertation, we focus on efficient techniques for measuring and analyzing the performance of applications running on very large parallel machines. Tuning the performance of large-scale applications can be a subtle and time-consuming task because application developers must measure and interpret data from many independent processes. While the volume of the raw data scales linearly with the number of tasks in the running system, the number of tasks is growing exponentially, and data for even small systems quickly becomes unmanageable. Transporting performance data from so many processes over a network can perturb application performance and make measurements inaccurate, and storing such data would require a prohibitive amount of space. Moreover, even if it were stored, analyzing the data would be extremely time-consuming. In this dissertation, we present novel methods for reducing performance data volume. The first draws on multi-scale wavelet techniques from signal processing to compress systemwide, time-varying load-balance data. The second uses statistical sampling to select a small subset of running processes to generate low-volume traces. A third approach combines sampling and wavelet compression to stratify performance data adaptively at run-time and to reduce further the cost of sampled tracing. We have integrated these approaches into Libra, a toolset for scalable load-balance analysis. We present Libra and show how it can be used to analyze data from large scientific applications scalably.

  19. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    IEAB Independent Economic Analysis Board Daniel D. Huppert, Chair Lon L. Peters, Vice-Chair Joel R and Guidance for Economic Analysis in Subbasin Planning Independent Economic Analysis Board January 2003, document IEAB 2003-2 Summary Subbasin planning may need to consider two types of economic issues; 1

  20. Numerical Analysis Gordon K. Smyth

    E-Print Network [OSTI]

    Smyth, Gordon K.

    Numerical Analysis Gordon K. Smyth in Encyclopedia of Biostatistics (ISBN 0471 975761) Edited by Peter Armitage and Theodore Colton John Wiley & Sons, Ltd, Chichester, 1998 #12;Numerical Analysis Numerical analysis is concerned with the accurate and efficient evalua- tion of mathematical expressions

  1. Finite Element Analysis Skateboard Truck

    E-Print Network [OSTI]

    De, Suvranu

    Finite Element Analysis Of a Skateboard Truck #12;2 Executive Summary: Engineering is and always is an element of the `truck,' which holds the wheels. Finite Element analysis will be conducted on this piece a combination of SolidWorks (for modeling) and ABAQUS (for finite element analysis). It is evident from

  2. Beowulf Analysis Symbolic INterface BASIN: Interactive Parallel Data Analysis for Everyone

    E-Print Network [OSTI]

    Enrico Vesperini; David M. Goldberg; Stephen L. W. McMillan; James Dura; Douglas Jones

    2008-04-29T23:59:59.000Z

    The advent of affordable parallel computers such as Beowulf PC clusters and, more recently, of multi-core PCs has been highly beneficial for a large number of scientists and smaller institutions that might not otherwise have access to substantial computing facilities. However, there has not been an analogous progress in the development and dissemination of parallel software: scientists need the expertise to develop parallel codes and have to invest a significant amount of time in the development of tools even for the most common data analysis tasks. We describe the Beowulf Analysis Symbolic INterface (BASIN) a multi-user parallel data analysis and visualization framework. BASIN is aimed at providing scientists with a suite of parallel libraries for astrophysical data analysis along with general tools for data distribution and parallel operations on distributed data to allow them to easily develop new parallel libraries for their specific tasks.

  3. Alternatives Analysis for the Resumption of Transient Testing Program

    SciTech Connect (OSTI)

    Lee Nelson

    2013-11-01T23:59:59.000Z

    An alternatives analysis was performed for resumption of transient testing. The analysis considered eleven alternatives – including both US international facilities. A screening process was used to identify two viable alternatives from the original eleven. In addition, the alternatives analysis includes a no action alternative as required by the National Environmental Policy Act (NEPA). The alternatives considered in this analysis included: 1. Restart the Transient Reactor Test Facility (TREAT) 2. Modify the Annular Core Research Reactor (ACRR) which includes construction of a new hot cell and installation of a new hodoscope. 3. No Action

  4. SMACS. Probabilistic Seismic Analysis System

    SciTech Connect (OSTI)

    Johnson, J.J.; Maslenikov, O.R.; Tiong, L.W.; Mraz, M.J. [EQE Incorporated, San Ramon, CA (United States); Bumpus, S.; Gerhard, M.A. [Lawrence Livermore National Lab., CA (United States)

    1992-01-14T23:59:59.000Z

    The SMACS (Seismic Methodology Analysis Chain with Statistics) system of computer programs is one of the major computational tools of the U.S. NRC Seismic Safety Margins Research Program (SSMRP). SMACS is comprised of the core program SMAX, which performs the SSI response analyses, five preprocessing programs, and two postprocessors. The preprocessing programs include: GLAY and CLAN, which generate the nominal impedance matrices and wave scattering vectors for surface-founded structures; INSSIN, which projects the dynamic properties of structures to the foundation in the form of modal participation factors and mass matrices; SAPPAC, which projects the dynamic and pseudostatic properties of multiply-supported piping systems to the support locations, and LNGEN, which can be used to generate the multiplication factors to be applied to the nominal soil, structural, and subsystem properties for each of the response calculations in accounting for random variations of these properties. The postprocessors are: PRESTO, which performs statistical operations on the raw data from the response vectors that SMAX produces to calculate best fit lognormal distributions for each response location, and CHANGO, which manipulates the data produced by PRESTO to produce other results of interest to the user. Also included is the computer program SAP4 (a modified version of the University of California, Berkeley SAPIV program), a general linear structural analysis program used for eigenvalue extractions and pseudostatic mode calculations of the models of major structures and subsystems. SAP4 is used to prepare input to the INSSIN and SAPPAC preprocessing programs. The GLAY and CLAN programs were originally developed by J.E. Luco (UCSD) and H.L. Wong (USC).

  5. Arundo Donax Analysis Report

    SciTech Connect (OSTI)

    Corrie I. Nichol, Ph.D.; Tyler L. Westover, Ph.D.

    2012-01-01T23:59:59.000Z

    This is a summary report of preliminary analysis conducted on Arundo Donax. Arundo Donax was received from Greenwood Resources via Portland General Electric. PGE plans to transition a coal-fired boiler to 100% biomass by 2020, and has partnered with EPRI and INL to conduct the necessary testing and development to understand what needs to take place to make this transition. Arundo Donax is a promising energy crop for biopower, and is as yet relatively untested and uncharacterized. The INL has begun initial characterization of this material, and this summary report presents the initial findings.

  6. Bus transfer analysis

    SciTech Connect (OSTI)

    Weronick, R.; Hassan, I.D. [Raytheon Engineers and Constructors, Lyndhurst, NJ (United States)

    1996-11-01T23:59:59.000Z

    This paper discusses bus transfer schemes and the methodology used in modeling and analysis. Due to the unavailability of generic acceptance criteria, simulations were performed to analyze the actual fast bus transfer operations at four operating nuclear power generating stations. Sample simulation results illustrating the transient variations in motors currents and torques are included. The analyses were performed to ensure that motors and other rotating parts are not subjected to excessive or accumulated stresses caused by bus transfer operations. A summary of the experience gained in the process of performing this work and suggested bus transfer acceptance criteria are also presented.

  7. Drift Degradation Analysis

    SciTech Connect (OSTI)

    D. Kicker

    2004-09-16T23:59:59.000Z

    Degradation of underground openings as a function of time is a natural and expected occurrence for any subsurface excavation. Over time, changes occur to both the stress condition and the strength of the rock mass due to several interacting factors. Once the factors contributing to degradation are characterized, the effects of drift degradation can typically be mitigated through appropriate design and maintenance of the ground support system. However, for the emplacement drifts of the geologic repository at Yucca Mountain, it is necessary to characterize drift degradation over a 10,000-year period, which is well beyond the functional period of the ground support system. This document provides an analysis of the amount of drift degradation anticipated in repository emplacement drifts for discrete events and time increments extending throughout the 10,000-year regulatory period for postclosure performance. This revision of the drift degradation analysis was developed to support the license application and fulfill specific agreement items between the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Energy (DOE). The earlier versions of ''Drift Degradation Analysis'' (BSC 2001 [DIRS 156304]) relied primarily on the DRKBA numerical code, which provides for a probabilistic key-block assessment based on realistic fracture patterns determined from field mapping in the Exploratory Studies Facility (ESF) at Yucca Mountain. A key block is defined as a critical block in the surrounding rock mass of an excavation, which is removable and oriented in an unsafe manner such that it is likely to move into an opening unless support is provided. However, the use of the DRKBA code to determine potential rockfall data at the repository horizon during the postclosure period has several limitations: (1) The DRKBA code cannot explicitly apply dynamic loads due to seismic ground motion. (2) The DRKBA code cannot explicitly apply loads due to thermal stress. (3) The DRKBA code, which determines structurally controlled key-block failure, is not applicable for stress-controlled failure in the lithophysal units. To address these limitations, additional numerical codes have been included that can explicitly apply seismic and thermal loads, providing significant improvements to the analysis of drift degradation and extending the validity of drift degradation models.

  8. Analysis5_.PDF

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for On-Highway4,1,50022,3,,,,6,1,9,1,50022,3,,,,6,1,Decade Year-0E (2001)gasoline prices4 OilU.S. OffshoreOil andEnergyAnalysis

  9. NREL Sustainability Analysis

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin of Contamination in Many Devils Wash,Energy NREL Job Task Analysis:Energy

  10. Analysis of Geothermal Reservoir Stimulation using Geomechanics...

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

    using Geomechanics-Based Stochastic Analysis of Injection-Induced Seismicity Analysis of Geothermal Reservoir Stimulation using Geomechanics-Based Stochastic Analysis of...

  11. Advanced Coal Wind Hybrid: Economic Analysis

    E-Print Network [OSTI]

    Phadke, Amol

    2008-01-01T23:59:59.000Z

    Coal Wind Hybrid: Economic Analysis additional cost of fuelWind Hybrid: Economic Analysis Levelized Generation CostCoal Wind Hybrid: Economic Analysis Notes: All Cost are in

  12. Geographically Based Hydrogen Demand and Infrastructure Analysis...

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

    Analysis Geographically Based Hydrogen Demand and Infrastructure Analysis Presentation by NREL's Margo Melendez at the 2010 - 2025 Scenario Analysis for Hydrogen Fuel Cell Vehicles...

  13. Sandia Energy - Transportation Energy Systems Analysis

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

    Transportation Energy Systems Analysis Home Transportation Energy Predictive Simulation of Engines Transportation Energy Systems Analysis Transportation Energy Systems AnalysisTara...

  14. Decision Analysis for EGS | Department of Energy

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

    Decision Analysis for EGS Decision Analysis for EGS Project objectives: DEVELOPMENT OF ANALYSIS TOOLS TO ASSESS: Uncertainties associated with exploration for EGS; Uncertainties...

  15. Final Report - Hydrogen Delivery Infrastructure Options Analysis...

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

    - Hydrogen Delivery Infrastructure Options Analysis Final Report - Hydrogen Delivery Infrastructure Options Analysis This report, by the Nexant team, documents an in-depth analysis...

  16. Suggestions for Functional Analysis Basics (FAB) Seminar

    E-Print Network [OSTI]

    2014-08-14T23:59:59.000Z

    Aug 14, 2014 ... Page 1 ... Functional analysis is a central topic in analysis at an advanced level and is at the foundation of many parts of analysis, including ...

  17. Climate Analysis The central theme of the Climate Analysis Division is the analysis and

    E-Print Network [OSTI]

    Haak, Hein

    Climate Analysis The central theme of the Climate Analysis Division is the analysis and diagnosis of the climate and its variability on the basis of observations and models. The objective of this research of climate change scenarios for impact studies using downscaling techniques. The research can be summarised

  18. Crude Oil Analysis Database

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

    Shay, Johanna Y.

    The composition and physical properties of crude oil vary widely from one reservoir to another within an oil field, as well as from one field or region to another. Although all oils consist of hydrocarbons and their derivatives, the proportions of various types of compounds differ greatly. This makes some oils more suitable than others for specific refining processes and uses. To take advantage of this diversity, one needs access to information in a large database of crude oil analyses. The Crude Oil Analysis Database (COADB) currently satisfies this need by offering 9,056 crude oil analyses. Of these, 8,500 are United States domestic oils. The database contains results of analysis of the general properties and chemical composition, as well as the field, formation, and geographic location of the crude oil sample. [Taken from the Introduction to COAMDATA_DESC.pdf, part of the zipped software and database file at http://www.netl.doe.gov/technologies/oil-gas/Software/database.html] Save the zipped file to your PC. When opened, it will contain PDF documents and a large Excel spreadsheet. It will also contain the database in Microsoft Access 2002.

  19. LOFA and LOCA analysis on CGNPC SCWR

    SciTech Connect (OSTI)

    Wu, P.; Gou, J.; Shan, J.; Jiang, Y.; Zhang, B. [Xi'an Jiaotong Univ., No.28, Xianning West Road, Xi'an, Shaanxi Province (China); Yang, J. [China Nuclear Power Technology Research Inst., Jiangsu Building, Yitian road, Shenzhen, Guangdong Province (China)

    2012-07-01T23:59:59.000Z

    Safety analysis is one of the chief difficulties during the research and design of SCWRs. At present, the development of SCWR safety analysis code is still in the initial stage all around the world, and very few computer codes could carry out trans-critical calculations where significant changes in water properties would take place. In this paper, a safety analysis code SCTRAN for SCWRs, has been developed based on RETRAN-02. The ability of SCTRAN code to simulate the transient where both supercritical and subcritical regimes are encountered has been verified by comparing with APROS code and RELAP5-3D code, respectively. With SCTRAN code, the preliminary LOFA and LOCA analysis of the SCWR design proposed by CGNPC, have been analyzed. The characteristics and performance of the passive safety systems applied to CGNPC-SCWR are evaluated. The results show that: 1) The SCTRAN computer code developed in this study is capable to carry out safety analysis for SCWRs, and its results are reliable; 2) During LOFA and LOCA accidents, very complex flow regime might take place in the double-pass core design, but the passive safety systems would greatly mitigate the consequences of these transients and increase the inherent safety. (authors)

  20. Hypothesis analysis methods, hypothesis analysis devices, and articles of manufacture

    DOE Patents [OSTI]

    Sanfilippo, Antonio P. (Richland, WA); Cowell, Andrew J. (Kennewick, WA); Gregory, Michelle L. (Richland, WA); Baddeley, Robert L. (Richland, WA); Paulson, Patrick R. (Pasco, WA); Tratz, Stephen C. (Richland, WA); Hohimer, Ryan E. (West Richland, WA)

    2012-03-20T23:59:59.000Z

    Hypothesis analysis methods, hypothesis analysis devices, and articles of manufacture are described according to some aspects. In one aspect, a hypothesis analysis method includes providing a hypothesis, providing an indicator which at least one of supports and refutes the hypothesis, using the indicator, associating evidence with the hypothesis, weighting the association of the evidence with the hypothesis, and using the weighting, providing information regarding the accuracy of the hypothesis.

  1. Abductive Analysis of Modular Logic Programs

    E-Print Network [OSTI]

    Giacobazzi, Roberto

    Abductive Analysis of Modular Logic Programs Roberto Giacobazzi LIX, Laboratoire d introduce a practical method for abductive analysis of modular logic programs. This is obtained of abductive reasoning in dataflow analysis of logic programs. 1 Introduction Dataflow analysis

  2. Stretch Efficiency - Thermodynamic Analysis of New Combustion...

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

    Stretch Efficiency - Thermodynamic Analysis of New Combustion Regimes (Agreement 10037) Stretch Efficiency - Thermodynamic Analysis of New Combustion Regimes (Agreement 10037)...

  3. Transcriptional analysis of the unicellular, diazotrophic cyanobacteri...

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

    analysis of the unicellular, diazotrophic cyanobacterium Cyanothece sp. ATCC 51142 grown under short daynight Transcriptional analysis of the unicellular, diazotrophic...

  4. Technoeconomic Analysis of Photoelectrochemical (PEC) Hydrogen...

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

    Analysis of Photoelectrochemical (PEC) Hydrogen Production Technoeconomic Analysis of Photoelectrochemical (PEC) Hydrogen Production This report documents the engineering and cost...

  5. Hydrogen Production Infrastructure Options Analysis | Department...

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

    Infrastructure Options Analysis Hydrogen Production Infrastructure Options Analysis Presentation on hydrogen production and infrastructure options presented at the DOE Transition...

  6. Analysis Activities at Idaho National Engineering & Environmental...

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

    Analysis Activities at Idaho National Engineering & Environmental Laboratory Analysis Activities at Idaho National Engineering & Environmental Laboratory Presentation on INEENL's...

  7. Updated Cost Analysis of Photobiological Hydrogen Production...

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

    Analysis of Photobiological Hydrogen Production from Chlamydomonas reinhardtii Green Algae: Milestone Completion Report Updated Cost Analysis of Photobiological Hydrogen...

  8. Ultrasound Analysis of Slurries

    DOE Patents [OSTI]

    Soong, Yee and Blackwell, Arthur G.

    2005-11-01T23:59:59.000Z

    An autoclave reactor allows for the ultrasonic analysis of slurry concentration and particle size distribution at elevated temperatures and pressures while maintaining the temperature- and pressure-sensitive ultrasonic transducers under ambient conditions. The reactor vessel is a hollow stainless steel cylinder containing the slurry which includes a stirrer and a N, gas source for directing gas bubbles through the slurry. Input and output transducers are connected to opposed lateral portions of the hollow cylinder for respectively directing sound waves through the slurry and receiving these sound waves after transmission through the slurry, where changes in sound wave velocity and amplitude can be used to measure slurry parameters. Ultrasonic adapters connect the transducers to the reactor vessel in a sealed manner and isolate the transducers from the hostile conditions within the vessel without ultrasonic signal distortion or losses.

