National Library of Energy BETA

Sample records for test critical components

  1. Abrasion Testing of Critical Components of Hydrokinetic Devices

    SciTech Connect (OSTI)

    Worthington, Monty; Ali, Muhammad; Ravens, Tom

    2013-12-06

    The objective of the Abrasion Testing of Critical Components of Hydrokinetic Devices (Project) was to test critical components of hydrokinetic devices in waters with high levels of suspended sediment – information that is widely applicable to the hydrokinetic industry. Tidal and river sites in Alaska typically have high suspended sediment concentrations. High suspended sediment also occurs in major rivers and estuaries throughout the world and throughout high latitude locations where glacial inputs introduce silt into water bodies. In assessing the vulnerability of technology components to sediment induced abrasion, one of the greatest concerns is the impact that the sediment may have on device components such as bearings and seals, failures of which could lead to both efficiency loss and catastrophic system failures.

  2. Status of the Boeing Dish Engine Critical Component Project

    SciTech Connect (OSTI)

    Brau, H.W.; Diver, R.B.; Nelving, H.; Stone, K.W.

    1999-01-08

    The Boeing Company's Dish Engine Critical Component (DECC) project started in April of 1998. It is a continuation of a solar energy program started by McDonnell Douglas (now Boeing) and United Stirling of Sweden in the mid 1980s. The overall objectives, schedule, and status of this project are presented in this paper. The hardware test configuration, hardware background, operation, and test plans are also discussed. A summary is given of the test data, which includes the daily power performance, generated energy, working-gas usage, mirror reflectivity, solar insolation, on-sun track time, generating time, and system availability. The system performance based upon the present test data is compared to test data from the 1984/88 McDonnell Douglas/United Stirling AB/Southem California Edison test program. The test data shows that the present power, energy, and mirror performance is comparable to when the hardware was first manufactured 14 years ago.

  3. Critical heat flux test apparatus

    DOE Patents [OSTI]

    Welsh, Robert E.; Doman, Marvin J.; Wilson, Edward C.

    1992-01-01

    An apparatus for testing, in situ, highly irradiated specimens at high temperature transients is provided. A specimen, which has a thermocouple device attached thereto, is manipulated into test position in a sealed quartz heating tube by a robot. An induction coil around a heating portion of the tube is powered by a radio frequency generator to heat the specimen. Sensors are connected to monitor the temperatures of the specimen and the induction coil. A quench chamber is located below the heating portion to permit rapid cooling of the specimen which is moved into this quench chamber once it is heated to a critical temperature. A vacuum pump is connected to the apparatus to collect any released fission gases which are analyzed at a remote location.

  4. Fueling Components Testing and Certification

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

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

  5. Component evaluation testing and analysis algorithms.

    SciTech Connect (OSTI)

    Hart, Darren M.; Merchant, Bion John

    2011-10-01

    The Ground-Based Monitoring R&E Component Evaluation project performs testing on the hardware components that make up Seismic and Infrasound monitoring systems. The majority of the testing is focused on the Digital Waveform Recorder (DWR), Seismic Sensor, and Infrasound Sensor. In order to guarantee consistency, traceability, and visibility into the results of the testing process, it is necessary to document the test and analysis procedures that are in place. Other reports document the testing procedures that are in place (Kromer, 2007). This document serves to provide a comprehensive overview of the analysis and the algorithms that are applied to the Component Evaluation testing. A brief summary of each test is included to provide the context for the analysis that is to be performed.

  6. Testing, Manufacturing, and Component Development Projects

    Office of Energy Efficiency and Renewable Energy (EERE)

    This report covers the Wind and Water Power Technologies Office's testing, manufacturing, and component development projects for utility-scale and distributed wind energy from fiscal years 2006 to 2014.

  7. Testing Subgroup Workshop on Critical Property Needs

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

    Testing Subgroup Workshop on Critical Property Needs Tim Armstrong September, 2007 Presented at AMSE/PWG Joint Meeting Participants Kevin Klug, David Moyer - CTC Paul Bakke - DOE David McColskey, Richard Ricker - NIST Zhili Feng, Steve Pawel, Govindarajan Muralidharan - ORNL Brian Somerday - SNL Andrew Duncan - SRNL Petros Safronis - U. Illinois Objectives Develop an action plan that: * details the necessary tests to measure and compare the physical properties of metallic materials relevant to

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

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2010-05-05

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

  9. Critical Issues in NPH Categorization and Limit State Selection of Structures, Systems, and Components

    Broader source: Energy.gov [DOE]

    Critical Issues in NPH Categorization and Limit State Selection of Structures, Systems, and Components Quazi Hossain Lawrence Livermore National Laboratory

  10. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2011-10-13

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment

  11. NGNP Component Test Capability Design Code of Record

    SciTech Connect (OSTI)

    S.L. Austad; D.S. Ferguson; L.E. Guillen; C.W. McKnight; P.J. Petersen

    2009-09-01

    The Next Generation Nuclear Plant Project is conducting a trade study to select a preferred approach for establishing a capability whereby NGNP technology development testing—through large-scale, integrated tests—can be performed for critical HTGR structures, systems, and components (SSCs). The mission of this capability includes enabling the validation of interfaces, interactions, and performance for critical systems and components prior to installation in the NGNP prototype.

  12. Fueling Components Testing and Certification | Department of Energy

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

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

  13. AVTA: Battery Testing - Electric Drive and Advanced Battery and Components

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

    Testbed | Department of Energy Battery Testing - Electric Drive and Advanced Battery and Components Testbed AVTA: Battery Testing - Electric Drive and Advanced Battery and Components Testbed The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future

  14. Heavy-ion Accelerators for Testing Microelectronic Components...

    Office of Science (SC) Website

    Print Text Size: A A A FeedbackShare Page Applicationinstrumentation: Use of heavy-ion accelerators for testing microelectronic components for space radiation effects Developed ...

  15. Testing universality in critical exponents: The case of rainfall...

    Office of Scientific and Technical Information (OSTI)

    Title: Testing universality in critical exponents: The case of rainfall Authors: Deluca, Anna ; Puig, Pedro ; Corral, lvaro Publication Date: 2016-04-01 OSTI Identifier: 1245042 ...

  16. Testing Subgroup Workshop on Critical Property Needs

    Broader source: Energy.gov [DOE]

    Objectives: Develop an action plan that details the necessary tests to measure and compare the physical properties of metallic materials relevant to high pressure hydrogen service

  17. Quality Assurance Program Application for the Component Test Capability

    SciTech Connect (OSTI)

    Stephanin L. Austad

    2009-06-01

    This paper documents the application of quality requirements to Component Test Capability (CTC) Project activities for each CTC alternative. Four alternatives are considered for quality program application: do nothing, vendor testing, existing testing facility modification, and Component Test Facility. It also describes the advantages and disadvantages of using the existing Next Generation Nuclear Plant Quality Program Plan with CTC modifications versus a stand-alone CTC Quality Program Plan.

  18. Task 8 -- Design and test of critical components

    SciTech Connect (OSTI)

    Chance, T.F.

    1996-11-01

    This report covers tasks 8.1, 8.1.1, and 8.2. The primary objective of Task 8.1, Particulates Flow Deposition, is to characterize the particulate generated in an operating gas turbine combined cycle (GTCC) power plant whose configuration approximates that proposed for an ATS power plant. In addition, the task is to evaluate the use of full-flow filtering to reduce the steam particulate loads. Before the start of this task, GE had already negotiated an agreement with the candidate power plant, piping and a filter unit had already been installed at the power plant site, and major elements of the data acquisition system had been purchased. The objective of Task 8.1.1, Coolant Purity, is to expose typical ATS gas turbine airfoil cooling channel geometries to real steam flow to determine whether there are any unexpected deposit formations. The task is a static analog of the centrifugal deposition rig trials of Task 8.2, in which a bucket channel return bend is exposed to steam flow. Two cooling channel geometries are of primary interest in this static exposure. The primary objective of Task 8.2, Particle Centrifugal Sedimentation, is to determine the settling characteristics of particles in a cooling stream from an operating gas turbine combined cycle (GTCC) power plant when that stream is ducted through a passage experiencing the G-loads expected in a simulated bucket channel specimen representative of designs proposed for an ATS gas turbine.

  19. Critical density for Landau damping in a two-electron-component plasma

    SciTech Connect (OSTI)

    Rupp, Constantin F.; López, Rodrigo A.; Araneda, Jaime A.

    2015-10-15

    The asymptotic evolution of an initial perturbation in a collisionless two-electron-component plasma with different temperatures is studied numerically. The transition between linear and nonlinear damping regimes is determined by slowly varying the density of the secondary electron-component using high-resolution Vlasov-Poisson simulations. It is shown that, for fixed amplitude perturbations, this transition behaves as a critical phenomenon with time scales and field amplitudes exhibiting power-law dependencies on the threshold density, similar to the critical amplitude behavior in a single-component plasma.