  9. Certification/enforcement analysis

    SciTech Connect (OSTI)

    None

    1980-06-01T23:59:59.000Z

    Industry compliance with minimum energy efficiency standards will be assured through a two-part program approach of certification and enforcement activities. The technical support document (TSD) presents the analyses upon which the proposed rule for assuring that consumer product comply with applicable energy efficiency standards is based. Much of the TSD is based upon support provided DOE by Vitro Laboratories. The OAO Corporation provided additional support in the development of the sampling plan incorporated in the proposed rule. Vitro's recommended approach to appliance certification and enforcement, developed after consideration of various program options, benefits, and impacts, establishes the C/E program framework, general criteria, and procedures for assuring a specified level of energy efficiency performance of covered consumer products. The results of the OAO analysis are given in Volume II of the TSD.

  10. Capacitor discharge pulse analysis.

    SciTech Connect (OSTI)

    Baker, Michael Sean; Griffiths, Stewart K.; Tanner, Danelle Mary

    2013-08-01T23:59:59.000Z

    Capacitors used in firing sets and other high discharge current applications are discharge tested to verify performance of the capacitor against the application requirements. Parameters such as capacitance, inductance, rise time, pulse width, peak current and current reversal must be verified to ensure that the capacitor will meet the application needs. This report summarizes an analysis performed on the discharge current data to extract these parameters by fitting a second-order system model to the discharge data and using this fit to determine the resulting performance metrics. Details of the theory and implementation are presented. Using the best-fit second-order system model to extract these metrics results in less sensitivity to noise in the measured data and allows for direct extraction of the total series resistance, inductance, and capacitance.

  11. Ultrasound Analysis Of Slurries

    DOE Patents [OSTI]

    Soong, Yee (Monroeville, PA); Blackwell, Arthur G. (Duquesne, PA)

    2005-11-01T23:59:59.000Z

    An autoclave reactor allows for the ultrasonic analysis of slurry concentration and particle size distribution at elevated temperatures and pressures while maintaining the temperature- and pressure-sensitive ultrasonic transducers under ambient conditions. The reactor vessel is a hollow stainless steel cylinder containing the slurry which includes a stirrer and a N.sub.2 gas source for directing gas bubbles through the slurry. Input and output transducers are connected to opposed lateral portions of the hollow cylinder for respectively directing sound waves through the slurry and receiving these sound waves after transmission through the slurry, where changes in sound wave velocity and amplitude can be used to measure slurry parameters. Ultrasonic adapters connect the transducers to the reactor vessel in a sealed manner and isolate the transducers from the hostile conditions within the vessel without ultrasonic signal distortion or losses.

  12. Accident tolerant fuel analysis

    SciTech Connect (OSTI)

    Smith, Curtis [Idaho National Laboratory; Chichester, Heather [Idaho National Laboratory; Johns, Jesse [Texas A& M University; Teague, Melissa [Idaho National Laboratory; Tonks, Michael Idaho National Laboratory; Youngblood, Robert [Idaho National Laboratory

    2014-09-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced ''RISMC toolkit'' that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional ''accident-tolerant'' (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  13. Accident Tolerant Fuel Analysis

    SciTech Connect (OSTI)

    Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood

    2014-09-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  14. Chemical process hazards analysis

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    The Office of Worker Health and Safety (EH-5) under the Assistant Secretary for the Environment, Safety and Health of the US Department (DOE) has published two handbooks for use by DOE contractors managing facilities and processes covered by the Occupational Safety and Health Administration (OSHA) Rule for Process Safety Management of Highly Hazardous Chemicals (29 CFR 1910.119), herein referred to as the PSM Rule. The PSM Rule contains an integrated set of chemical process safety management elements designed to prevent chemical releases that can lead to catastrophic fires, explosions, or toxic exposures. The purpose of the two handbooks, ``Process Safety Management for Highly Hazardous Chemicals`` and ``Chemical Process Hazards Analysis,`` is to facilitate implementation of the provisions of the PSM Rule within the DOE. The purpose of this handbook ``Chemical Process Hazards Analysis,`` is to facilitate, within the DOE, the performance of chemical process hazards analyses (PrHAs) as required under the PSM Rule. It provides basic information for the performance of PrHAs, and should not be considered a complete resource on PrHA methods. Likewise, to determine if a facility is covered by the PSM rule, the reader should refer to the handbook, ``Process Safety Management for Highly Hazardous Chemicals`` (DOE- HDBK-1101-96). Promulgation of the PSM Rule has heightened the awareness of chemical safety management issues within the DOE. This handbook is intended for use by DOE facilities and processes covered by the PSM rule to facilitate contractor implementation of the PrHA element of the PSM Rule. However, contractors whose facilities and processes not covered by the PSM Rule may also use this handbook as a basis for conducting process hazards analyses as part of their good management practices. This handbook explains the minimum requirements for PrHAs outlined in the PSM Rule. Nowhere have requirements been added beyond what is specifically required by the rule.

  15. Semi-classical signal analysis

    E-Print Network [OSTI]

    Taous-Meriem Laleg-Kirati; Emmanuelle Crépeau; Michel Sorine

    2010-07-06T23:59:59.000Z

    This study introduces a new signal analysis method called SCSA, based on a semi-classical approach. The main idea in the SCSA is to interpret a pulse-shaped signal as a potential of a Schr\\"odinger operator and then to use the discrete spectrum of this operator for the analysis of the signal. We present some numerical examples and the first results obtained with this method on the analysis of arterial blood pressure waveforms.

  16. Sandia National Laboratories: Modeling & Analysis

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

    Mark Boslough Featured in NOVA Special about the Chelyabinsk Meteor On April 3, 2013, in Capabilities, Computational Modeling & Simulation, Modeling, Modeling, Modeling & Analysis,...

  17. Sandia National Laboratories: Modeling & Analysis

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

    Sandian Mark Boslough Featured on NOVA Episode about Chelyabinsk Meteor On November 20, 2013, in Computational Modeling & Simulation, Modeling, Modeling, Modeling & Analysis,...

  18. Virtual data in CMS analysis

    SciTech Connect (OSTI)

    A. Arbree et al.

    2003-10-01T23:59:59.000Z

    The use of virtual data for enhancing the collaboration between large groups of scientists is explored in several ways: by defining ''virtual'' parameter spaces which can be searched and shared in an organized way by a collaboration of scientists in the course of their analysis; by providing a mechanism to log the provenance of results and the ability to trace them back to the various stages in the analysis of real or simulated data; by creating ''check points'' in the course of an analysis to permit collaborators to explore their own analysis branches by refining selections, improving the signal to background ratio, varying the estimation of parameters, etc.; by facilitating the audit of an analysis and the reproduction of its results by a different group, or in a peer review context. We describe a prototype for the analysis of data from the CMS experiment based on the virtual data system Chimera and the object-oriented data analysis framework ROOT. The Chimera system is used to chain together several steps in the analysis process including the Monte Carlo generation of data, the simulation of detector response, the reconstruction of physics objects and their subsequent analysis, histogramming and visualization using the ROOT framework.

  19. Virtual Crosswalk Analysis Tool (VCAT)

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

    synthesized from ideas in functional analysis, business process modeling, and complex network science. VCAT discovers synergies by analyzing natural language descriptions....

  20. Chapter 16: Environmental Impact Analysis

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

    or gases a . This analysis also considers carbon dioxide (CO 2 ). a More information on air pollution characteristics and regulations is available on the U.S. Environment...

  1. Power network analysis and optimization

    E-Print Network [OSTI]

    Zhang, Wanping

    2009-01-01T23:59:59.000Z

    chip power supply network optimization using multigrid-basedchip decoupling capacitor optimization for high- performanceSapatnekar, “Analysis and optimization of structured power/

  2. Biomass Rapid Analysis Network (BRAN)

    SciTech Connect (OSTI)

    Not Available

    2003-10-01T23:59:59.000Z

    Helping the emerging biotechnology industry develop new tools and methods for real-time analysis of biomass feedstocks, process intermediates and The Biomass Rapid Analysis Network is designed to fast track the development of modern tools and methods for biomass analysis to accelerate the development of the emerging industry. The network will be led by industry and organized and coordinated through the National Renewable Energy Lab. The network will provide training and other activities of interest to BRAN members. BRAN members will share the cost and work of rapid analysis method development, validate the new methods, and work together to develop the training for the future biomass conversion workforce.

  3. "Charter and Code" Gap Analysis ANALYSIS FOR NORWAY

    E-Print Network [OSTI]

    Johansen, Tom Henning

    "Charter and Code" ­ Gap Analysis ANALYSIS FOR NORWAY The European Charter for Researchers: Acceptable. The principle of research freedom is well-established in Norway. The committee refers for Research Ethics in Norway. #12;In recent years, issues of research ethics have received increasing

  4. Text analysis devices, articles of manufacture, and text analysis methods

    DOE Patents [OSTI]

    Turner, Alan E; Hetzler, Elizabeth G; Nakamura, Grant C

    2013-05-28T23:59:59.000Z

    Text analysis devices, articles of manufacture, and text analysis methods are described according to some aspects. In one aspect, a text analysis device includes processing circuitry configured to analyze initial text to generate a measurement basis usable in analysis of subsequent text, wherein the measurement basis comprises a plurality of measurement features from the initial text, a plurality of dimension anchors from the initial text and a plurality of associations of the measurement features with the dimension anchors, and wherein the processing circuitry is configured to access a viewpoint indicative of a perspective of interest of a user with respect to the analysis of the subsequent text, and wherein the processing circuitry is configured to use the viewpoint to generate the measurement basis.

  5. DNDO Analysis Cell Concept

    SciTech Connect (OSTI)

    Pagh, Richard T.; Dimmerling, Paul J.; Guillen, Zoe C.; Hoyt, Joel R.; Jarman, Kenneth D.; Kernan, Warnick J.; Reichmuth, Barbara A.; Rohlfing, Kerrie S.; Schweppe, John E.; Sego, Landon H.; Shergur, Jason M.; Siciliano, Edward R.; Woodring, Mitchell L.

    2014-03-12T23:59:59.000Z

    The Domestic Nuclear Detection Office (DNDO) has a mission of implementing rad/nuc interdiction capabilities for a managed and coordinated response to threats, integration of federal nuclear forensics programs, and coordinating the development of the global nuclear detection and reporting architecture. In the process of executing this mission, DNDO has generated substantial information, data, technical results, operational workflows and analytical tools. The effective utilization of these resources is an overarching goal of the organization. After nearly a decade of performing work, DNDO faces a challenge in capitalizing on the large amount of data, reports, processes, tools, and people. As new work is being planned, managers and researchers need to have an understating of what information has been collected, what tools are available, the collaborations which can be utilized to propel the work forward, processes to plan and execute, and how to present conclusions and results that can assist the government in making decisions. This type of challenge can be met through the use of a series of organized and connected elements which form a broader structure (cell) that promotes cross utilization of elements such that they can be tailored (analyzed) to fit the context of the problem to be solved. The development of an analysis cell for DNDO will address the challenges of utilizing existing elements, identifying gaps, annually reporting the performance of rad/nuc interdiction instrumentation, and planning the execution of future work.

  6. Frequency Response Analysis Tool

    SciTech Connect (OSTI)

    Etingov, Pavel V.; Kosterev, Dmitry; Dai, T.

    2014-12-31T23:59:59.000Z

    Frequency response has received a lot of attention in recent years at the national level, which culminated in the development and approval of North American Electricity Reliability Corporation (NERC) BAL-003-1 Frequency Response and Frequency Bias Setting Reliability Standard. This report is prepared to describe the details of the work conducted by Pacific Northwest National Laboratory (PNNL) in collaboration with the Bonneville Power Administration and Western Electricity Coordinating Council (WECC) Joint Synchronized Information Subcommittee (JSIS) to develop a frequency response analysis tool (FRAT). The document provides the details on the methodology and main features of the FRAT. The tool manages the database of under-frequency events and calculates the frequency response baseline. Frequency response calculations are consistent with frequency response measure (FRM) in NERC BAL-003-1 for an interconnection and balancing authority. The FRAT can use both phasor measurement unit (PMU) data, where available, and supervisory control and data acquisition (SCADA) data. The tool is also capable of automatically generating NERC Frequency Response Survey (FRS) forms required by BAL-003-1 Standard.

  7. Structural Analysis of Combustion Models

    E-Print Network [OSTI]

    Tóth, J; Zsély, I

    2013-01-01T23:59:59.000Z

    Using ReactionKinetics, a Mathematica based package a few dozen detailed models for combustion of hydrogen, carbon monoxide and methanol are investigated. Essential structural characteristics are pulled out, and similarities and differences of the mechanisms are highlighted. These investigations can be used before or parallel with usual numerical investigations, such as pathway analysis, sensitivity analysis, parameter estimation, or simulation.

  8. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    IEAB Independent Economic Analysis Board Kenneth L. Casavant, Chair Roger Mann, Vice-Chair Joel R of Independent Economic Analysis Board's Activities and Contributions to NPPC Fish and Wildlife Planning document of achieving the same sound biological objective exist, the alternative with the minimum economic cost

  9. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    IEAB Independent Economic Analysis Board Daniel D. Huppert, Chair Lon L. Peters, Vice-Chair Joel R. Hamilton Kenneth L. Casavant Jack A. Richards Roger Mann Paul C. Sorensen Hans Radtke Economic Review of Instream Water Supply Components of the Salmon Creek Project Independent Economic Analysis Board Northwest

  10. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    IEAB Independent Economic Analysis Board Roger Mann, Chair Noelwah R. Netusil, Vice-Chair Kenneth L. Casavant Daniel D. Huppert Joel R. Hamilton Lon L. Peters Susan S. Hanna Hans Radtke A I - 1 Economic Effects From Columbia River Basin Anadromous Salmonid Fish Production Independent Economic Analysis Board

  11. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    IEAB Independent Economic Analysis Board Hans Radtke, Chair Roger Mann, Vice-Chair Daniel D. Huppert Joel R. Hamilton Susan S. Hanna John Duffield Noelwah R. Netusil Independent Economic Analysis Board Task Number 139 Integrated Hatchery Operations: Fish and Wildlife Program Costs and Other Economic

  12. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    IEAB Independent Economic Analysis Board Kenneth L. Casavant, Chair Roger Mann, Vice-Chair Joel R Application of the IEAB's Recommendations and Guidance for Economic Analysis in Subbasin Planning improvements related to economic content of the draft Clearwater Subbasin Management Plan (the draft Clearwater

  13. Sentiment Analysis and Opinion Mining

    E-Print Network [OSTI]

    Plotkin, Joshua B.

    Sentiment Analysis and Opinion Mining Bing Liu Department of Computer Science University Mining Morgan & Claypool Publishers, May 2012. #12;Bing Liu @ AAAI-2011, Aug. 8, 2011, San Francisco, USA 2 Introduction Opinion mining or sentiment analysis Computational study of opinions, sentiments

  14. Thyristor converter simulation and analysis

    SciTech Connect (OSTI)

    Zhang, S.Y.

    1991-01-01T23:59:59.000Z

    In this paper we present a simulation on thyristor converters. The simulation features nonlinearity, non-uniform firing, and the commutations. Several applications such as a current regulation, a converter frequency characteristics analysis, and a power line disturbance analysis will be presented. 4 refs., 4 figs.

  15. PITTSBURGH REGIONAL ENVIRONMENTAL THREATS ANALYSIS

    E-Print Network [OSTI]

    Jiang, Huiqiang

    AND COMMUNITIES PITTSBURGH, PA. | AUGUST 2013 #12;PRETA AIR: HAZARDOUS AIR POLLUTANTS 32 PITTSBURGH REGIONAL ENVIRONMENTAL THREATS ANALYSIS REPORT PRETA AIR: HAZARDOUS AIR POLLUTANTS (HAPs)/AIR TOXICS PREPARED BY AUTHORSPITTSBURGH REGIONAL ENVIRONMENTAL THREATS ANALYSIS (PRETA) REPORT PRETA AIR: HAZARDOUS AIR

  16. VCAT: Visual Crosswalk Analysis Tool

    SciTech Connect (OSTI)

    Cleland, Timothy J. [Los Alamos National Laboratory; Forslund, David W. [Los Alamos National Laboratory; Cleland, Catherine A. [Los Alamos National Laboratory

    2012-08-31T23:59:59.000Z

    VCAT is a knowledge modeling and analysis tool. It was synthesized from ideas in functional analysis, business process modeling, and complex network science. VCAT discovers synergies by analyzing natural language descriptions. Specifically, it creates visual analytic perspectives that capture intended organization structures, then overlays the serendipitous relationships that point to potential synergies within an organization or across multiple organizations.

  17. Granite County Secondary Data Analysis

    E-Print Network [OSTI]

    Maxwell, Bruce D.

    Granite County Secondary Data Analysis July 23, 2012 1 1 Community Health Data, MT Dept (CDC) (2012) 4 American Diabetes Association (2012) Region 4 (Southwest) ­ Lewis and Clark, Granite. CLRD* #12; Granite County Secondary Data Analysis July 23, 2012 2 Socioeconomic Measures1

  18. NUMERICAL ANALYSIS KENDALL E. ATKINSON

    E-Print Network [OSTI]

    Atkinson, Kendall

    of mathematics and computer science that creates, analyzes, and implements algorithms for solving nu- merically mathematical models in science and engineering, and numerical analysis of increasing sophistication has been of numerical analysis varies from quite theoretical mathematical studies (e.g. see [5]) to computer science

  19. Canonical Analysis of Unimodular Gravity

    E-Print Network [OSTI]

    J. Kluson

    2014-10-07T23:59:59.000Z

    This short note is devoted to the Hamiltonian analysis of the Unimodular Gravity.We treat the unimodular gravity as General Relativity action with the unimodular constraint imposed with the help of Lagrange multiplier. We perform the canonical analysis of the resulting theory and determine its constraint structure.