  20. Evaluation of Integrated High Temperature Component Testing Needs

    SciTech Connect (OSTI)

    Rafael Soto; David Duncan; Vincent Tonc

    2009-05-01

    This paper describes the requirements for a large-scale component test capability to support the development of advanced nuclear reactor technology and their adaptation to commercial applications that advance U.S. energy economy, reliability, and security and reduce carbon emissions.

  1. CMI Unique Facility: Filtration Test Facility | Critical Materials

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

    Institute Filtration Test Facility filtration set up for CMI unique facility at Idaho National Laboratory The Filtration Test Facility is one of more than a dozen unique facilities developed by the Critical Materials Institute, an Energy Innovation Hub of the U.S. Department of Energy. The chemical separation of materials is often water-intensive. It is important to establish filtration methods that are both efficient and environmentally sound. Mineral processing streams are particularly

  2. Testing of optical components to assure performance in a high acerage power environment

    SciTech Connect (OSTI)

    Chow, R.; Taylor, J.R.; Eickelberg, W.K.; Primdahl, K.A.

    1997-06-24

    Evaluation and testing of the optical components used in the Atomic Vapor Laser Isotope Separation (AVLIS) plant is critical for qualification of suppliers, development of new optical multilayer designs and monufacturing processes, and assurance of performance in the production cycle. The range of specifications requires development of specialized test equipment and methods which are not routine or readily available in industry. Specifications are given on material characteristics such as index homogeneity, subsurface damage left after polishing, microscopic surface defects and contamination, coating absorption, and high average power laser damage. The approach to testing these performance characteristics and assuring the quality throughout the production cycle is described.

  3. Heavy-ion Accelerators for Testing Microelectronic Components at LBNL |

    Office of Science (SC) Website

    U.S. DOE Office of Science (SC) Heavy-ion Accelerators for Testing Microelectronic Components at LBNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear Science Applications of Nuclear Science Archives Small Business Innovation Research / Small Business Technology Transfer Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy

  4. RoboRave Rally tests Northern New Mexico students' critical thinking...

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

    tests students' critical thinking, teamwork skills RoboRave Rally tests Northern New Mexico students' critical thinking, teamwork skills Teams from schools in Rio Arriba, Taos,...

  5. Field Testing of Nano-PCM Enhanced Building Envelope Components

    SciTech Connect (OSTI)

    Biswas, Kaushik; Childs, Phillip W; Atchley, Jerald Allen

    2013-08-01

    The U.S. Department of Energy s (DOE) Building Technologies Program s goal of developing high-performance, energy efficient buildings will require more cost-effective, durable, energy efficient building envelopes. Forty-eight percent of the residential end-use energy consumption is spent on space heating and air conditioning. Reducing envelope-generated heating and cooling loads through application of phase change material (PCM)-enhanced envelope components can facilitate maximizing the energy efficiency of buildings. Field-testing of prototype envelope components is an important step in estimating their energy benefits. An innovative phase change material (nano-PCM) was developed with PCM encapsulated with expanded graphite (interconnected) nanosheets, which is highly conducive for enhanced thermal storage and energy distribution, and is shape-stable for convenient incorporation into lightweight building components. During 2012, two test walls with cellulose cavity insulation and prototype PCM-enhanced interior wallboards were installed in a natural exposure test (NET) facility at Charleston, SC. The first test wall was divided into four sections, which were separated by wood studs and thin layers of foam insulation. Two sections contained nano-PCM-enhanced wallboards: one was a three-layer structure, in which nano-PCM was sandwiched between two gypsum boards, and the other one had PCM dispersed homogeneously throughout graphite nanosheets-enhanced gypsum board. The second test wall also contained two sections with interior PCM wallboards; one contained nano-PCM dispersed homogeneously in gypsum and the other was gypsum board containing a commercial microencapsulated PCM (MEPCM) for comparison. Each test wall contained a section covered with gypsum board on the interior side, which served as control or a baseline for evaluation of the PCM wallboards. The walls were instrumented with arrays of thermocouples and heat flux transducers. Further, numerical modeling of

  6. LEGOS: Object-based software components for mission-critical systems. Final report, June 1, 1995--December 31, 1997

    SciTech Connect (OSTI)

    1998-08-01

    An estimated 85% of the installed base of software is a custom application with a production quantity of one. In practice, almost 100% of military software systems are custom software. Paradoxically, the marginal costs of producing additional units are near zero. So why hasn`t the software market, a market with high design costs and low productions costs evolved like other similar custom widget industries, such as automobiles and hardware chips? The military software industry seems immune to market pressures that have motivated a multilevel supply chain structure in other widget industries: design cost recovery, improve quality through specialization, and enable rapid assembly from purchased components. The primary goal of the ComponentWare Consortium (CWC) technology plan was to overcome barriers to building and deploying mission-critical information systems by using verified, reusable software components (Component Ware). The adoption of the ComponentWare infrastructure is predicated upon a critical mass of the leading platform vendors` inevitable adoption of adopting emerging, object-based, distributed computing frameworks--initially CORBA and COM/OLE. The long-range goal of this work is to build and deploy military systems from verified reusable architectures. The promise of component-based applications is to enable developers to snap together new applications by mixing and matching prefabricated software components. A key result of this effort is the concept of reusable software architectures. A second important contribution is the notion that a software architecture is something that can be captured in a formal language and reused across multiple applications. The formalization and reuse of software architectures provide major cost and schedule improvements. The Unified Modeling Language (UML) is fast becoming the industry standard for object-oriented analysis and design notation for object-based systems. However, the lack of a standard real-time distributed

  7. Bench wear testing of engine power cylinder components

    SciTech Connect (OSTI)

    Patterson, D.J.; Hill, S.H.; Tung, S.C.

    1993-02-01

    A need exists for an accurate and repeatable friction and wear bench test for engine power cylinder components that more closely relates to engine test results. Current research and development includes investigation of new engine designs, materials, coatings and surface treatments for reduced weight, longer life, higher operating temperature, and reduced friction. Alternative fuels being examined include alcohols and gaseous fuels, as well as reformulated gasolines and distillate fuels. Concurrently, new lubricants are being formulated for the new engine and fuel combinations. Because of the enormous cost and time of developing commercial engine, fuel and lubricant combinations by means of engine testing alone, much interest is being focused on more representative and repeatable bench tests. This paper examines some known bench testers employing either rotary or reciprocating motion for evaluating the friction, wear, and durability of material couples. Information is presented on experience and practice with one rotary (Falex type) and two reciprocating testers (Cameron-Plint and a new design, the EMA-L59). Some correlation with engine data is given.

  8. Reactor Testing and Qualification: Prioritized High-level Criticality Testing Needs

    SciTech Connect (OSTI)

    S. Bragg-Sitton; J. Bess; J. Werner; G. Harms; S. Bailey

    2011-09-01

    Researchers at the Idaho National Laboratory (INL) were tasked with reviewing possible criticality testing needs to support development of the fission surface power system reactor design. Reactor physics testing can provide significant information to aid in development of technologies associated with small, fast spectrum reactors that could be applied for non-terrestrial power systems, leading to eventual system qualification. Several studies have been conducted in recent years to assess the data and analyses required to design and build a space fission power system with high confidence that the system will perform as designed [Marcille, 2004a, 2004b; Weaver, 2007; Parry et al., 2008]. This report will provide a summary of previous critical tests and physics measurements that are potentially applicable to the current reactor design (both those that have been benchmarked and those not yet benchmarked), summarize recent studies of potential nuclear testing needs for space reactor development and their applicability to the current baseline fission surface power (FSP) system design, and provide an overview of a suite of tests (separate effects, sub-critical or critical) that could fill in the information database to improve the accuracy of physics modeling efforts as the FSP design is refined. Some recommendations for tasks that could be completed in the near term are also included. Specific recommendations on critical test configurations will be reserved until after the sensitivity analyses being conducted by Los Alamos National Laboratory (LANL) are completed (due August 2011).