  20. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    Snake dams. The Corps EIS set a high standard as an open, public and peer reviewed analysis that has in the Corps of Engineers Lower Snake EIS in 2000. This is crucial, because the cost of replacement power. The Revenue Stream report is not a peer reviewed analysis, the work was not conducted by an open public

  1. Groundwater Data Analysis Lalit Kumar

    E-Print Network [OSTI]

    Sohoni, Milind

    Groundwater Data Analysis Lalit Kumar (10305073) Guide: Prof. Milind Sohoni Department of Computer BombayGroundwater Data Analysis Oct 25, 2011 1 / 23 #12;Outline Motivation Objective Terminology Case Sohoni (Department of Computer Science and EngineeringIndian Institute of Technology BombayGroundwater

  2. TECH REPORT Enrichment analysis of

    E-Print Network [OSTI]

    Chait, Brian T.

    TECH REPORT Enrichment analysis of phosphorylated proteins as a tool for probing of relatively abundant proteins2,3. Therefore, for effective proteome analysis it becomes critical to enrich substrates can be greatly enhanced by enriching the sample of phosphorylated proteins. Although enrichment

  3. Preliminary Analysis of the BASALA-H Experimental Programme

    SciTech Connect (OSTI)

    Blaise, Patrick; Fougeras, Philippe; Philibert, Herve; Laval, Valerie; Perret, Gregory [Commissariat a l'Energie Atomique - CEA Cadarache, 13108 St. Paul lez Durance Cedex (France)

    2002-07-01T23:59:59.000Z

    This paper is focused on the preliminary analysis of results obtained on the first cores of the first phase of the BASALA (Boiling water reactor Advanced core physics Study Aimed at mox fuel Lattice) programme, aimed at studying the neutronic parameters in ABWR core in hot conditions, currently under investigation in the French EOLE critical facility, within the framework of a cooperation between NUPEC, CEA and Cogema. The first 'on-line' analysis of the results has been made, using a new preliminary design and safety scheme based on the French APOLLO-2 code in its 2.4 qualified version and associated CEA-93 V4 (JEF-2.2) Library, that will enable the Experimental Physics Division (SPEx) to perform future core designs. It describes the scheme adopted and the results obtained in various cases, going to the critical size determination to the reactivity worth of the perturbed configurations (voided, over-moderated, and poisoned with Gd{sub 2}O{sub 3}-UO{sub 2} pins). A preliminary study on the experimental results on the MISTRAL-4 is resumed, and the comparison of APOLLO-2 versus MCNP-4C calculations on these cores is made. The results obtained show very good agreements between the two codes, and versus the experiment. This work opens the way to the future full analysis of the experimental results of the qualifying teams with completely validated schemes, based on the new 2.5 version of the APOLLO-2 code. (authors)

  4. Miniaturized flow injection analysis system

    DOE Patents [OSTI]

    Folta, James A. (Livermore, CA)

    1997-01-01T23:59:59.000Z

    A chemical analysis technique known as flow injection analysis, wherein small quantities of chemical reagents and sample are intermixed and reacted within a capillary flow system and the reaction products are detected optically, electrochemically, or by other means. A highly miniaturized version of a flow injection analysis system has been fabricated utilizing microfabrication techniques common to the microelectronics industry. The microflow system uses flow capillaries formed by etching microchannels in a silicon or glass wafer followed by bonding to another wafer, commercially available microvalves bonded directly to the microflow channels, and an optical absorption detector cell formed near the capillary outlet, with light being both delivered and collected with fiber optics. The microflow system is designed mainly for analysis of liquids and currently measures 38.times.25.times.3 mm, but can be designed for gas analysis and be substantially smaller in construction.

  5. APPLICATIONS OF FOURIER ANALYSIS TO NON-ANALYTIC Abstract. Fourier analysis, a classical topic in analysis, can be applied to

    E-Print Network [OSTI]

    May, J. Peter

    APPLICATIONS OF FOURIER ANALYSIS TO NON-ANALYTIC FIELDS KEVIN QIAN Abstract. Fourier analysis, a classical topic in analysis, can be applied to many nonanalytic fields. This paper explores Fourier analysis in multiple do- mains in order to prove several nonanalytic results. Fourier analysis will be explored

  6. Infrastructure Analysis Tools: A Focus on Cash Flow Analysis (Presentation)

    SciTech Connect (OSTI)

    Melaina, M.; Penev, M.

    2012-09-01T23:59:59.000Z

    NREL has developed and maintains a variety of infrastructure analysis models for the U.S. Department of Energy. Business case analysis has recently been added to this tool set. This presentation focuses on cash flow analysis. Cash flows depend upon infrastructure costs, optimized spatially and temporally, and assumptions about financing and revenue. NREL has incorporated detailed metrics on financing and incentives into the models. Next steps in modeling include continuing to collect feedback on regional/local infrastructure development activities and 'roadmap' dynamics, and incorporating consumer preference assumptions on infrastructure to provide direct feedback between vehicles and station rollout.

  7. SYNTHESIS OF SAFETY ANALYSIS AND FIRE HAZARD ANALYSIS METHODOLOGIES

    SciTech Connect (OSTI)

    Coutts, D

    2007-04-17T23:59:59.000Z

    Successful implementation of both the nuclear safety program and fire protection program is best accomplished using a coordinated process that relies on sound technical approaches. When systematically prepared, the documented safety analysis (DSA) and fire hazard analysis (FHA) can present a consistent technical basis that streamlines implementation. If not coordinated, the DSA and FHA can present inconsistent conclusions, which can create unnecessary confusion and can promulgate a negative safety perception. This paper will compare the scope, purpose, and analysis techniques for DSAs and FHAs. It will also consolidate several lessons-learned papers on this topic, which were prepared in the 1990s.

  8. SPECTRAL ANALYSIS OF RADIOXENON

    SciTech Connect (OSTI)

    Cooper, Matthew W.; Bowyer, Ted W.; Hayes, James C.; Heimbigner, Tom R.; Hubbard, Charles W.; McIntyre, Justin I.; Schrom, Brian T.

    2008-09-23T23:59:59.000Z

    Monitoring changes in atmospheric radioxenon concentrations is a major tool in the detection of an underground nuclear explosion. Ground based systems like the Automated Radioxenon Sampler /Analyzer (ARSA), the Swedish Unattended Noble gas Analyzer (SAUNA) and the Automatic portable radiometer of isotopes Xe (ARIX), can collect and detect several radioxenon isotopes by processing and transferring samples into a high efficiency beta-gamma coincidence detector. The high efficiency beta-gamma coincidence detector makes these systems highly sensitive to the radioxenon isotopes 133Xe, 131mXe, 133mXe and 135Xe. The standard analysis uses regions of interest (ROI) to determine the amount of a particular radioxenon isotope present. The ROI method relies on the peaks of interest falling within energy limits of the ROI. Some potential problems inherent in this method are the reliance on stable detector gains and a fixed resolution for each energy peak. In addition, when a high activity sample is measured there will be more interference among the ROI, in particular within the 133Xe, 133mXe, and 131mXe regions. A solution to some of these problems can be obtained through spectral fitting of the data. Spectral fitting is simply the fitting of the peaks using known functions to determine the number and relative peak positions and widths. By knowing this information it is possible to determine which isotopes are present. Area under each peak can then be used to determine an overall concentration for each isotope. Using the areas of the peaks several key detector characteristics can be determined: efficiency, energy calibration, energy resolution and ratios between interfering isotopes (Radon daughters).

  9. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices A--D. Volume 2, Part 2

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P. [Brookhaven National Lab., Upton, NY (United States)] [and others

    1994-06-01T23:59:59.000Z

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the Potential risks during low Power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the Plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful. This document, Volume 2, Pt. 2 provides appendices A through D of this report.

  10. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices E (Sections E.1--E.8). Volume 2, Part 3A

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P. [Brookhaven National Lab., Upton, NY (United States)] [and others

    1994-06-01T23:59:59.000Z

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. The authors recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful.

  11. Liquid Effluents Program mission analysis

    SciTech Connect (OSTI)

    Lowe, S.S.

    1994-09-27T23:59:59.000Z

    Systems engineering is being used to identify work to cleanup the Hanford Site. The systems engineering process transforms an identified mission need into a set of performance parameters and a preferred system configuration. Mission analysis is the first step in the process. Mission analysis supports early decision-making by clearly defining the program objectives, and evaluating the feasibility and risks associated with achieving those objectives. The results of the mission analysis provide a consistent basis for subsequent systems engineering work. A mission analysis was performed earlier for the overall Hanford Site. This work was continued by a ``capstone`` team which developed a top-level functional analysis. Continuing in a top-down manner, systems engineering is now being applied at the program and project levels. A mission analysis was conducted for the Liquid Effluents Program. The results are described herein. This report identifies the initial conditions and acceptable final conditions, defines the programmatic and physical interfaces and sources of constraints, estimates the resources to carry out the mission, and establishes measures of success. The mission analysis reflects current program planning for the Liquid Effluents Program as described in Liquid Effluents FY 1995 Multi-Year Program Plan.

  12. Radiation analysis devices, radiation analysis methods, and articles of manufacture

    DOE Patents [OSTI]

    Roybal, Lyle Gene

    2010-06-08T23:59:59.000Z

    Radiation analysis devices include circuitry configured to determine respective radiation count data for a plurality of sections of an area of interest and combine the radiation count data of individual of sections to determine whether a selected radioactive material is present in the area of interest. An amount of the radiation count data for an individual section is insufficient to determine whether the selected radioactive material is present in the individual section. An article of manufacture includes media comprising programming configured to cause processing circuitry to perform processing comprising determining one or more correction factors based on a calibration of a radiation analysis device, measuring radiation received by the radiation analysis device using the one or more correction factors, and presenting information relating to an amount of radiation measured by the radiation analysis device having one of a plurality of specified radiation energy levels of a range of interest.

  13. Introduction to Network Analysis 1 Introduction to Network Analysis

    E-Print Network [OSTI]

    Safro, Ilya

    of movie actors Transportation and logistics network of nuclear power plant Actors, Reactors and More #12). Points Grade 92 A 80 B 60 C 0 F #12;Introduction to Network Analysis 2 Recommended Books (optional

  14. DOE Hydrogen Program Systems Analysis Workshop

    E-Print Network [OSTI]

    ) · Define analysis scenarios NREL SYSTEMS INTEGRATION · Accountable for analysis activities · Provide inputs · Coordinate and provide ideas/recommendations to SI on cross-cutting analysis · Manage analysis tasks internal to DOE (Labs/FFRDCs only) · Perform analysis of technoeconomic topics for TA and SI · Perform subprogram

  15. Full Core, Heterogeneous, Time Dependent Neutron Transport Calculations with the 3D Code DeCART

    E-Print Network [OSTI]

    Hursin, Mathieu

    2010-01-01T23:59:59.000Z

    core layout for the 1/8th PWR core model ________________ 76and future of the NEACRP PWR core transient benchmark. 199449. Hursin, M. (2008). PWR Control Rod Ejection Analysis

  16. 22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005

    E-Print Network [OSTI]

    Kazimi, Mujid S.

    This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, ...

  17. 22.351 Systems Analysis of the Nuclear Fuel Cycle, Spring 2003

    E-Print Network [OSTI]

    Kazimi, Mujid S.

    In-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, ...

  18. Intrinsic Shapes of Molecular Cloud Cores

    E-Print Network [OSTI]

    C. E. Jones; Shantanu Basu; John Dubinski

    2001-01-08T23:59:59.000Z

    We conduct an analysis of the shapes of molecular cloud cores using recently compiled catalogs of observed axis ratios of individual cores mapped in ammonia or through optical selection. We apply both analytical and statistical techniques to deproject the observed axis ratios in order to determine the true distribution of cloud core shapes. We find that neither pure oblate nor pure prolate cores can account for the observed distribution of core shapes. Intrinsically triaxial cores produce distributions which agree with observations. The best-fit triaxial distribution contains cores which are more nearly oblate than prolate.

  19. The MARTE VNIR Imaging Spectrometer Experiment: Design and Analysis

    E-Print Network [OSTI]

    Brown, Adrian J; Dunagan, Stephen

    2014-01-01T23:59:59.000Z

    We report on the design, operation, and data analysis methods employed on the VNIR imaging spectrometer instrument that was part of the Mars Astrobiology Research and Technology Experiment (MARTE). The imaging spectrometer is a hyperspectral scanning pushbroom device sensitive to VNIR wavelengths from 400-1000 nm. During the MARTE project, the spectrometer was deployed to the Rio Tinto region of Spain. We analyzed subsets of 3 cores from Rio Tinto using a new band modeling technique. We found most of the MARTE drill cores to contain predominantly goethite, though spatially coherent areas of hematite were identified in Core 23. We also distinguished non Fe-bearing minerals that were subsequently analyzed by X-ray diffraction (XRD) and found to be primarily muscovite. We present drill core maps that include spectra of goethite, hematite, and non Fe-bearing minerals.

  20. UNL Core for Applied Genomics and Ecology

    E-Print Network [OSTI]

    Farritor, Shane

    UNL Core for Applied Genomics and Ecology Bioinformatics training Roche 454 GS-FLX Registration, Microbiomes, Variant Analysis, Whole Genomes, Transcriptomes Data Analysis and Statistics CAGE database and employer. University of Nebraska-Lincoln*Core for Applied Genomics and Ecology* 323 Filley Hall *Lincoln

  1. Analysis of transcriptional regulatory circuitry

    E-Print Network [OSTI]

    Rinaldi, Nicola J., 1974-

    2004-01-01T23:59:59.000Z

    The research in this thesis has focused on the analysis of data from two types of microarray technologies with the goal of improving understanding of transcriptional regulatory circuitry in yeast. These microarray technologies, ...

  2. Protein Structure Analysis Iosif Vaisman

    E-Print Network [OSTI]

    Vaisman, Iosif

    Protein Structure Analysis Iosif Vaisman 2012 BINF 731 Protein Engineering Protein Engineering Increase catalytic activity Change substrate binding site to increase specificity Change the thermal stability Increase proteins resistance to proteases Change codon composition Protein Engineering

  3. Nonstandard Tools for Nonsmooth Analysis

    E-Print Network [OSTI]

    S. S. Kutateladze

    2012-06-11T23:59:59.000Z

    This is an overview of the basic tools of nonsmooth analysis which are grounded on nonstandard models of set theory. By way of illustration we give a criterion for an infinitesimally optimal path of a general discrete dynamic system.

  4. Geometric Analysis and General Relativity

    E-Print Network [OSTI]

    Lars Andersson

    2005-12-23T23:59:59.000Z

    This article discusses methods of geometric analysis in general relativity, with special focus on the role of "critical surfaces" such as minimal surfaces, marginal surface, maximal surfaces and null surfaces.

  5. Building America Analysis – Existing Homes

    Broader source: Energy.gov [DOE]

    The Building America Analysis Spreadsheets are companions to the House Simulation Protocols, and can assist with many of the calculations and look-up tables found in the report.

  6. Hydrogen Delivery Infrastructure Options Analysis

    Fuel Cell Technologies Publication and Product Library (EERE)

    This report, by the Nexant team, documents an in-depth analysis of seven hydrogen delivery options to identify the most cost-effective hydrogen infrastructure for the transition and long term. The pro

  7. Protein Structure Analysis Iosif Vaisman

    E-Print Network [OSTI]

    Vaisman, Iosif

    Protein Structure Analysis Iosif Vaisman 2012 BINF 731 Protein Engineering Protein Engineering Increase catalytic activity Change substrate binding site to increase specificity Change the thermal Engineering Protein Engineering #12;Protein Engineering Protein Engineering Protein Engineering Protein

  8. Process Cooling Pumping Systems Analysis

    E-Print Network [OSTI]

    Sherman, C.

    2008-01-01T23:59:59.000Z

    An analysis of the mill water pumping systems at a North American manufacturing facility was conducted late las year and the following issues were observed: 1. Overpumping – Both systems were overpumped to a significant degree against...

  9. Nationwide Used Fuel Inventory Analysis

    E-Print Network [OSTI]

    Yancey, Kristina

    2013-11-27T23:59:59.000Z

    The goal of this research was to develop a methodology to collect inventory estimates for the analysis and characterization of used fuel in the United States. To accomplish this, the Spent Fuel Database (SFD) was created. Data was collected...

  10. Thermal analysis of vascular reactivity

    E-Print Network [OSTI]

    Deshpande, Chinmay Vishwas

    2009-05-15T23:59:59.000Z

    dysfunction. Given the promising nature of thermal monitoring to study VR, this thesis focuses on the analysis of the underlying physics affecting fingertip temperature during vascular occlusion and subsequent hyperemia. I will quantify the contribution...

  11. NREL: Energy Analysis - Marissa Hummon

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

    Marissa Hummon is a member of the Energy Forecasting and Modeling Group in the Strategic Energy Analysis Center. Engineer On staff since January 2010 Phone number: 303-275-3269...

  12. Mandatory Photovoltaic System Cost Analysis

    Broader source: Energy.gov [DOE]

    The Arizona Corporation Commission requires electric utilities to conduct a cost/benefit analysis to compare the cost of line extension with the cost of installing a stand-alone photovoltaic (PV)...