  9. Prediction of critical heat flux in water-cooled plasma facing components using computational fluid dynamics.

    SciTech Connect (OSTI)

    Bullock, James H.; Youchison, Dennis Lee; Ulrickson, Michael Andrew

    2010-11-01

    Several commercial computational fluid dynamics (CFD) codes now have the capability to analyze Eulerian two-phase flow using the Rohsenow nucleate boiling model. Analysis of boiling due to one-sided heating in plasma facing components (pfcs) is now receiving attention during the design of water-cooled first wall panels for ITER that may encounter heat fluxes as high as 5 MW/m2. Empirical thermalhydraulic design correlations developed for long fission reactor channels are not reliable when applied to pfcs because fully developed flow conditions seldom exist. Star-CCM+ is one of the commercial CFD codes that can model two-phase flows. Like others, it implements the RPI model for nucleate boiling, but it also seamlessly transitions to a volume-of-fluid model for film boiling. By benchmarking the results of our 3d models against recent experiments on critical heat flux for both smooth rectangular channels and hypervapotrons, we determined the six unique input parameters that accurately characterize the boiling physics for ITER flow conditions under a wide range of absorbed heat flux. We can now exploit this capability to predict the onset of critical heat flux in these components. In addition, the results clearly illustrate the production and transport of vapor and its effect on heat transfer in pfcs from nucleate boiling through transition to film boiling. This article describes the boiling physics implemented in CCM+ and compares the computational results to the benchmark experiments carried out independently in the United States and Russia. Temperature distributions agreed to within 10 C for a wide range of heat fluxes from 3 MW/m2 to 10 MW/m2 and flow velocities from 1 m/s to 10 m/s in these devices. Although the analysis is incapable of capturing the stochastic nature of critical heat flux (i.e., time and location may depend on a local materials defect or turbulence phenomenon), it is highly reliable in determining the heat flux where boiling instabilities begin

  10. The principal component analysis method used with polynomial Chaos expansion to propagate uncertainties through critical transport problems

    SciTech Connect (OSTI)

    Rising, M. E.; Prinja, A. K.

    2012-07-01

    A critical neutron transport problem with random material properties is introduced. The total cross section and the average neutron multiplicity are assumed to be uncertain, characterized by the mean and variance with a log-normal distribution. The average neutron multiplicity and the total cross section are assumed to be uncorrected and the material properties for differing materials are also assumed to be uncorrected. The principal component analysis method is used to decompose the covariance matrix into eigenvalues and eigenvectors and then 'realizations' of the material properties can be computed. A simple Monte Carlo brute force sampling of the decomposed covariance matrix is employed to obtain a benchmark result for each test problem. In order to save computational time and to characterize the moments and probability density function of the multiplication factor the polynomial chaos expansion method is employed along with the stochastic collocation method. A Gauss-Hermite quadrature set is convolved into a multidimensional tensor product quadrature set and is successfully used to compute the polynomial chaos expansion coefficients of the multiplication factor. Finally, for a particular critical fuel pin assembly the appropriate number of random variables and polynomial expansion order are investigated. (authors)

  11. Battery systems performance studies - HIL components testing | Department

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

    of Energy vss_16_shidore.pdf (1.92 MB) More Documents & Publications HEV, PHEV, BEV Test Standard Validation J1634 SAE BEV Test Procedures HEV, PHEV, EV Test Standard Development and Validation

  12. NREL: Water Power Research - Device and Component Testing

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

    NREL houses the nation's premier laboratory facilities for testing offshore wind and water ... to obtain high-resolution measurements in the laboratory and open water test sites. ...

  13. NREL: TroughNet - Parabolic Trough System and Component Testing

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

    in an operating power plant environment. ... test stand using electric resistance heating to measure the thermal losses from parabolic ... of mirrors coming off the production line. ...

  14. NGNP – Creating Validated TRL and TDRMs for Critical Systems, Subsystems, and Components

    SciTech Connect (OSTI)

    John W. Collins; John M. Beck; Emmanuel O. Opare; Layne F. Pincock

    2008-09-01

    This report introduces two draft Next Generation Nuclear Plant (NGNP) Technology Development Roadmaps (TDRMs) and documents the methods used to create them. As such, this report depicts the development of the hardware needed to successfully operate the NGNP and identifies this hardware by the area of the plant it supports and by system, subsystem, and component (SSC). Several options exist for which technologies are selected to fulfill the functions of the NGNP. These options are represented by differing SSCs and are grouped into reference designs. Each SSC associated with each reference design is evaluated, rated, and assigned a technology readiness level (TRL). A rollup of the TRLs allows for comparison of the various reference designs. A TDRM then documents the tasks needed to obtain information in key discriminating criteria to support technology down selection and the tasks and test required to sufficiently mature the technology and reduce the likelihood of technological failure upon installation. This report presents the path forward, methods, and tools used to understand the requirements, manage the uncertainty, and mitigate the risk for the NGNP project. The key tool, TDRMs, is the means to facilitate NGNP risk-informed decision making, technology down selection, and technology qualification and maturation while serving to coordinate engineering, research and development, and licensing efforts.