  13. Corporate Analysis of DOE Safety Performance

    Broader source: Energy.gov [DOE]

    The Office of Environment, Health, Safety and Security (EHSS), Office of Analysis develops analysis tools and performance dashboards, and conducts analysis of DOE safety performance corporately and on a variety of specific environment, safety and health topics.

  14. Geospatial Analysis School of Forest Resources &

    E-Print Network [OSTI]

    Watson, Craig A.

    Geospatial Analysis GIS 4121 School of Forest Resources & Conservation Geomatics Program _______________________________________________________________________________________ 1 GIS 4121 Geospatial Analysis INSTRUCTORS: Dr. Hartwig Henry Hochmair (FLREC Fort Lauderdale) Dr MATERIALS: de Smith, MJ, Goodchild, MF, & Longley, PA (2010). Geospatial Analysis (3rd ed.). Leicester

  15. Valliappa Lakshmanan Automating the Analysis of

    E-Print Network [OSTI]

    Lakshmanan, Valliappa

    Geospatial Images January 5, 2012 Springer #12;Contents 1 Automated Analysis of Spatial Grids: MotivationValliappa Lakshmanan Automating the Analysis of Spatial Grids A Practitioner's Guide to Data Mining . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.5 Challenges in Automated Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1

  16. Bismuth-based electrochemical stripping analysis

    DOE Patents [OSTI]

    Wang, Joseph

    2004-01-27T23:59:59.000Z

    Method and apparatus for trace metal detection and analysis using bismuth-coated electrodes and electrochemical stripping analysis. Both anodic stripping voltammetry and adsorptive stripping analysis may be employed.

  17. Multi-Metric Sustainability Analysis

    SciTech Connect (OSTI)

    Cowlin, S.; Heimiller, D.; Macknick, J.; Mann, M.; Pless, J.; Munoz, D.

    2014-12-01T23:59:59.000Z

    A readily accessible framework that allows for evaluating impacts and comparing tradeoffs among factors in energy policy, expansion planning, and investment decision making is lacking. Recognizing this, the Joint Institute for Strategic Energy Analysis (JISEA) funded an exploration of multi-metric sustainability analysis (MMSA) to provide energy decision makers with a means to make more comprehensive comparisons of energy technologies. The resulting MMSA tool lets decision makers simultaneously compare technologies and potential deployment locations.

  18. Analysis Paralysis: when to stop?

    E-Print Network [OSTI]

    Bhardwaj, Er Akshay

    2009-01-01T23:59:59.000Z

    Analysis of a system constitutes the most important aspect of the systems development life cycle.But it is also the most confusing and time consuming of all the stages.The critical question always remains: How much and till when to analyse? Ed Yourdon has called this phenomenon as Analysis Paralysis. In this paper, I suggest a model which can actually help in arriving at a satisfactory answer to this problem.

  19. Hydrogen Delivery Infrastructure Analysis, Options and Trade...

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

    Analysis, Options and Trade-offs, Transition and Long-term Hydrogen Delivery Infrastructure Analysis, Options and Trade-offs, Transition and Long-term Presentation on Hydrogen...

  20. Analysis Activities at Pacific Northwest National Laboratory

    Broader source: Energy.gov [DOE]

    Presentation on PNNL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

  1. Advanced Vehicle Technology Analysis & Evaluation Team

    Broader source: Energy.gov [DOE]

    Presentation on Advanced Vehicle Technology Analysis & Evaluation Team to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

  2. Comparative Analysis of Proteome and Transcriptome Variation...

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

    Comparative Analysis of Proteome and Transcriptome Variation in Mouse. Comparative Analysis of Proteome and Transcriptome Variation in Mouse. Abstract: The relationships between...

  3. Quantitative proteomics analysis of adsorbed plasma proteins...

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

    proteomics analysis of adsorbed plasma proteins classifies nanoparticles with different surface properties and size Quantitative proteomics analysis of adsorbed plasma proteins...

  4. Electron Spectrometer: Scanning Multiprobe Surface Analysis System...

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

    Scanning Multiprobe Surface Analysis System - Versaprobe Electron Spectrometer: Scanning Multiprobe Surface Analysis System - Versaprobe The SMSAS is a multi-technique surface...

  5. Innovative Corridors Initiative: Business Model Analysis

    E-Print Network [OSTI]

    Shaheen, Susan; Lingham, Viginia; Finson, Rachel S.

    2007-01-01T23:59:59.000Z

    Wenger, Joyce. Business Models for Vehicle InfrastructureCorridors Initiative: Business Model Analysis Rachel S.Corridors Initiative: Business Model Analysis Task Order

  6. Issues in International Energy Consumption Analysis: Electricity...

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

    Issues in International Energy Consumption Analysis: Electricity Usage in India's Housing Sector November 2014 Independent Statistics & Analysis www.eia.gov U.S. Department of...

  7. Analysis Activities at National Renewable Energy Laboratory

    Broader source: Energy.gov [DOE]

    Presentation on NREL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

  8. Analysis Activities at Lawrence Livermore National Laboratory

    Broader source: Energy.gov [DOE]

    Presentation on Lawrence Livermore’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

  9. UCSF Sustainability Baseline Assessment: Carbon Footprint Analysis

    E-Print Network [OSTI]

    Yamamoto, Keith

    UCSF Sustainability Baseline Assessment: Carbon Footprint Analysis Final Issue Date: March 21, 2010 #12;Carbon Footprint Analysis Background This chapter of the Sustainability Assessment focuses on UCSF

  10. Analysis Activities at Sandia National Laboratory

    Broader source: Energy.gov [DOE]

    Presentation on SNL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

  11. Computational prediction and analysis of protein structure

    E-Print Network [OSTI]

    Meruelo, Alejandro Daniel

    2012-01-01T23:59:59.000Z

    I, and Bowie JU. Kink prediction in membrane proteins.Los Angeles Computational prediction and analysis of proteinOF THE DISSERTATION Computational prediction and analysis of

  12. NREL: Energy Analysis - Caroline Uriarte Chapman

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

    Chapman is a member of the Market and Policy Impact Analysis Group in the Strategic Energy Analysis Center. Energy Analyst On staff since April 2009 Phone number:...

  13. Fayette Country, Pennsylvania, Housing Market Analysis | Department...

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

    Fayette Country, Pennsylvania, Housing Market Analysis Fayette Country, Pennsylvania, Housing Market Analysis This is a document from the Fayette County Housing Consortium posted...

  14. Geographically-Based Infrastructure Analysis | Department of...

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

    Infrastructure Analysis given by Keith Parks of the National Renewable Energy Laboratory during the DOE Hydrogen Transition Analysis Workshop on January 26,...

  15. Buildings Performance Database Analysis Tools | Department of...

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

    Performance Database Analysis Tools The Buildings Performance Database offers several analysis tools for exploring building data and forecasting financial and energy savings,...

  16. Analysis Activities at Argonne National Laboratory

    Broader source: Energy.gov [DOE]

    Presentation on Argonne’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

  17. Integrated Vehicle Thermal Management Systems (VTMS) Analysis...

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

    Systems (VTMS) AnalysisModeling Integrated Vehicle Thermal Management Systems (VTMS) AnalysisModeling 2009 DOE Hydrogen Program and Vehicle Technologies Program Annual Merit...

  18. Integrated External Aerodynamic and Underhood Thermal Analysis...

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

    External Aerodynamic and Underhood Thermal Analysis for Heavy Vehicles Integrated External Aerodynamic and Underhood Thermal Analysis for Heavy Vehicles 2012 DOE Hydrogen and Fuel...

  19. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03T23:59:59.000Z

    The purpose of this seismic preclosure safety analysis is to identify the potential seismically-initiated event sequences associated with preclosure operations of the repository at Yucca Mountain and assign appropriate design bases to provide assurance of achieving the performance objectives specified in the Code of Federal Regulations (CFR) 10 CFR Part 63 for radiological consequences. This seismic preclosure safety analysis is performed in support of the License Application for the Yucca Mountain Project. In more detail, this analysis identifies the systems, structures, and components (SSCs) that are subject to seismic design bases. This analysis assigns one of two design basis ground motion (DBGM) levels, DBGM-1 or DBGM-2, to SSCs important to safety (ITS) that are credited in the prevention or mitigation of seismically-initiated event sequences. An application of seismic margins approach is also demonstrated for SSCs assigned to DBGM-2 by showing a high confidence of a low probability of failure at a higher ground acceleration value, termed a beyond-design basis ground motion (BDBGM) level. The objective of this analysis is to meet the performance requirements of 10 CFR 63.111(a) and 10 CFR 63.111(b) for offsite and worker doses. The results of this calculation are used as inputs to the following: (1) A classification analysis of SSCs ITS by identifying potential seismically-initiated failures (loss of safety function) that could lead to undesired consequences; (2) An assignment of either DBGM-1 or DBGM-2 to each SSC ITS credited in the prevention or mitigation of a seismically-initiated event sequence; and (3) A nuclear safety design basis report that will state the seismic design requirements that are credited in this analysis. The present analysis reflects the design information available as of October 2004 and is considered preliminary. The evolving design of the repository will be re-evaluated periodically to ensure that seismic hazards are properly evaluated and identified. This document supersedes the seismic classifications, assignments, and computations in ''Seismic Analysis for Preclosure Safety'' (BSC 2004a).

  20. The ALICE analysis train system

    E-Print Network [OSTI]

    Markus Zimmermann; for the ALICE collaboration

    2015-02-23T23:59:59.000Z

    In the ALICE experiment hundreds of users are analyzing big datasets on a Grid system. High throughput and short turn-around times are achieved by a centralized system called the LEGO trains. This system combines analysis from different users in so-called analysis trains which are then executed within the same Grid jobs thereby reducing the number of times the data needs to be read from the storage systems. The centralized trains improve the performance, the usability for users and the bookkeeping in comparison to single user analysis. The train system builds upon the already existing ALICE tools, i.e. the analysis framework as well as the Grid submission and monitoring infrastructure. The entry point to the train system is a web interface which is used to configure the analysis and the desired datasets as well as to test and submit the train. Several measures have been implemented to reduce the time a train needs to finish and to increase the CPU efficiency.

  1. Space elevator systems level analysis

    SciTech Connect (OSTI)

    Laubscher, B. E. (Bryan E.)

    2004-01-01T23:59:59.000Z

    The Space Elevator (SE) represents a major paradigm shift in space access. It involves new, untried technologies in most of its subsystems. Thus the successful construction of the SE requires a significant amount of development, This in turn implies a high level of risk for the SE. This paper will present a systems level analysis of the SE by subdividing its components into their subsystems to determine their level of technological maturity. such a high-risk endeavor is to follow a disciplined approach to the challenges. A systems level analysis informs this process and is the guide to where resources should be applied in the development processes. It is an efficient path that, if followed, minimizes the overall risk of the system's development. systems level analysis is that the overall system is divided naturally into its subsystems, and those subsystems are further subdivided as appropriate for the analysis. By dealing with the complex system in layers, the parameter space of decisions is kept manageable. Moreover, A rational way to manage One key aspect of a resources are not expended capriciously; rather, resources are put toward the biggest challenges and most promising solutions. This overall graded approach is a proven road to success. The analysis includes topics such as nanotube technology, deployment scenario, power beaming technology, ground-based hardware and operations, ribbon maintenance and repair and climber technology.

  2. Method of photon spectral analysis

    DOE Patents [OSTI]

    Gehrke, R.J.; Putnam, M.H.; Killian, E.W.; Helmer, R.G.; Kynaston, R.L.; Goodwin, S.G.; Johnson, L.O.

    1993-04-27T23:59:59.000Z

    A spectroscopic method to rapidly measure the presence of plutonium in soils, filters, smears, and glass waste forms by measuring the uranium L-shell x-ray emissions associated with the decay of plutonium. In addition, the technique can simultaneously acquire spectra of samples and automatically analyze them for the amount of americium and [gamma]-ray emitting activation and fission products present. The samples are counted with a large area, thin-window, n-type germanium spectrometer which is equally efficient for the detection of low-energy x-rays (10-2,000 keV), as well as high-energy [gamma] rays (>1 MeV). A 8,192- or 16,384 channel analyzer is used to acquire the entire photon spectrum at one time. A dual-energy, time-tagged pulser, that is injected into the test input of the preamplifier to monitor the energy scale, and detector resolution. The L x-ray portion of each spectrum is analyzed by a linear-least-squares spectral fitting technique. The [gamma]-ray portion of each spectrum is analyzed by a standard Ge [gamma]-ray analysis program. This method can be applied to any analysis involving x- and [gamma]-ray analysis in one spectrum and is especially useful when interferences in the x-ray region can be identified from the [gamma]-ray analysis and accommodated during the x-ray analysis.

  3. Method of photon spectral analysis

    DOE Patents [OSTI]

    Gehrke, Robert J. (Idaho Falls, ID); Putnam, Marie H. (Idaho Falls, ID); Killian, E. Wayne (Idaho Falls, ID); Helmer, Richard G. (Idaho Falls, ID); Kynaston, Ronnie L. (Blackfoot, ID); Goodwin, Scott G. (Idaho Falls, ID); Johnson, Larry O. (Pocatello, ID)

    1993-01-01T23:59:59.000Z

    A spectroscopic method to rapidly measure the presence of plutonium in soils, filters, smears, and glass waste forms by measuring the uranium L-shell x-ray emissions associated with the decay of plutonium. In addition, the technique can simultaneously acquire spectra of samples and automatically analyze them for the amount of americium and .gamma.-ray emitting activation and fission products present. The samples are counted with a large area, thin-window, n-type germanium spectrometer which is equally efficient for the detection of low-energy x-rays (10-2000 keV), as well as high-energy .gamma. rays (>1 MeV). A 8192- or 16,384 channel analyzer is used to acquire the entire photon spectrum at one time. A dual-energy, time-tagged pulser, that is injected into the test input of the preamplifier to monitor the energy scale, and detector resolution. The L x-ray portion of each spectrum is analyzed by a linear-least-squares spectral fitting technique. The .gamma.-ray portion of each spectrum is analyzed by a standard Ge .gamma.-ray analysis program. This method can be applied to any analysis involving x- and .gamma.-ray analysis in one spectrum and is especially useful when interferences in the x-ray region can be identified from the .gamma.-ray analysis and accommodated during the x-ray analysis.

  4. Development of Tritium Permeation Analysis Code (TPAC)

    SciTech Connect (OSTI)

    Eung S. Kim; Chang H. Oh; Mike Patterson

    2010-10-01T23:59:59.000Z

    Idaho National Laboratory developed the Tritium Permeation Analysis Code (TPAC) for tritium permeation in the Very High Temperature Gas Cooled Reactor (VHTR). All the component models in the VHTR were developed and were embedded into the MATHLAB SIMULINK package with a Graphic User Interface. The governing equations of the nuclear ternary reaction and thermal neutron capture reactions from impurities in helium and graphite core, reflector, and control rods were implemented. The TPAC code was verified using analytical solutions for the tritium birth rate from the ternary fission, the birth rate from 3He, and the birth rate from 10B. This paper also provides comparisons of the TPAC with the existing other codes. A VHTR reference design was selected for tritium permeation study from the reference design to the nuclear-assisted hydrogen production plant and some sensitivity study results are presented based on the HTGR outlet temperature of 750 degrees C.

  5. GUM Analysis for TIMS Isotopic Ratios in BEP0 Graphite Qualification Samples, Round 2

    SciTech Connect (OSTI)

    Gerlach, David C.; Heasler, Patrick G.; Reid, Bruce D.

    2009-01-01T23:59:59.000Z

    In May 2007, one set of three samples from NBL were addressed to Steve Petersen for TIMS analysis, and included BEP0 samples numbered 27008, 30986, and 50846. All cores were trimmed by tooling, and lightly cleaned by CO2 pellet blasting. Small discs were cut from the second set of samples for SIMS analysis, with the remainder of each used for TIMS preparation.

  6. ESF Subsurface Standby Generator Analysis

    SciTech Connect (OSTI)

    L. Fernandez

    1998-04-17T23:59:59.000Z

    The purpose of this analysis is to outline and recommend two standby generator systems. These systems shall provide power during a utility outage to critical Alcove No.5's thermal test loads and to subsurface flow through ventilation loads. Critical loads that will be supported by these generator systems will be identified and evaluated. Additionally, other requirements from the Exploratory Studies Facilities Design Requirements (ESFDR) document will be evaluated. Finally, the standby generator systems will be integrated into the existing ESF subsurface distribution system. The objective of this analysis is to provide design inputs for an efficient and reliable standby generator systems which will provide power for critical loads during a power outage; specifically, Alcove No.5's thermal test loads and the subsurface flow through ventilation loads. Additionally, preliminary one-line diagrams will be developed using this analysis as a primary input.

  7. Multilinear (Tensor) Image Synthesis, Analysis, and Recognition

    E-Print Network [OSTI]

    Terzopoulos, Demetri

    and a col- umn space. In a factor analysis of D, the SVD orthogonalizes these two spaces and decomposesMultilinear (Tensor) Image Synthesis, Analysis, and Recognition [exploratory DSP] M. Alex O analysis (PCA) and its refinement known as independ- ent components analysis (ICA) model single

  8. Freight Analysis Framework version 3 (FAF3)

    E-Print Network [OSTI]

    Freight Analysis Framework version 3 (FAF3) Oak Ridge National Laboratory managed by UT Technologies Research Brief T he Freight Analysis Framework version 3 (FAF3) database is a Federal Highway data to enable users to perform train analysis. FAF3 Geography Figure 1 shows the analysis regions

  9. Systems Analysis Department Annual Report 2001

    E-Print Network [OSTI]

    benchmarking analysis to the Danish district heating sector Technology Scenarios 17 Sensor Technology Foresight

  10. Controlled Hydrogen Fleet and Infrastructure Analysis (Presentation)

    SciTech Connect (OSTI)

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

    2010-06-10T23:59:59.000Z

    This presentation summarizes controlled hydrogen fleet & infrastructure analysis undertaken for the DOE Fuel Cell Technologies Program.

  11. Medial Techniques for Automating Finite Element Analysis

    E-Print Network [OSTI]

    Whitton, Mary C.

    Medial Techniques for Automating Finite Element Analysis by Jessica Renee Crawford Crouch Analysis. (Under the direction of Stephen M. Pizer.) Finite element analysis provides a principled method the simulation of tissue deformation. The drawback to using finite element analysis for imaging problems

  12. Numerical bifurcation analysis of piecewise smooth systems

    E-Print Network [OSTI]

    ( ) ( ) ( ) ( ), , outoutinin inin xffxff xhhxgg xxxx == == #12;Numerical bifurcation analysis of piecewise smooth systems INRIA

  13. analysis energy analysis: Topics by E-print Network

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

    energy analysis First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Energy, Environmental, and Economic...

  14. Traversal, Case Analysis, and Lowering for C++ Program Analysis

    E-Print Network [OSTI]

    Wagner, Luke A.

    2010-01-14T23:59:59.000Z

    ++. This extension, named Filter, assists the tool builder in traversal, case analysis, and lowering of the data structure representing C++ programs. Comparisons described in the thesis show a 2-4x code reduction when solving basic problems (e.g., searching for uses...

  15. Initial Decision and Risk Analysis

    SciTech Connect (OSTI)

    Engel, David W.

    2012-02-29T23:59:59.000Z

    Decision and Risk Analysis capabilities will be developed for industry consideration and possible adoption within Year 1. These tools will provide a methodology for merging qualitative ranking of technology maturity and acknowledged risk contributors with quantitative metrics that drive investment decision processes. Methods and tools will be initially introduced as applications to the A650.1 case study, but modular spreadsheets and analysis routines will be offered to industry collaborators as soon as possible to stimulate user feedback and co-development opportunities.

  16. Relative trajectory data reduction analysis

    E-Print Network [OSTI]

    Grant, Kenneth William

    1969-01-01T23:59:59.000Z

    REDATIVE TRAJECTORY DATA RFDUCTION ANA1. YS1S A Thesis KENNE'Ill Vi. GRANT Subrnitl ed to the Gratluate College of 'J exas ASM University in pa) &ial full'illment of the reouir ament for the degree of MASTER OF SCIENCE August 1969 Major... Trajectory Data Reduction Analysis. (August 1969) Kenneth W. Grant, B. A. , University of California at Riverside Directed by: Dr. Rudolph Freund Knowledge of missile/drone intercept parameters is extremely important in the analysis of ordnance system...

  17. Advances in total scattering analysis

    SciTech Connect (OSTI)

    Proffen, Thomas E [Los Alamos National Laboratory; Kim, Hyunjeong [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    In recent years the analysis of the total scattering pattern has become an invaluable tool to study disordered crystalline and nanocrystalline materials. Traditional crystallographic structure determination is based on Bragg intensities and yields the long range average atomic structure. By including diffuse scattering into the analysis, the local and medium range atomic structure can be unravelled. Here we give an overview of recent experimental advances, using X-rays as well as neutron scattering as well as current trends in modelling of total scattering data.

  18. Analysis Methodologies | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'s Reply Comments AT&T,FACT SAmes LabSystems Analysis » Analysis

  19. Resource Analysis | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreakingMay 2015 < prevQuickEnergyforDepartmentSystems Analysis » Analysis

  20. Canister storage building hazard analysis report

    SciTech Connect (OSTI)

    POWERS, T.B.

    1999-05-11T23:59:59.000Z

    This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the CSB final safety analysis report (FSAR) and documents the results. The hazard analysis was performed in accordance with the DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', and meets the intent of HNF-PRO-704, ''Hazard and Accident Analysis Process''. This hazard analysis implements the requirements of DOE Order 5480.23, ''Nuclear Safety Analysis Reports''.

  1. Feasibility of a Monte Carlo-deterministic hybrid method for fast reactor analysis

    SciTech Connect (OSTI)

    Heo, W.; Kim, W.; Kim, Y. [Korea Advanced Institute of Science and Technology - KAIST, 291 Daehak-ro, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of); Yun, S. [Korea Atomic Energy Research Institute - KAERI, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

    A Monte Carlo and deterministic hybrid method is investigated for the analysis of fast reactors in this paper. Effective multi-group cross sections data are generated using a collision estimator in the MCNP5. A high order Legendre scattering cross section data generation module was added into the MCNP5 code. Both cross section data generated from MCNP5 and TRANSX/TWODANT using the homogeneous core model were compared, and were applied to DIF3D code for fast reactor core analysis of a 300 MWe SFR TRU burner core. For this analysis, 9 groups macroscopic-wise data was used. In this paper, a hybrid calculation MCNP5/DIF3D was used to analyze the core model. The cross section data was generated using MCNP5. The k{sub eff} and core power distribution were calculated using the 54 triangle FDM code DIF3D. A whole core calculation of the heterogeneous core model using the MCNP5 was selected as a reference. In terms of the k{sub eff}, 9-group MCNP5/DIF3D has a discrepancy of -154 pcm from the reference solution, 9-group TRANSX/TWODANT/DIF3D analysis gives -1070 pcm discrepancy. (authors)

  2. Cold Vacuum Drying Facility hazard analysis report

    SciTech Connect (OSTI)

    Krahn, D.E.

    1998-02-23T23:59:59.000Z

    This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports.

  3. Canister storage building hazard analysis report

    SciTech Connect (OSTI)

    Krahn, D.E.; Garvin, L.J.

    1997-07-01T23:59:59.000Z

    This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the final CSB safety analysis report (SAR) and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Report, and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

  4. A technique for human error analysis (ATHEANA)

    SciTech Connect (OSTI)

    Cooper, S.E.; Ramey-Smith, A.M.; Wreathall, J.; Parry, G.W. [and others

    1996-05-01T23:59:59.000Z

    Probabilistic risk assessment (PRA) has become an important tool in the nuclear power industry, both for the Nuclear Regulatory Commission (NRC) and the operating utilities. Human reliability analysis (HRA) is a critical element of PRA; however, limitations in the analysis of human actions in PRAs have long been recognized as a constraint when using PRA. A multidisciplinary HRA framework has been developed with the objective of providing a structured approach for analyzing operating experience and understanding nuclear plant safety, human error, and the underlying factors that affect them. The concepts of the framework have matured into a rudimentary working HRA method. A trial application of the method has demonstrated that it is possible to identify potentially significant human failure events from actual operating experience which are not generally included in current PRAs, as well as to identify associated performance shaping factors and plant conditions that have an observable impact on the frequency of core damage. A general process was developed, albeit in preliminary form, that addresses the iterative steps of defining human failure events and estimating their probabilities using search schemes. Additionally, a knowledge- base was developed which describes the links between performance shaping factors and resulting unsafe actions.

  5. Mesoscale harmonic analysis of homogenous dislocation nucleation

    E-Print Network [OSTI]

    Asad Hasan; Craig E. Maloney

    2012-05-08T23:59:59.000Z

    We perform atomistic computer simulations to study the mechanism of homogeneous dislocation nucleation in two dimensional (2D) hexagonal crystalline films during indentation with a circular nanoindenter. The nucleation process is governed by the vanishing of the energy associated with a single normal mode. This critical mode is largely confined to a single plane of adjacent atoms. For fixed film thickness, L, the spatial extent, \\xi, of the critical mode grows with indenter radius, R. For fixed R/L, the spatial extent \\xi, grows roughly as \\xi ~ L^0.4. We, furthermore, perform a mesoscale analysis to determine the lowest energy normal mode for mesoscale regions of varying radius, r_{meso}, centered on the critical mode's core. The energy, \\lambda_{meso}, of the lowest normal mode in the meso-region decays very rapidly with r_{meso} and \\lambda_{meso} ~= 0 for r_{meso} >~ \\xi. The lowest normal mode shows a spatial extent, \\xi_{meso}, which has a sublinear power-law increase with r_{meso} for r_{meso} mesoscale analysis gives good estimates for the energy and spatial extent of the critical mode \\emph{only} for r_{meso} >~ 1.5 \\xi. In this sense homogeneous dislocation nucleation should be understood as a quasi-local phenomenon.

  6. ANALYSIS OF TRANSIENT ELECTROMAGENTIC SCATTERING ...

    E-Print Network [OSTI]

    2015-04-02T23:59:59.000Z

    Moreover, an a priori estimate is established for the electric field ... of capturing wide-band signals and modeling more general material and nonlinearity. [11,24 ... the resulted system via frequency-domain TBC, and (iii) the analysis of the finite-.

  7. Community Impact Analysis Emerging Approaches

    E-Print Network [OSTI]

    Minnesota, University of

    to require preparation of an environmental impact statement. When an environmental impact statement, then the environmental impact statement will discuss all of these effects on the human environment. #12;PrioritiesCommunity Impact Analysis Emerging Approaches #12;1960s · 1964 Title VI of Civil Rights Act of 1964

  8. IEAB Independent Economic Analysis Board

    E-Print Network [OSTI]

    . Huppert Noelwah R. Netusil JunJie Wu Cost-Effectiveness of Fish Tagging Technologies and Programs in the Columbia River Basin1 Independent Economic Analysis Board Fish and Wildlife Program Northwest Power and Conservation Council June 2, 2013 1 This report benefitted from the meetings of the Fish Tagging Forum

  9. Multipole analysis in cosmic topology

    E-Print Network [OSTI]

    Peter Kramer

    2010-09-29T23:59:59.000Z

    Low multipole amplitudes in the Cosmic Microwave Background CMB radiation can be explained by selection rules from the underlying multiply-connected homotopy. We apply a multipole analysis to the harmonic bases and introduce point symmetry.We give explicit results for two cubic 3-spherical manifolds and lowest polynomial degrees, and derive three new spherical 3-manifolds.

  10. Regression analysis with missing data

    E-Print Network [OSTI]

    Michelli, Frank Anthony

    1968-01-01T23:59:59.000Z

    : Statistios REGRESSION ANALYSIS WITH MISS1NG DATA A Thesis FRANK ANTHONY MICHELLI Approved as to style and content by: hairman of o ttee Member Head of Department Member Member Zanuary 196B ACZNOWLED ONE NT S I can only begin to express my sincere...

  11. ABBGroup-1-Quantitative analysis of

    E-Print Network [OSTI]

    Basse, Nils Plesner

    of short-circuit current in high- voltage gas circuit breakers Pressure produced by the arc is used©ABBGroup-1- 3-Sep-07 Quantitative analysis of gas circuit breaker physics through direct;©ABBGroup-4- 3-Sep-07 CFD pressure animation #12;©ABBGroup-5- 3-Sep-07 Current interruption phases Sequence

  12. Fourier Analysis of Ghost Imaging

    E-Print Network [OSTI]

    Honglin Liu; Jing Cheng; Yanfeng Bai; Shensheng Han

    2006-09-28T23:59:59.000Z

    Fourier analysis of ghost imaging (FAGI) is proposed in this paper to analyze the properties of ghost imaging with thermal light sources. This new theory is compatible with the general correlation theory of intensity fluctuation and could explain some amazed phenomena. Furthermore we design a series of experiments to verify the new theory and investigate the inherent properties of ghost imaging.

  13. Protein Structure Analysis Iosif Vaisman

    E-Print Network [OSTI]

    Vaisman, Iosif

    Protein Structure Analysis Iosif Vaisman 2009 BINF 731 Protein Engineering Protein Engineering Increase catalytic activity Change substrate binding site to increase specificity Change the thermal152S -1.08 1goj S152T 1.12 Protein Engineering Protein Engineering #12;Protein Engineering Protein

  14. WHC fire hazards analysis policy

    SciTech Connect (OSTI)

    Evans, C.B.

    1994-04-01T23:59:59.000Z

    The purpose of this document is to establish the fire protection policy for Westinghouse Hanford Company (WHC) relative to US Department of Energy (DOE) directives for Fire Hazards Analyses (FHAs) and their relationship to facility Safety Analysis Reports (SARs) as promulgated by the DOE Richland Operations Office.

  15. Exergy analysis of magnetic refrigeration

    E-Print Network [OSTI]

    Lucia, Umberto

    2010-01-01T23:59:59.000Z

    One of the main challenges of the industry today is to face its impact on global warming considering that the greenhouse effect problem is not be solved completely yet. Magnetic refrigeration represents an environment-safe refrigeration technology. The magnetic refrigeration is analysed using the second law analysis and introducing exergy in order to obtain a model for engineering application.

  16. ECE 2100 Circuit Analysis NAME: ________________________________________________

    E-Print Network [OSTI]

    Miller, Damon A.

    ECE 2100 Circuit Analysis Fall 2011 Exam #1 NAME Schematics drawn using LTspice IV (linear.com). Some problems might be adapted from the course text Schematics drawn using LTspice IV (linear.com). Some problems might be adapted from the course text

  17. Strategic Energy Analysis (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-02-01T23:59:59.000Z

    NREL complements its scientific research with high-quality, credible, technology-neutral, objective analysis that informs policy and investment decisions as renewable energy and energy efficiency technologies move from innovation through integration. This sheet highlights NREL's analytical capabilities and achievements.

  18. Tolerance Analysis of Flexible Assemblies Using Finite Element and Spectral Analysis

    E-Print Network [OSTI]

    Tolerance Analysis of Flexible Assemblies Using Finite Element and Spectral Analysis ADCATS Report the autocorrelation function from frequency spectrum analysis to model random surface variations. Finite element BACKGROUND LITERATURE REVIEW 5 3 STATISTICAL TOLERANCE ANALYSIS USING FINITE ELEMENT ANALYSIS 3.1 Assumptions

  19. AGR-1 Thermocouple Data Analysis

    SciTech Connect (OSTI)

    Jeff Einerson

    2012-05-01T23:59:59.000Z

    This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas Reactor (AGR) fuel irradiation test program conducted in the INL's Advanced Test Reactor (ATR) to support the Next Generation Nuclear Plant (NGNP) R&D program. The work follows up on a previous study (Pham and Einerson, 2010), in which statistical analysis methods were applied for AGR-1 thermocouple data qualification. The present work exercises the idea that, while recognizing uncertainties inherent in physics and thermal simulations of the AGR-1 test, results of the numerical simulations can be used in combination with the statistical analysis methods to further improve qualification of measured data. Additionally, the combined analysis of measured and simulation data can generate insights about simulation model uncertainty that can be useful for model improvement. This report also describes an experimental control procedure to maintain fuel target temperature in the future AGR tests using regression relationships that include simulation results. The report is organized into four chapters. Chapter 1 introduces the AGR Fuel Development and Qualification program, AGR-1 test configuration and test procedure, overview of AGR-1 measured data, and overview of physics and thermal simulation, including modeling assumptions and uncertainties. A brief summary of statistical analysis methods developed in (Pham and Einerson 2010) for AGR-1 measured data qualification within NGNP Data Management and Analysis System (NDMAS) is also included for completeness. Chapters 2-3 describe and discuss cases, in which the combined use of experimental and simulation data is realized. A set of issues associated with measurement and modeling uncertainties resulted from the combined analysis are identified. This includes demonstration that such a combined analysis led to important insights for reducing uncertainty in presentation of AGR-1 measured data (Chapter 2) and interpretation of simulation results (Chapter 3). The statistics-based simulation-aided experimental control procedure described for the future AGR tests is developed and demonstrated in Chapter 4. The procedure for controlling the target fuel temperature (capsule peak or average) is based on regression functions of thermocouple readings and other relevant parameters and accounting for possible changes in both physical and thermal conditions and in instrument performance.

  20. Analysis reveals potential rangeland impacts if Williamson Act eliminated

    E-Print Network [OSTI]

    Wetzel, William C; Lacher, Iara L; Swezey, Daniel s; Moffitt, Sarah E; Manning, Dale T

    2012-01-01T23:59:59.000Z

    Act, using a geospatial analysis and a mail question- naireelimination scenario. The geospatial analysis revealed that

  1. SAFETY ANALYSIS AND INTEGRATION FOR ROBOTIC SYSTEMS -APPLICATION TO A

    E-Print Network [OSTI]

    Guiochet, Jérémie

    Analysis (FMEA) and Fault Tree Analysis (FTA) which identify potential unit errors resulting in hazards

  2. Preliminary hazards analysis -- vitrification process

    SciTech Connect (OSTI)

    Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P. [Science Applications International Corp., Pleasanton, CA (United States)] [Science Applications International Corp., Pleasanton, CA (United States)

    1994-06-01T23:59:59.000Z

    This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.

  3. B PLANT DOCUMENTED SAFETY ANALYSIS

    SciTech Connect (OSTI)

    DODD, E.N.; KERR, N.R.