  15. Analysis of components from drip tests with ATM-10 glass

    SciTech Connect (OSTI)

    Fortner, J.A.; Bates, J.K.; Gerding, T.J.

    1996-09-01

    Waste package assemblies consisting of actinide-doped West Valley ATM-10 reference glass and sensitized 304L stainless steel have been reacted with simulated repository groundwater using the Unsaturated Test Method. Analyses of surface corrosion and reaction products resulting from tests that were terminated at scheduled intervals between 13 and 52 weeks are reported. Analyses reveal complex interactions between the groundwater, the sensitized stainless steel waste form holder, and the glass. Alteration phases form that consist mainly of smectite clay, brockite, and an amorphous thorium iron titanium silicate, the latter two incorporating thorium, uranium, and possibly transuranics. The results from the terminated tests, combined with data from tests that are still ongoing, will help determine the suitability of glass waste forms in the proposed high-level repository at the Yucca Mountain Site.

  16. A review of DOE HEPA filter component test activities

    SciTech Connect (OSTI)

    Slawski, J.W.; Bresson, J.F.; Scripsick, R.C.

    1997-08-01

    All HEPA filters purchased for installation in DOE nuclear facilities are required to be tested at a Filter Test Facility (FTF) prior to installation. The number of HEPA filters purchased by DOE has been reduced so much that the Hanford FTF was closed. From Fiscal Year (FY) 1992 to 1994, funding was not provided to the FTF Technical Support Group (TSG) at the Los Alamos National Laboratory. As a consequence, Round Robin Tests (RRTs), performed twice each year by the FTFs to assess constituency of test results among the FTFs, were not performed in FY 1992 and FY 1993. The Annual Reports of FTF test activities were not prepared for FY 1992 - 1995. Technical support provided to the FTFs was minimal. There is talk of closing a second FTF, and ongoing discussions as to whether DOE will continue to fund operation of the FTFs. In FY 1994, DOE Defense Programs commenced funding the TSG. RRT data for FY 1994 and 1995 have been entered into the database; the FY 1994 RRT report has been issued; and the FY 1995 RRT report is in progress. Data from semiannual reports have been retrieved and entered into the database. Standards related to HEPA filter test and procurement activities are now scheduled for issuance by FY 1996. Continuation of these activities depends on whether DOE will continue to support the HEPA filter test program. The history and activities of the FTFs and the TSG at Los Alamos have been reported at previous Air Cleaning Conferences. Data from the FY 1991 Annual Report of FTF activities was presented at the 1992 Air Cleaning Conference. Preparation of the Annual Reports was temporarily suspended in 1992. However, all of the FTF Semiannual report data have been retrieved and entered into the data base. This paper focuses primarily on the results of HEPA filter tests conducted by FTFs during FY 1992 - FY 1995, and the possible effects of the DOE program uncertainties on the quality of HEPA filters for installation at the DOE sites. 15 refs., 13 tabs.

  17. NNSA Completes its Critical Radar Arming and Fuzing Test for...

    National Nuclear Security Administration (NNSA)

    and Fuzing Test for the W88 ALT 370 September 25, 2014 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) recently completed an important test for the W88 ...

  18. Engineering development of selective agglomeration: Task 6, Operation of the Component Development Test Facility

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

    The objective of this report is to summarize the component development and laboratory binder test work at Wilsonville during Task 6. This Task included the construction and startup of the Component Development Test Facility (CDTF), coal procurement, evaluation of unit operation and dewatering performance, laboratory binder tests for diesel and heptane, production characterization, and vendor tests. Data evaluation, interpretation, and analysis are not included in this report, but will be discussed in the Task 7 report.

  19. Methodology to identify risk-significant components for inservice inspection and testing

    SciTech Connect (OSTI)

    Anderson, M.T.; Hartley, R.S.; Jones, J.L. Jr.; Kido, C.; Phillips, J.H.

    1992-08-01

    Periodic inspection and testing of vital system components should be performed to ensure the safe and reliable operation of Department of Energy (DOE) nuclear processing facilities. Probabilistic techniques may be used to help identify and rank components by their relative risk. A risk-based ranking would allow varied DOE sites to implement inspection and testing programs in an effective and cost-efficient manner. This report describes a methodology that can be used to rank components, while addressing multiple risk issues.