    2003-08-01T23:59:59.000Z

    This document provides the documented safety analysis (DSA) and Central Plateau Remediation Project (CP) requirements that apply to surveillance and maintenance (S&M) activities at the 221-B Canyon Building and ancillary support structures (B Plant). The document replaces BHI-010582, Documented Safety Analysis for the B-Plant Facility. The B Plant is non-operational, deactivated and undergoing long term S&M prior to decontamination and decommissioning (D&D). This DSA is compliant with 10 CFR 830, Nuclear Safety Management, Subpart B, ''Safety Basis Requirements.'' The DSA was developed in accordance with U.S. Department of Energy (DOE) standard DOE-STD-1120-98, Integration of Environment, Safety, and Health into Facility Disposition Activities (DOE 1998) per Table 2 of 10 CFR 830 Appendix A, DOE Richland Operation Office (RL) direction (02-ABD-0053, Fluor Hanford Nuclear Safety Basis Strategy and Criteria) for facilities in long term S&M, and RL Direction (02-ABD-0091, ''FHI Nuclear Safety Expectations for Nuclear Facilities in Surveillance and Maintenance''). A crosswalk was prepared to identify potential inconsistencies between the previous B Plant safety analysis and DOE-STD-1120-98 guidance. In general, the safety analysis met the criteria of DOE-STD-1120-98. Some format and content changes have been made, including incorporating recent facility modifications and updating the evaluation guidelines and control selection criteria in accordance with RL direction (02-ABD-0053). The facility fire hazard analysis (FHA) and Technical Safety Requirements (TSR) are appended to this DSA as an aid to the users, to minimize editorial redundancy, and to provide an efficient basis for update.

  4. Core Analysis For The Development And Constraint Of Physical...

    Open Energy Info (EERE)

    Of Geothermal Reservoirs Abstract Effective reservoir exploration, characterization, and engineering require a fundamental understanding of the geophysical properties of reservoir...

  5. Analysis and Stability of Bent–Core Liquid Crystal Fibers

    E-Print Network [OSTI]

    2011-02-21T23:59:59.000Z

    Feb 21, 2011 ... We show that the relative size of the energy's elasticity con- ... energy to balance the tendency of surface tension to constrict the fiber and.

  6. Core Analysis At Long Valley Caldera Geothermal Area (Smith ...

    Open Energy Info (EERE)

    studies, and seem to prove useful in most cases (Flexser, 1991; Goff et al., 1991; Smith and Suemnicht, 1991). Results from these studies are also summarized in Sorey et al....

  7. Transient analysis of hydride fueled pressurized water reactor cores

    E-Print Network [OSTI]

    Trant, Jarrod Michael

    2004-01-01T23:59:59.000Z

    This thesis contributes to the hydride nuclear fuel project led by U. C. Berkeley for which MIT is to perform the thermal hydraulic and economic analyses. A parametric study has been performed to determine the optimum ...

  8. Analysis of tru-fueled vhtr prismatic core performance domains 

    E-Print Network [OSTI]

    Lewis, Tom Goslee

    2009-05-15T23:59:59.000Z

    in opening and safeguarding such a repository have led to investigations of alternative waste management strategies. One potential strategy would make use of fuels containing transuranic (TRU) nuclides in nuclear reactors. This would prolong reactor operation...

  9. Neutronic analysis of pebble-bed cores with transuranics 

    E-Print Network [OSTI]

    Pritchard, Megan Leigh

    2009-05-15T23:59:59.000Z

    ................................................................... 76 VI.A Sensitivity of the Pebble-Bed Performance to Loading Height ......................................................................... 76 VI.B Sensitivity of the Pebble-Bed Performance to the Central Graphite Column... Temperature Coefficient for Various Fuel Loadings ......... 74 XIX Isothermal Temperature Coefficients ................................................... 75 XX Effect of Central Graphite Column Size on Multiplication Factor....... 79 XXI Summary...

  10. Neutronic analysis of pebble-bed cores with transuranics

    E-Print Network [OSTI]

    Pritchard, Megan Leigh

    2009-05-15T23:59:59.000Z

    At the brink of nuclear waste repository crises, viable alternatives for the long term radiotoxic wastes are seriously being considered worldwide. Minor actinides serve as one of these targeted wastes. Partitioning and transmutation in fission...

  11. Analysis of tru-fueled vhtr prismatic core performance domains

    E-Print Network [OSTI]

    Lewis, Tom Goslee

    2009-05-15T23:59:59.000Z

    and 1.5 kg of minor actinides (MAs). The remainder consists of fission products (FPs) (~30 kg) and depleted uranium (DU) [7]. Elements labeled as TRUs have atomic numbers greater than 92 (uranium) and are created in nuclear reactors from 238 U...

  12. Core Analysis At Alum Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew| ExplorationCooperstown,Terrace,Lakes, Arizona:Alum Area

  13. Core Analysis At Colrado Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew| ExplorationCooperstown,Terrace,Lakes,

  14. Core Analysis At Coso Geothermal Area (1980) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew| ExplorationCooperstown,Terrace,Lakes,transfer mechanism

  15. Core Analysis At Dunes Geothermal Area (1976) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew| ExplorationCooperstown,Terrace,Lakes,transfer

  16. Core Analysis At Coso Geothermal Area (1979) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump to:Coppell, Texas:CoraIIDate

  17. Core Analysis At International Geothermal Area, Indonesia (Boitnott, 2003)

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump| Open Energy Information

  18. Core Analysis At International Geothermal Area, Indonesia (Laney, 2005) |

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump| Open Energy

  19. Core Analysis At International Geothermal Area, Philippines (Laney, 2005) |

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump| Open EnergyOpen Energy

  20. Core Analysis At Raft River Geothermal Area (1979) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump| OpenInformation Permitted

  1. Core Analysis At Raft River Geothermal Area (2011) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.pngRoofs and Heat Islands Jump| OpenInformation

  2. Analysis

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041cloth DocumentationProductsAlternative FuelsSanta FeAuthorization| Ironmethods. |

  3. Extending and automating a systems-theoretic hazard analysis for requirements generation and analysis

    E-Print Network [OSTI]

    Thomas, John P., IV

    2013-01-01T23:59:59.000Z

    Systems Theoretic Process Analysis (STPA) is a powerful new hazard analysis method designed to go beyond traditional safety techniques-such as Fault Tree Analysis (FTA)-that overlook important causes of accidents like ...

  4. Experiment Design and Analysis Guide - Neutronics & Physics

    SciTech Connect (OSTI)

    Misti A Lillo

    2014-06-01T23:59:59.000Z

    The purpose of this guide is to provide a consistent, standardized approach to performing neutronics/physics analysis for experiments inserted into the Advanced Test Reactor (ATR). This document provides neutronics/physics analysis guidance to support experiment design and analysis needs for experiments irradiated in the ATR. This guide addresses neutronics/physics analysis in support of experiment design, experiment safety, and experiment program objectives and goals. The intent of this guide is to provide a standardized approach for performing typical neutronics/physics analyses. Deviation from this guide is allowed provided that neutronics/physics analysis details are properly documented in an analysis report.

  5. Logging-while-coring method and apparatus

    DOE Patents [OSTI]

    Goldberg, David S.; Myers, Gregory J.

    2007-01-30T23:59:59.000Z

    A method and apparatus for downhole coring while receiving logging-while-drilling tool data. The apparatus includes core collar and a retrievable core barrel. The retrievable core barrel receives core from a borehole which is sent to the surface for analysis via wireline and latching tool The core collar includes logging-while-drilling tools for the simultaneous measurement of formation properties during the core excavation process. Examples of logging-while-drilling tools include nuclear sensors, resistivity sensors, gamma ray sensors, and bit resistivity sensors. The disclosed method allows for precise core-log depth calibration and core orientation within a single borehole, and without at pipe trip, providing both time saving and unique scientific advantages.

  6. Logging-while-coring method and apparatus

    DOE Patents [OSTI]

    Goldberg, David S. (New York, NY); Myers, Gregory J. (Cornwall, NY)

    2007-11-13T23:59:59.000Z

    A method and apparatus for downhole coring while receiving logging-while-drilling tool data. The apparatus includes core collar and a retrievable core barrel. The retrievable core barrel receives core from a borehole which is sent to the surface for analysis via wireline and latching tool The core collar includes logging-while-drilling tools for the simultaneous measurement of formation properties during the core excavation process. Examples of logging-while-drilling tools include nuclear sensors, resistivity sensors, gamma ray sensors, and bit resistivity sensors. The disclosed method allows for precise core-log depth calibration and core orientation within a single borehole, and without at pipe trip, providing both time saving and unique scientific advantages.

  7. Analysis & Design of Active Inductor

    E-Print Network [OSTI]

    Rana, Dibyendu

    2014-03-05T23:59:59.000Z

    Inductor DC bus voltage capped at 800 V by bleeder resistor .......... 59 Figure 39: Circuit diagram for experimental setup ........................................................ 60 Figure 40: Experimental setup for 200 W, three phase diode rectifier... ................................................................................. 79 Figure 57: Thyristor based CSI with Active Inductor emulating the reactor ................. 80 Figure 58: Relative core losses at 20 kHz. Reprinted with permission from [58] ......... 86 Figure 59: Nanocrystalline core (Vitoperm) core loss...

  8. Needs Analysis for Dimethyl Mercury

    SciTech Connect (OSTI)

    Schmoldt, Michael J.

    2013-02-13T23:59:59.000Z

    For this needs analysis, a total of 131 DMHg analytical results were collected and reviewed from the Hanford Tank Farms from 2004 to 2007. Sampling data from the Site Wide Industrial Hygiene Database (SWIHO), the Tank waste inventory System (TWINs), and prior sampling campaigns by CH2M Hill Hanford that were not available in the SWIHD database, were aggregated for analysis. Technical literature used by the Savannah River Site (SRS). Bechtel RPP·WTP, and CH2M Hill Hanford from 2003-2007, were also reviewed to identify potential DMHg exposure concerns applicable to the tank farms. After analyzing the adequacy of lhe data, information gaps were identified and recommendations for corrective actions items were developed.

  9. Building Energy Monitoring and Analysis

    SciTech Connect (OSTI)

    Hong, Tianzhen; Feng, Wei; Lu, Alison; Xia, Jianjun; Yang, Le; Shen, Qi; Im, Piljae; Bhandari, Mahabir

    2013-06-01T23:59:59.000Z

    This project aimed to develop a standard methodology for building energy data definition, collection, presentation, and analysis; apply the developed methods to a standardized energy monitoring platform, including hardware and software, to collect and analyze building energy use data; and compile offline statistical data and online real-time data in both countries for fully understanding the current status of building energy use. This helps decode the driving forces behind the discrepancy of building energy use between the two countries; identify gaps and deficiencies of current building energy monitoring, data collection, and analysis; and create knowledge and tools to collect and analyze good building energy data to provide valuable and actionable information for key stakeholders.

  10. Method of multivariate spectral analysis

    DOE Patents [OSTI]

    Keenan, Michael R.; Kotula, Paul G.

    2004-01-06T23:59:59.000Z

    A method of determining the properties of a sample from measured spectral data collected from the sample by performing a multivariate spectral analysis. The method can include: generating a two-dimensional matrix A containing measured spectral data; providing a weighted spectral data matrix D by performing a weighting operation on matrix A; factoring D into the product of two matrices, C and S.sup.T, by performing a constrained alternating least-squares analysis of D=CS.sup.T, where C is a concentration intensity matrix and S is a spectral shapes matrix; unweighting C and S by applying the inverse of the weighting used previously; and determining the properties of the sample by inspecting C and S. This method can be used to analyze X-ray spectral data generated by operating a Scanning Electron Microscope (SEM) with an attached Energy Dispersive Spectrometer (EDS).

  11. Residential solar home resale analysis

    SciTech Connect (OSTI)

    Noll, S.A.

    1980-01-01T23:59:59.000Z

    One of the determinants of the market acceptance of solar technologies in the residential housing sector is the value placed upon the solar property at the time of resale. The resale factor is shown to be an important economic parameter when net benefits of the solar design are considered over a typical ownership cycle rather than the life cycle of the system. Although a study of solar resale in Davis, Ca, indicates that those particular homes have been appreciating in value faster than nonsolar market comparables, no study has been made that would confirm this conclusion for markets in other geograhical locations with supporting tests of statistical significance. The data to undertake such an analysis is available through numerous local sources; however, case by case data collection is prohibitively expensive. A recommended alternative approach is to make use of real estate market data firms who compile large data bases and provide multi-variate statistical analysis packages.

  12. Voltammetric analysis apparatus and method

    DOE Patents [OSTI]

    Almon, A.C.

    1993-06-08T23:59:59.000Z

    An apparatus and method is described for electrochemical analysis of elements in solution. An auxiliary electrode, a reference electrode, and five working electrodes are positioned in a container containing a sample solution. The working electrodes are spaced apart evenly from each other and the auxiliary electrode to minimize any inter-electrode interference that may occur during analysis. An electric potential is applied between the auxiliary electrode and each of the working electrodes. Simultaneous measurements taken of the current flow through each of the working electrodes for each given potential in a potential range are used for identifying chemical elements present in the sample solution and their respective concentrations. Multiple working electrodes enable a more positive identification to be made by providing unique data characteristic of chemical elements present in the sample solution.

  13. Ion mobility analysis of lipoproteins

    DOE Patents [OSTI]

    Benner, W. Henry (Danville, CA); Krauss, Ronald M. (Berkeley, CA); Blanche, Patricia J. (Berkeley, CA)

    2007-08-21T23:59:59.000Z

    A medical diagnostic method and instrumentation system for analyzing noncovalently bonded agglomerated biological particles is described. The method and system comprises: a method of preparation for the biological particles; an electrospray generator; an alpha particle radiation source; a differential mobility analyzer; a particle counter; and data acquisition and analysis means. The medical device is useful for the assessment of human diseases, such as cardiac disease risk and hyperlipidemia, by rapid quantitative analysis of lipoprotein fraction densities. Initially, purification procedures are described to reduce an initial blood sample to an analytical input to the instrument. The measured sizes from the analytical sample are correlated with densities, resulting in a spectrum of lipoprotein densities. The lipoprotein density distribution can then be used to characterize cardiac and other lipid-related health risks.

  14. Analysis of Reactor Physics Experiment for the Irradiated LWR MOX Fuels

    SciTech Connect (OSTI)

    Katsuyuki; Kawashima; Toru, Yamamoto; Katsuichiro, Kamimura [Japan Nuclear Energy Safety Organization, Tokyu Reit Toranomon Bldg. 7F, 3-17-1, Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

    2006-07-01T23:59:59.000Z

    As an important part to validate the LWR core neutronics analysis methods, Japan Nuclear Energy Safety Organization (JNES) has been participating in the REBUS international program and performing analyses and evaluations of the reactor physics experiment data including the irradiated fuels. In REBUS program, physics experiments were performed at the VENUS critical test facility in SCK/CEN, Belgium, in which the five core configurations were tested. In each core configuration, the central part of the 3.3%- and 4%-enriched UO{sub 2} fuel core was replaced by the test bundle of (1)fresh MOX fuel, (2)medium-burnup MOX fuel, (3)high-burnup MOX fuel, (4)fresh UO{sub 2} fuel, and (5)irradiated UO{sub 2} fuel. Measured parameters are critical water level, water level reactivity, fission rate distributions, and neutron flux distributions. In this paper, the results of the fresh MOX and medium-burnup MOX core critical experiments and analysis are presented. The medium-burnup MOX fuel used in this test is 6.9% in initial fissile enrichment and the burnup averaged over the fuel rods is 20 GWd/t. In the core critical analysis, a continuous energy Monte Carlo code MVP was used with the JENDL-3.2 nuclear data library as well as a deterministic analysis code SRAC. The calculated results are compared with the experimental ones. (authors)

  15. Analysis of hydrogen isotope mixtures

    DOE Patents [OSTI]

    Villa-Aleman, Eliel (Aiken, SC)

    1994-01-01T23:59:59.000Z

    An apparatus and method for determining the concentrations of hydrogen isotopes in a sample. Hydrogen in the sample is separated from other elements using a filter selectively permeable to hydrogen. Then the hydrogen is condensed onto a cold finger or cryopump. The cold finger is rotated as pulsed laser energy vaporizes a portion of the condensed hydrogen, forming a packet of molecular hydrogen. The desorbed hydrogen is ionized and admitted into a mass spectrometer for analysis.

  16. System for analysis of explosives

    DOE Patents [OSTI]

    Haas, Jeffrey S. (San Ramon, CA)

    2010-06-29T23:59:59.000Z

    A system for analysis of explosives. Samples are spotted on a thin layer chromatography plate. Multi-component explosives standards are spotted on the thin layer chromatography plate. The thin layer chromatography plate is dipped in a solvent mixture and chromatography is allowed to proceed. The thin layer chromatography plate is dipped in reagent 1. The thin layer chromatography plate is heated. The thin layer chromatography plate is dipped in reagent 2.

  17. Devonian shale production data analysis

    SciTech Connect (OSTI)

    Koziar, G.

    1984-05-01T23:59:59.000Z

    Analysis of Devonian shale production histories without careful data screening can easily mislead even the most exacting investigator. Trends established from cumulative production data may not accurately represent the true production pattern. The difference between a good well and a poorer producer may be the result of fracture depletion or the length of actual producing time (among other factors) rather than a change in reservoir quality. The use of matrix controlled production information, derived from decline curves, appears to resolve this problem.

  18. Analysis Patterns for Oil Refineries

    E-Print Network [OSTI]

    Lei Zhen; Guangzhen Shao

    We present analysis patterns to describe the structure of oil refineries. The Refinery Produc tion Unit Pattern describes the structure of units and unit groups. The Oil Storage Pattern describes the structure of tanks and tank groups. The Oil Delivery Pattern describes the structure of stations for import and export of oil. The Production Process Pattern describes the productionprocess. The audience for this paper includes analysts, designers, and programmers who are involved in developing Refinery Information Systems.

  19. The VERITAS standard data analysis

    E-Print Network [OSTI]

    M. K. Daniel; for the VERITAS collaboration

    2007-09-25T23:59:59.000Z

    VERITAS is an array of Imaging Atmospheric Cherenkov Telescopes designed for very high energy gamma ray (E>100,GeV) observations of astrophysical sources. The experiment began its scientific observation program in the 2006/2007 observing season. We describe here the analysis chain for reducing the data, reconstructing the direction and energy of incident gamma rays and the rejection of background cosmic rays.

  20. Systems Analysis | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data CenterEnergyGlossaryProgramRussiaSpaceNewsSustainableSystems Analysis

  1. Failure Analysis of Ceramic Components

    SciTech Connect (OSTI)

    B.W. Morris

    2000-06-29T23:59:59.000Z

    Ceramics are being considered for a wide range of structural applications due to their low density and their ability to retain strength at high temperatures. The inherent brittleness of monolithic ceramics requires a departure from the deterministic design philosophy utilized to analyze metallic structural components. The design program ''Ceramic Analysis and Reliability Evaluation of Structures Life'' (CARES/LIFE) developed by NASA Lewis Research Center uses a probabilistic approach to predict the reliability of monolithic components under operational loading. The objective of this study was to develop an understanding of the theories used by CARES/LIFE to predict the reliability of ceramic components and to assess the ability of CARES/LIFE to accurately predict the fast fracture behavior of monolithic ceramic components. A finite element analysis was performed to determine the temperature and stress distribution of a silicon carbide O-ring under diametral compression. The results of the finite element analysis were supplied as input into CARES/LIFE to determine the fast fracture reliability of the O-ring. Statistical material strength parameters were calculated from four-point flexure bar test data. The predicted reliability showed excellent correlation with O-ring compression test data indicating that the CARES/LIFE program can be used to predict the reliability of ceramic components subjected to complicated stress states using material properties determined from simple uniaxial tensile tests.

  2. Model building techniques for analysis.

    SciTech Connect (OSTI)

    Walther, Howard P.; McDaniel, Karen Lynn; Keener, Donald; Cordova, Theresa Elena; Henry, Ronald C.; Brooks, Sean; Martin, Wilbur D.

    2009-09-01T23:59:59.000Z

    The practice of mechanical engineering for product development has evolved into a complex activity that requires a team of specialists for success. Sandia National Laboratories (SNL) has product engineers, mechanical designers, design engineers, manufacturing engineers, mechanical analysts and experimentalists, qualification engineers, and others that contribute through product realization teams to develop new mechanical hardware. The goal of SNL's Design Group is to change product development by enabling design teams to collaborate within a virtual model-based environment whereby analysis is used to guide design decisions. Computer-aided design (CAD) models using PTC's Pro/ENGINEER software tools are heavily relied upon in the product definition stage of parts and assemblies at SNL. The three-dimensional CAD solid model acts as the design solid model that is filled with all of the detailed design definition needed to manufacture the parts. Analysis is an important part of the product development process. The CAD design solid model (DSM) is the foundation for the creation of the analysis solid model (ASM). Creating an ASM from the DSM currently is a time-consuming effort; the turnaround time for results of a design needs to be decreased to have an impact on the overall product development. This effort can be decreased immensely through simple Pro/ENGINEER modeling techniques that summarize to the method features are created in a part model. This document contains recommended modeling techniques that increase the efficiency of the creation of the ASM from the DSM.

  3. Efficiency of static core turn-off in a system-on-a-chip with variation

    DOE Patents [OSTI]

    Cher, Chen-Yong; Coteus, Paul W; Gara, Alan; Kursun, Eren; Paulsen, David P; Schuelke, Brian A; Sheets, II, John E; Tian, Shurong

    2013-10-29T23:59:59.000Z

    A processor-implemented method for improving efficiency of a static core turn-off in a multi-core processor with variation, the method comprising: conducting via a simulation a turn-off analysis of the multi-core processor at the multi-core processor's design stage, wherein the turn-off analysis of the multi-core processor at the multi-core processor's design stage includes a first output corresponding to a first multi-core processor core to turn off; conducting a turn-off analysis of the multi-core processor at the multi-core processor's testing stage, wherein the turn-off analysis of the multi-core processor at the multi-core processor's testing stage includes a second output corresponding to a second multi-core processor core to turn off; comparing the first output and the second output to determine if the first output is referring to the same core to turn off as the second output; outputting a third output corresponding to the first multi-core processor core if the first output and the second output are both referring to the same core to turn off.

  4. Systems Analysis Workshop List of Attendees

    Broader source: Energy.gov [DOE]

    List of Attendees from DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  5. INTERACTIVE ANALYSIS AND DISPLAY OF TABULAR DATA

    E-Print Network [OSTI]

    Benson, W.H.

    2010-01-01T23:59:59.000Z

    July 1976. Kitous,B. Interactive matrix displays andSS98{~ tA(!. -3.2 . I INTERACTIVE ANALYSIS AND DISPLAY OF ·owned rights. ~j • 6 U I INTERACTIVE ANALYSIS AND DISPLAY OF

  6. Data Analysis and Mining at NERSC

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

    Mining Data Analysis and Mining microCTdani.jpg Data analysis techniques include post-processing (e.g., data statistics) of experimental datasets andor simulation output, as well...

  7. Contributions to the analysis of proteins

    E-Print Network [OSTI]

    Sharifi Sedeh, Reza

    2011-01-01T23:59:59.000Z

    Proteins are essential to organisms and play a central role in almost every biological process. The analysis of the conformational dynamics and mechanics of proteins using numerical methods, such as normal mode analysis ...

  8. Flame Spectral Analysis for Boiler Control 

    E-Print Network [OSTI]

    Metcalfe, C. I.; Cole, W. E.; Batra, S. K.

    1987-01-01T23:59:59.000Z

    FLAME SPECTRAL ANALYSIS FOR BOILER CONTROL CHRISTOPHER I. METCALFE WILLIAM E. COLE SUSHIL K. BATRA Tecogen, Inc. ( A Subsidiary of Thermo Electron Corporation) Waltham, Massachusetts ABSTRACT SPECTRAL FLAME ANALYSIS FOR BURNER CONTROL During...

  9. Transportation Analysis, Modeling, and Simulation (TAMS) Application

    E-Print Network [OSTI]

    Transportation Analysis, Modeling, and Simulation (TAMS) Application Center for Transportation Passenger Flows Supply Chain Efficiency Transportation: Energy Environment Safety Security Vehicle Technologies T he Center for Transportation Analysis (CTA) TAMS application is a web-based tool that supports

  10. Eugene Solid Waste Management Market Analysis

    E-Print Network [OSTI]

    Oregon, University of

    Eugene Solid Waste Management Market Analysis Prepared By: Mitchell Johnson Alex Sonnichsen #12;Eugene Solid Waste Management Market Analysis May 2012 Page 1 Summary This study examines the economic impact of the solid waste management system

  11. System architecture analysis and selection under uncertainty

    E-Print Network [OSTI]

    Smaling, Rudolf M

    2005-01-01T23:59:59.000Z

    A system architecture analysis and selection methodology is presented that builds on the Multidisciplinary Analysis and Optimization framework. It addresses a need and opportunity to extend the MAO techniques to include a ...

  12. Semantic Social Network Analysis, a concrete case

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Semantic Social Network Analysis, a concrete case Guillaume Erétéo, Orange Labs, guillaume permitting a high degree of interaction between participants, and social network analysis (SNA) seeks) shared by the members of these networks. These enriched representations of social networks, combined

  13. Energy Analysis of the Texas Capitol Restoration

    E-Print Network [OSTI]

    Hunn, B. D.; Banks, J. A.; Reddy, S. N.

    This paper presents the methodology and results of a detailed energy analysis of the Texas Capitol Restoration. The purpose of this analysis was two-fold: 1) to determine the projected energy cost savings of a series of design alternatives...

  14. EXPERIMENTAL ANALYSIS OF HEURISTICS FOR THE ...

    E-Print Network [OSTI]

    2010-01-08T23:59:59.000Z

    mental analysis [16], systematic experimental analysis of heuristic algorithms .... flow-shop [31], printed circuit board assembly [4], reconstructing sequential order from inaccurate ..... linear time algorithm of Manku [23] or Punnen and Nair [29].

  15. 2012 U.S. Vehicle Analysis

    E-Print Network [OSTI]

    Lam, Ho Yeung Michael

    2012-01-01T23:59:59.000Z

    and Air Quality. Green Vehicle Guide. Web. May 2012. 2. "Los Angeles 2012 U.S. Vehicle Analysis A thesis submitted inOF THE THESIS 2012 U.S. Vehicle Analysis by Ho Yeung Michael

  16. Recommendations for the Supplement Analysis Process

    Energy Savers [EERE]

    Site (DOEEIS-0229-SA2, February 2002) - DOE analyzed use of KAMS for storage of surplus, non-pit plutonium for up to 50 years. This made the analysis consistent with the analysis...

  17. Job Safety Analysis College/Department/Unit

    E-Print Network [OSTI]

    Saskatchewan, University of

    Job Safety Analysis (JSA) College/Department/Unit: Title of Job Activity: Oven Location of Activity and understanding the Job Safety Analysis: Date Name (Print) Signature #12;JSA # Page 3 Basic Job Steps Possible

  18. Energy analysis program. 1994 annual report

    SciTech Connect (OSTI)

    Levine, M.D.

    1995-04-01T23:59:59.000Z

    This report provides an energy analysis overview. The following topics are described: building energy analysis; urban and energy environmental issues; appliance energy efficiency standards; utility planning and policy; energy efficiency, economics, and policy issues; and international energy and environmental issues.

  19. Cost Analysis of Hydrogen Storage Systems

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

    Cost Analysis of Hydrogen Cost Analysis of Hydrogen Storage Systems Storage Systems TIAX LLC 15 Acorn Park Cambridge, MA 02140-2390 Tel. 617- 498-5000 Fax 617-498-7200...

  20. SUBSURFACE VISUAL ALARM SYSTEM ANALYSIS

    SciTech Connect (OSTI)

    D.W. Markman

    2001-08-06T23:59:59.000Z

    The ''Subsurface Fire Hazard Analysis'' (CRWMS M&O 1998, page 61), and the document, ''Title III Evaluation Report for the Surface and Subsurface Communication System'', (CRWMS M&O 1999a, pages 21 and 23), both indicate the installed communication system is adequate to support Exploratory Studies Facility (ESF) activities with the exception of the mine phone system for emergency notification purposes. They recommend the installation of a visual alarm system to supplement the page/party phone system The purpose of this analysis is to identify data communication highway design approaches, and provide justification for the selected or recommended alternatives for the data communication of the subsurface visual alarm system. This analysis is being prepared to document a basis for the design selection of the data communication method. This analysis will briefly describe existing data or voice communication or monitoring systems within the ESF, and look at how these may be revised or adapted to support the needed data highway of the subsurface visual alarm. system. The existing PLC communication system installed in subsurface is providing data communication for alcove No.5 ventilation fans, south portal ventilation fans, bulkhead doors and generator monitoring system. It is given that the data communication of the subsurface visual alarm system will be a digital based system. It is also given that it is most feasible to take advantage of existing systems and equipment and not consider an entirely new data communication system design and installation. The scope and primary objectives of this analysis are to: (1) Briefly review and describe existing available data communication highways or systems within the ESF. (2) Examine technical characteristics of an existing system to disqualify a design alternative is paramount in minimizing the number of and depth of a system review. (3) Apply general engineering design practices or criteria such as relative cost, and degree of difficulty and complexity in determining requirements in adapting existing data communication highways to support the subsurface visual alarm system. These requirements would include such things as added or new communication cables, added Programmable Logic Controller (PLC), Inputs and Outputs (I/O), and communication hardware components, and human machine interfaces and their software operating system. (4) Select the best data communication highway system based on this review of adapting or integrating with existing data communication systems.

  1. Microlocal Analysis of Thermoacoustic (or ... - Purdue University

    E-Print Network [OSTI]

    Plamen Stefanov

    2012-07-20T23:59:59.000Z

    Microlocal Analysis of Thermoacoustic (or Multiwave). Tomography, III. Plamen Stefanov. Purdue University. TAT of brain imaging (discontinuous wave speed).

  2. Optimization Online - Analysis of mixed integer programming ...

    E-Print Network [OSTI]

    Thiago Henrique Nogueira

    2014-07-15T23:59:59.000Z

    Jul 15, 2014 ... Analysis of mixed integer programming formulations for single machine scheduling problems with sequence dependent setup times and ...

  3. DATA MONITORING AND ANALYSIS PROGRAM MANUAL

    E-Print Network [OSTI]

    Gravois, Melanie

    2007-01-01T23:59:59.000Z

    charts and analysis guidelines can be found in common textbooks and guidebooks on Statistical Process Control (SPC).

  4. Tensor Principal Component Analysis via Convex Optimization

    E-Print Network [OSTI]

    Bo Jiang

    2012-12-11T23:59:59.000Z

    Dec 11, 2012 ... Keywords: Tensor; Principal Component Analysis; Low Rank; Nuclear Norm; Semidefinite Programming Relaxation. Category 1: Convex and ...

  5. Biomass Compositional Analysis Laboratory (Fact Sheet), National...

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

    Providing detailed and accurate characterization of the chemical composition of biomass feedstocks, intermediates, and products Compositional Analysis Service Capabilities...

  6. Analysis of accidents during flashing operations

    E-Print Network [OSTI]

    Obermeyer, Michael Edward

    1993-01-01T23:59:59.000Z

    University, 1976 Federal Highway Administration Study, 1980 San Francisco Study National Study Portland, Oregon Study Summary of Literature Review Studies 13 14 16 17 20 CHAPTER Page III. ACCIDENT ANALYSIS METHODOLOGY . 22 Study Site Location... V. SUMMARY AND FINDINGS 44 REFERENCES 48 VITA 50 LIST OF TABLES TABLE 1. Groupings for Marson's Accident Analysis 2. Groupings for San Francisco Accident Analysis 3. Groupings for Portland Accident Analysis 4. Sample Sizes by Volume Ratio 5...

  7. Biomass Compositional Analysis Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-07-01T23:59:59.000Z

    This fact sheet provides information about Biomass Compositional Analysis Laboratory (BCAL) capabilities and applications at NREL's National Bioenergy Center.

  8. MEASUREMENT AND ANALYSIS OF CIRCUMSOLAR RADIATION

    E-Print Network [OSTI]

    Grether, Donald

    2013-01-01T23:59:59.000Z

    cloud transient studies); Sandia, Albuquerque (input to performance calculation program Helios); SERI (analysis of effect of circumsolar radiation

  9. Compiler Construction Lecture 3: Lexical Analysis II

    E-Print Network [OSTI]

    Ábrahám, Erika

    Compiler Construction Lecture 3: Lexical Analysis II (Extended Matching Problem) Thomas Noll-Longest-Match Analysis 5 Implementation of FLM Analysis Compiler Construction Summer Semester 2012 3.2 #12;Lexical Construction Summer Semester 2012 3.3 #12;The DFA Method I Known from Formal Systems, Automata and Processes

  10. GIS Analysis GIS 6116 -Spring 2015

    E-Print Network [OSTI]

    Watson, Craig A.

    ). Geospatial Analysis (4th ed.). Leicester: Matador. Available online at httpGIS Analysis GIS 6116 - Spring 2015 School of Forest Resources and Conservation Geomatics Program _______________________________________________________________________________________ 1 GIS 6116 (GIS Analysis) INSTRUCTORS: Dr. Hartwig Henry Hochmair (FLREC Fort Lauderdale) Dr. Amr

  11. Hierarchical Linear Discriminant Analysis for Beamforming

    E-Print Network [OSTI]

    Park, Haesun

    model of h-LDA by relating it to the two-way multivariate analysis of variance (MANOVA), which fits well dimension reduction, hierarchical linear discriminant analysis (h-LDA) to a well-known spatial localization1 Hierarchical Linear Discriminant Analysis for Beamforming Jaegul Choo , Barry L. Drake

  12. Analysis methods for Atmospheric Cerenkov Telescopes

    E-Print Network [OSTI]

    Mathieu de Naurois

    2006-07-12T23:59:59.000Z

    Three different analysis techniques for Atmospheric Imaging System are presented. The classical Hillas parameters based technique is shown to be robust and efficient, but more elaborate techniques can improve the sensitivity of the analysis. A comparison of the different analysis techniques shows that they use different information for gamma-hadron separation, and that it is possible to combine their qualities.

  13. Analysis of Water Modeling of Air Entrainment

    E-Print Network [OSTI]

    Beckermann, Christoph

    Analysis of Water Modeling of Air Entrainment S.C. Jain Professor and Research Engineer Dept. Civil, C., "Analysis of Water Modeling of Air Entrainment," in Proceedings of the 48th SFSA Technical An analysis is reported of the water modeling experiments of Bates et al. (1994) to study air entrainment

  14. DATA MONITORING AND ANALYSIS PROGRAM MANUAL

    E-Print Network [OSTI]

    DATA MONITORING AND ANALYSIS PROGRAM MANUAL LBNL/PUB-5519 (3), Rev. 0 Effective Date: _July 23 Data Monitoring and Analysis Program Manual REVISION HISTORY Revision Date Revision Description #12;LBNL/PUB-5519 (3), Rev. 0 Page 3 of 23 Data Monitoring and Analysis Program Manual TABLE OF CONTENTS

  15. Automated Eye-Movement Protocol Analysis

    E-Print Network [OSTI]

    Salvucci, Dario D.