  20. Three-dimensional NDE of VHTR core components via simulation-based testing. Final report

    SciTech Connect (OSTI)

    Guzina, Bojan; Kunerth, Dennis

    2014-09-30

    A next generation, simulation-driven-and-enabled testing platform is developed for the 3D detection and characterization of defects and damage in nuclear graphite and composite structures in Very High Temperature Reactors (VHTRs). The proposed work addresses the critical need for the development of high-fidelity Non-Destructive Examination (NDE) technologies for as-manufactured and replaceable in-service VHTR components. Centered around the novel use of elastic (sonic and ultrasonic) waves, this project deploys a robust, non-iterative inverse solution for the 3D defect reconstruction together with a non-contact, laser-based approach to the measurement of experimental waveforms in VHTR core components. In particular, this research (1) deploys three-dimensional Scanning Laser Doppler Vibrometry (3D SLDV) as a means to accurately and remotely measure 3D displacement waveforms over the accessible surface of a VHTR core component excited by mechanical vibratory source; (2) implements a powerful new inverse technique, based on the concept of Topological Sensitivity (TS), for non-iterative elastic waveform tomography of internal defects - that permits robust 3D detection, reconstruction and characterization of discrete damage (e.g. holes and fractures) in nuclear graphite from limited-aperture NDE measurements; (3) implements state-of-the art computational (finite element) model that caters for accurately simulating elastic wave propagation in 3D blocks of nuclear graphite; (4) integrates the SLDV testing methodology with the TS imaging algorithm into a non-contact, high-fidelity NDE platform for the 3D reconstruction and characterization of defects and damage in VHTR core components; and (5) applies the proposed methodology to VHTR core component samples (both two- and three-dimensional) with a priori induced, discrete damage in the form of holes and fractures. Overall, the newly established SLDV-TS testing platform represents a next-generation NDE tool that surpasses

  1. FFTF thermal-hydraulic testing results affecting piping and vessel component design in LMFBR's

    SciTech Connect (OSTI)

    Stover, R.L.; Beaver, T.R.; Chang, S.C.

    1983-01-01

    The Fast Flux Test Facility completed four years of pre-operational testing in April 1982. This paper describes thermal-hydraulic testing results from this period which impact piping and vessel component design in LMFBRs. Data discussed are piping flow oscillations, piping thermal stratification and vessel upper plenum stratification. Results from testing verified that plant design limits were met.

  2. Design and operation of a rapid thermal transient component testing sodium loop

    SciTech Connect (OSTI)

    Crandall, D.L.

    1984-04-16

    A specific problem developed during the design of an on-line sampling system for the Sodium Loop Safety Facility fast breeder reactor experiments. Rapid fluctuations in the sodium temperature, caused by reactor operation and shutdown, exposed the system components to conditions that could result in fatigue failure. A component test loop was designed and built at the Idaho National Engineering Laboratory to allow experimental qualification of component integrity. This paper outlines test system requirements, describes the design and special features, presents test procedures ad relates significant operating experience.

  3. Structural aging program to assess the adequacy of critical concrete components in nuclear power plants

    SciTech Connect (OSTI)

    Naus, D.J.; Marchbanks, M.F.; Oland, C.B.; Arndt, E.G.

    1989-01-01

    The Structural Aging (SAG) Program is carried out by the Oak Ridge National Laboratory (ORNL) under sponsorship of the United States Nuclear Regulatory Commission (USNRC). The Program has evolved from preliminary studies conducted to evaluate the long-term environmental challenges to light-water reactor safety-related concrete civil structures. An important conclusion of these studies was that a damage methodology, which can provide a quantitative measure of a concrete structure's durability with respect to potential future requirements, needs to be developed. Under the SAG Program, this issue is being addressed through: establishment of a structural materials information center, evaluation of structural component assessment and repair technologies, and development of a quantitative methodology for structural aging determinations. Progress to date of each of these activities is presented as well as future plans. 7 refs., 5 figs.

  4. Testing of Vessel Critical to Hanford Tank Waste Processing Set to Begin

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

    This Year | Department of Energy Testing of Vessel Critical to Hanford Tank Waste Processing Set to Begin This Year Testing of Vessel Critical to Hanford Tank Waste Processing Set to Begin This Year July 28, 2016 - 12:40pm Addthis The 65-ton vessel arrives in Richland. The 65-ton vessel arrives in Richland. RICHLAND, Wash. - A 65-ton vessel critical to determining the safe mixing and processing of radioactive waste at EM's Office of River Protection Waste Treatment and Immobilization Plant

  5. The development and testing of ceramic components in piston engines. Final report

    SciTech Connect (OSTI)

    McEntire, B.J.; Willis, R.W.; Southam, R.E.