    Automated Eye-Movement Protocol Analysis Dario D. Salvucci and John R. Anderson Carnegie Mellon analysis of eye-movement protocols. Although eye movements have be- come increasingly popular as a tool an ap- proach to automating eye-movement protocol analysis by means of tracing--re- lating observed eye

  16. Quantitative Methods of Policy Analysis Spring 2013

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    ENVS 5120 Quantitative Methods of Policy Analysis Spring 2013 Lecture: M/W 5:00-6:15pm Class. Some of these practical skill sets include: basic research design, cost-benefit analysis, risk and skill sets that are commonly used in the professional world of policymaking and policy analysis. Some

  17. Systematic risk analysis: first steps towards

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    implementable. Keywords: Quantitative finance, risk analysis, beta, alpha, trends, technical analysisSystematic risk analysis: first steps towards a new definition of beta Michel FLIESS , Cédric JOIN studies systematic (or market) risks in quantitative finance via the well known coefficient (see, e

  18. : : ". RSST I Lunar Day Counter Reliability Analysis

    E-Print Network [OSTI]

    Rathbun, Julie A.

    : : ". RSST I Lunar Day Counter Reliability Analysis NO. ATM 846 PAGE 1 REV. MO. OF 10 DATE 12/3/69 This ATM presents a Reliability analysis of the Lunar Day Counter, the Resettable Solid State Timer (RSST equipment. The analysis is based on a parts count, average failure rates and two (2) years operation

  19. Finite Element Analysis in Vertebrate Biomechanics

    E-Print Network [OSTI]

    Finite Element Analysis in Vertebrate Biomechanics CALLUM F. ROSS* Department of Organismal Biology presents a series of papers that apply the method of finite element analysis (FEA) to questions ontogenetic or phylogenetic transformations. © 2005 Wiley-Liss, Inc. Key words: finite-element analysis

  20. 309 Building deactivation mission analysis report

    SciTech Connect (OSTI)

    Lund, D.P.

    1995-05-24T23:59:59.000Z

    This report presents the results of the 309 Building (Plutonium Fuels Utilization Program) Deactivation Project mission analysis. Hanford systems engineering (SE) procedures call for a mission analysis. The mission analysis is an important first step in the SE process. The functions and requirements to successfully accomplish this mission, the selected alternatives and products will later be defined using the SE process.

  1. 308 Building deactivation mission analysis report

    SciTech Connect (OSTI)

    Lund, D.P.

    1995-05-24T23:59:59.000Z

    This report presents the results of the 308 Building (Fuels Development Laboratory) Deactivation Project mission analysis. Hanford systems engineering (SE) procedures call for a mission analysis. The mission analysis is an important first step in the SE process. The functions and requirements to successfully accomplish this mission, the selected alternatives and products will later be defined using the SE process.

  2. Lectures on Survival Analysis Richard D. Gill

    E-Print Network [OSTI]

    Gill, Richard D.

    in survival analysis--is product-integration, and to begin with I have tried to cover its basic theory in fair1 Lectures on Survival Analysis Richard D. Gill Mathematical Institute, University Utrecht `topics in and around survival analysis which interest me at the moment, with an audience of French

  3. MODAL ENERGY ANALYSIS Nicolas Totaro1*

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    MODAL ENERGY ANALYSIS Nicolas Totaro1* , Jean-Louis Guyader1 1 Laboratoire Vibrations Acoustique.totaro@insa-lyon.fr Keywords: Energy methods, non resonant, pure tone, Statistical Energy Analysis, MODENA. ABSTRACT The Modal Energy Analysis presented in this paper is a method to predict energy exchanges between vibro

  4. Principal Components Analysis for Binary Data

    E-Print Network [OSTI]

    Lee, Seokho

    2010-07-14T23:59:59.000Z

    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ix CHAPTER I INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Formulations of Principal Components Analysis . . . . . . . . 2 1.2 Generalization of Sparse Principal Components Analysis to Binary Variables... . . . . . . . . . . . . . . . . . . . . . . . . 8 1.3 Review of Estimation Procedures . . . . . . . . . . . . . . . . 11 1.4 Overview of Dissertation . . . . . . . . . . . . . . . . . . . . . 18 II SPARSE PRINCIPAL COMPONENTS ANALYSIS FOR BI- NARY DATA...

  5. Image patch analysis of sunspots and active regions. I. Intrinsic dimension and correlation analysis

    E-Print Network [OSTI]

    Moon, Kevin R; Delouille, Veronique; De Visscher, Ruben; Watson, Fraser; Hero, Alfred O

    2015-01-01T23:59:59.000Z

    Complexity of an active region is related to its flare-productivity. Mount Wilson or McIntosh sunspot classifications measure such complexity but in a categorical way, and may therefore not use all the information present in the observations. Moreover, such categorical schemes hinder a systematic study of an active region's evolution for example. We propose fine-scale quantitative descriptors for an active region's complexity and relate them to the Mount Wilson classification. We analyze the local correlation structure within continuum and magnetogram data, as well as the cross-correlation between continuum and magnetogram data. We compute the intrinsic dimension, partial correlation, and canonical correlation analysis (CCA) of image patches of continuum and magnetogram active region images taken from the SOHO-MDI instrument. We use masks of sunspots derived from continuum as well as larger masks of magnetic active regions derived from the magnetogram to analyze separately the core part of an active region fr...

  6. A streamlined failure mode and effects analysis

    SciTech Connect (OSTI)

    Ford, Eric C., E-mail: eford@uw.edu; Smith, Koren; Terezakis, Stephanie; Croog, Victoria; Gollamudi, Smitha; Gage, Irene; Keck, Jordie; DeWeese, Theodore; Sibley, Greg [Department of Radiation Oncology and Molecular Radiation Sciences, Johns Hopkins University, Baltimore, MD 21287 (United States)] [Department of Radiation Oncology and Molecular Radiation Sciences, Johns Hopkins University, Baltimore, MD 21287 (United States)

    2014-06-15T23:59:59.000Z

    Purpose: Explore the feasibility and impact of a streamlined failure mode and effects analysis (FMEA) using a structured process that is designed to minimize staff effort. Methods: FMEA for the external beam process was conducted at an affiliate radiation oncology center that treats approximately 60 patients per day. A structured FMEA process was developed which included clearly defined roles and goals for each phase. A core group of seven people was identified and a facilitator was chosen to lead the effort. Failure modes were identified and scored according to the FMEA formalism. A risk priority number,RPN, was calculated and used to rank failure modes. Failure modes with RPN > 150 received safety improvement interventions. Staff effort was carefully tracked throughout the project. Results: Fifty-two failure modes were identified, 22 collected during meetings, and 30 from take-home worksheets. The four top-ranked failure modes were: delay in film check, missing pacemaker protocol/consent, critical structures not contoured, and pregnant patient simulated without the team's knowledge of the pregnancy. These four failure modes hadRPN > 150 and received safety interventions. The FMEA was completed in one month in four 1-h meetings. A total of 55 staff hours were required and, additionally, 20 h by the facilitator. Conclusions: Streamlined FMEA provides a means of accomplishing a relatively large-scale analysis with modest effort. One potential value of FMEA is that it potentially provides a means of measuring the impact of quality improvement efforts through a reduction in risk scores. Future study of this possibility is needed.

  7. Canister Storage Building (CSB) Hazard Analysis Report

    SciTech Connect (OSTI)

    POWERS, T.B.

    2000-03-16T23:59:59.000Z

    This report describes the methodology used in conducting the Canister Storage Building (CSB) Hazard Analysis to support the final CSB Safety Analysis Report and documents the results. This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the CSB final safety analysis report (FSAR) and documents the results. The hazard analysis process identified hazardous conditions and material-at-risk, determined causes for potential accidents, identified preventive and mitigative features, and qualitatively estimated the frequencies and consequences of specific occurrences. The hazard analysis was performed by a team of cognizant CSB operations and design personnel, safety analysts familiar with the CSB, and technical experts in specialty areas. The material included in this report documents the final state of a nearly two-year long process. Attachment A provides two lists of hazard analysis team members and describes the background and experience of each. The first list is a complete list of the hazard analysis team members that have been involved over the two-year long process. The second list is a subset of the first list and consists of those hazard analysis team members that reviewed and agreed to the final hazard analysis documentation. The material included in this report documents the final state of a nearly two-year long process involving formal facilitated group sessions and independent hazard and accident analysis work. The hazard analysis process led to the selection of candidate accidents for further quantitative analysis. New information relative to the hazards, discovered during the accident analysis, was incorporated into the hazard analysis data in order to compile a complete profile of facility hazards. Through this process, the results of the hazard and accident analyses led directly to the identification of safety structures, systems, and components, technical safety requirements, and other controls required to protect the public, workers, and environment.

  8. Psy 992 Social Network Analysis Syllabus 1 Social Network Analysis (Psy 992)

    E-Print Network [OSTI]

    Liu, Taosheng

    Psy 992 Social Network Analysis Syllabus 1 Social Network Analysis (Psy 992) Fall 2012 Instructor: Social network analysis is a distinct approach to research that focuses on the structure of relationships collection methodologies, and analysis of social networks. Specifically, we will begin the course by focusing

  9. Asset-based poverty analysis in rural Bangladesh: A comparison of principal component analysis and

    E-Print Network [OSTI]

    Mound, Jon

    1 Asset-based poverty analysis in rural Bangladesh: A comparison of principal component analysis not be regarded as the views of SRI or The University of Leeds. #12;3 Asset-based poverty analysis in rural The trend towards multi-dimensional poverty assessment ..................... 5 Principal component analysis

  10. Submitted to: Finite Elements in Analysis and Design Finite Element Analysis over Tangled Simplicial Meshes

    E-Print Network [OSTI]

    Suresh, Krishnan

    Submitted to: Finite Elements in Analysis and Design 1 Finite Element Analysis over Tangled In modern finite element analysis (FEA), a mesh is said to be `tangled' if it contains one or more inverted are also illustrated. 1. INTRODUCTION In modern finite element analysis (FEA), the underlying mesh

  11. Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture

    DOE Patents [OSTI]

    West, Phillip B. (Idaho Falls, ID); Novascone, Stephen R. (Idaho Falls, ID); Wright, Jerry P. (Idaho Falls, ID)

    2012-05-29T23:59:59.000Z

    Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture are described. According to one embodiment, an earth analysis method includes engaging a device with the earth, analyzing the earth in a single substantially lineal direction using the device during the engaging, and providing information regarding a subsurface feature of the earth using the analysis.

  12. Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture

    DOE Patents [OSTI]

    West, Phillip B. (Idaho Falls, ID); Novascone, Stephen R. (Idaho Falls, ID); Wright, Jerry P. (Idaho Falls, ID)

    2011-09-27T23:59:59.000Z

    Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture are described. According to one embodiment, an earth analysis method includes engaging a device with the earth, analyzing the earth in a single substantially lineal direction using the device during the engaging, and providing information regarding a subsurface feature of the earth using the analysis.

  13. Discrete analysis of stochastic NMR

    SciTech Connect (OSTI)

    Wong, Sam Tak-Sum

    1988-12-01T23:59:59.000Z

    Stochastic NMR is an efficient technique for high field in vivo imaging and spectroscopic studies in cases where the peak rf power required may be prohibitively high for conventional pulsed NMR techniques. This dissertation presents a theoretical analysis of a stochastic NMR method of acquiring spectroscopy data. The spin system is excited with rf pulses where the flip angles or the phases of the pulses are samples of a discrete stochastic process. The method is formulated as a stochastic difference equation which is then converted to ordinary deterministic difference equations describing the input-output cross-correlation, average signal power and signal power spectrum. The solutions of these equations are used to evaluate the stochastic, technique in terms of peak rf power requirement, spectral distortions and signal-to-noise ratio. Experimental results are also presented which verify the results of the discrete analysis. The analysis shows that the maximum signal-to-noise ratio is achieved when the RMS flip angle is approximately the Ernst angle. When the RMS flip angle is below the Ernst angle, the input-output cross-correlation is a good estimate of the FID. Increase of excitation power causes line broadening. In addition, the use of random flip angle, fixed phase excitation causes a notch artifact and non-uniform response across the spectrum both of which are not found in two new types of excitation, the random phase excitation and the random quadrature excitation. The signal power spectrum is also a good estimate of the real spectrum. The approximation of the cross-correlation by a time average causes systematic noise. The amount of systematic noise is found to be significantly reduced when an entire maximum length sequence (MLS) is used for excitation. Noise-like distortion at high power MLS excitation is discovered to be related to the number of feedback paths in the MLS generator. 29 refs., 58 figs.

  14. Quantitative WDS analysis using electron probe microanalyzer

    SciTech Connect (OSTI)

    Ul-Hamid, Anwar [Research Institute, King Fahd University of Petroleum and Minerals, P.O. Box 1073, Dhahran 31261 (Saudi Arabia)]. E-mail: anwar@kfupm.edu.sa; Tawancy, Hani M. [Research Institute, King Fahd University of Petroleum and Minerals, P.O. Box 1073, Dhahran 31261 (Saudi Arabia); Mohammed, Abdul-Rashid I. [Research Institute, King Fahd University of Petroleum and Minerals, P.O. Box 1073, Dhahran 31261 (Saudi Arabia); Al-Jaroudi, Said S. [Saudi Aramco, P.O. Box 65, Tanajib 31311 (Saudi Arabia); Abbas, Nureddin M. [Research Institute, King Fahd University of Petroleum and Minerals, P.O. Box 1073, Dhahran 31261 (Saudi Arabia)

    2006-04-15T23:59:59.000Z

    In this paper, the procedure for conducting quantitative elemental analysis by ZAF correction method using wavelength dispersive X-ray spectroscopy (WDS) in an electron probe microanalyzer (EPMA) is elaborated. Analysis of a thermal barrier coating (TBC) system formed on a Ni-based single crystal superalloy is presented as an example to illustrate the analysis of samples consisting of a large number of major and minor elements. The analysis was performed by known standards and measured peak-to-background intensity ratios. The procedure for using separate set of acquisition conditions for major and minor element analysis is explained and its importance is stressed.

  15. Hierarchical Analysis of the Omega Ontology

    SciTech Connect (OSTI)

    Joslyn, Cliff A.; Paulson, Patrick R.

    2009-12-01T23:59:59.000Z

    Initial delivery for mathematical analysis of the Omega Ontology. We provide an analysis of the hierarchical structure of a version of the Omega Ontology currently in use within the US Government. After providing an initial statistical analysis of the distribution of all link types in the ontology, we then provide a detailed order theoretical analysis of each of the four main hierarchical links present. This order theoretical analysis includes the distribution of components and their properties, their parent/child and multiple inheritance structure, and the distribution of their vertical ranks.

  16. Chemical substructure analysis in toxicology

    SciTech Connect (OSTI)

    Beauchamp, R.O. Jr. [Center for Information on Toxicology and Environment, Raleigh, NC (United States)

    1990-12-31T23:59:59.000Z

    A preliminary examination of chemical-substructure analysis (CSA) demonstrates the effective use of the Chemical Abstracts compound connectivity file in conjunction with the bibliographic file for relating chemical structures to biological activity. The importance of considering the role of metabolic intermediates under a variety of conditions is illustrated, suggesting structures that should be examined that may exhibit potential activity. This CSA technique, which utilizes existing large files accessible with online personal computers, is recommended for use as another tool in examining chemicals in drugs. 2 refs., 4 figs.

  17. The Independent Technical Analysis Process

    SciTech Connect (OSTI)

    Duberstein, Corey A.; Ham, Kenneth D.; Dauble, Dennis D.; Johnson, Gary E.

    2007-04-13T23:59:59.000Z

    The Bonneville Power Administration (BPA) contracted with the Pacific Northwest National Laboratory (PNNL) to provide technical analytical support for system-wide fish passage information (BPA Project No. 2006-010-00). The goal of this project was to produce rigorous technical analysis products using independent analysts and anonymous peer reviewers. In the past, regional parties have interacted with a single entity, the Fish Passage Center to access the data, analyses, and coordination related to fish passage. This project provided an independent technical source for non-routine fish passage analyses while allowing routine support functions to be performed by other well-qualified entities.

  18. Foucault's Analysis of Power's Methodologies

    E-Print Network [OSTI]

    Scott, Gary Alan

    that, for Foucault, truth does not exist outside of a complex relation of power/knowledge. Since any claim to truth has purchase only within a particular power/knowledge relation, truth cannot be thought to control, constrain, or judge power...FOUCAULT'S ANALYSIS OF POWER'S M E T H O D O L O G I E S Gary Alan Scott Siena College Part 4 of The Will to Know, where Foucault turns to his most direct treatment of power, contains the often-cited statement, "In political thought...

  19. MPQC: Performance Analysis and Optimization

    SciTech Connect (OSTI)

    Sarje, Abhinav; Williams, Samuel; Bailey, David

    2012-11-30T23:59:59.000Z

    MPQC (Massively Parallel Quantum Chemistry) is a widely used computational quantum chemistry code. It is capable of performing a number of computations commonly occurring in quantum chemistry. In order to achieve better performance of MPQC, in this report we present a detailed performance analysis of this code. We then perform loop and memory access optimizations, and measure performance improvements by comparing the performance of the optimized code with that of the original MPQC code. We observe that the optimized MPQC code achieves a significant improvement in the performance through a better utilization of vector processing and memory hierarchies.

  20. Analysis of Feed Melting Procesess

    SciTech Connect (OSTI)

    Matyas, Josef; Hrma, Pavel R.; Kim, Dong-Sang

    2003-05-12T23:59:59.000Z

    An efficient waste-glass melter with a sustained, high-volume glass throughput will allow a smaller vitrification facility, a shorter lifecycle, and glass with a higher concentration of waste. The vitrification process of two feeds that exhibited different rates of conversion was studied using thermal analyses, including evolved gas analysis with volume-expansion monitoring. Quantitative X-ray diffraction and scanning electron microscopy were performed on quenched samples. The difference in the melting rates was attributed to different melt viscosities at the temperature at which the melt interfaces the cold cap. It was suggested that low viscosity destabilizes foam under the cold cap, thus enhancing the rate of melting.