    1994-10-01

    Within the past 10--15 years, ceramic hardware has been fabricated and tested in a number of piston engine applications including valves, piston pins, roller followers, tappet shims, and other wear components. It has been shown that, with proper design and installation, ceramics improve performance, fuel economy, and wear and corrosion resistance. These results have been obtained using rig and road tests on both stock and race engines. Selected summaries of these tests are presented in this review paper.

  6. Coal-fired MHD test progress at the component development and integration facility

    SciTech Connect (OSTI)

    Hart, A.T.; Lofftus, D.

    1994-12-31

    The Component and Development and Integration Facility (CDIF) is a Department of Energy test facility operated by MSE, Inc. MSE personnel were responsible for the integration of topping cycle components for the national coal-fired magnetohydrodynamics development program. Initial facility checkout and baseline data generation testing at the CDIF used a 50-megawatt (MW{sub t}), oil-fired combustor (with ash injection to simulate coal slag carryover) coupled to the 1A{sub 1} supersonic channel. In the fall of 1984, a 50-MW{sub t}, pressurized, slag rejecting coal-fired combustor replaced the oil-fired combustor in the test train. In the spring of 1989, a coal-fired precombustor was added to the workhorse test hardware. In the spring of 1992, workhorse hardware was replaced with the prototypic coal-fired test train. Testing during the last year emphasized prototypic hardware testing targeted at longer duration testing, some intermediate checkout testing, and more reliable operation. These phases of testing and the associated facility modifications are discussed. Progress of the proof-of-concept testing, through the time of testing shutdown, is addressed.

  7. An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components

    SciTech Connect (OSTI)

    Holcomb, David Eugene; Cetiner, Sacit M; Flanagan, George F; Peretz, Fred J; Yoder Jr, Graydon L

    2009-11-01

    This report provides guidance on the component testing necessary during the next phase of fluoride salt-cooled high temperature reactor (FHR) development. In particular, the report identifies and describes the reactor component performance and reliability requirements, provides an overview of what information is necessary to provide assurance that components will adequately achieve the requirements, and then provides guidance on how the required performance information can efficiently be obtained. The report includes a system description of a representative test scale FHR reactor. The reactor parameters presented in this report should only be considered as placeholder values until an FHR test scale reactor design is completed. The report focus is bounded at the interface between and the reactor primary coolant salt and the fuel and the gas supply and return to the Brayton cycle power conversion system. The analysis is limited to component level testing and does not address system level testing issues. Further, the report is oriented as a bottom-up testing requirements analysis as opposed to a having a top-down facility description focus.

  8. Critical point of gas-liquid type phase transition and phase equilibrium functions in developed two-component plasma model

    SciTech Connect (OSTI)

    Butlitsky, M. A.; Zelener, B. V.

    2014-07-14

    A two-component plasma model, which we called a shelf Coulomb model has been developed in this work. A Monte Carlo study has been undertaken to calculate equations of state, pair distribution functions, internal energies, and other thermodynamics properties. A canonical NVT ensemble with periodic boundary conditions was used. The motivation behind the model is also discussed in this work. The shelf Coulomb model can be compared to classical two-component (electron-proton) model where charges with zero size interact via a classical Coulomb law. With important difference for interaction of opposite charges: electrons and protons interact via the Coulomb law for large distances between particles, while interaction potential is cut off on small distances. The cut off distance is defined by an arbitrary ? parameter, which depends on system temperature. All the thermodynamics properties of the model depend on dimensionless parameters ? and ? = ?e{sup 2}n{sup 1/3} (where ? = 1/k{sub B}T, n is the particle's density, k{sub B} is the Boltzmann constant, and T is the temperature) only. In addition, it has been shown that the virial theorem works in this model. All the calculations were carried over a wide range of dimensionless ? and ? parameters in order to find the phase transition region, critical point, spinodal, and binodal lines of a model system. The system is observed to undergo a first order gas-liquid type phase transition with the critical point being in the vicinity of ?{sub crit}?13(T{sub crit}{sup *}?0.076),?{sub crit}?1.8(v{sub crit}{sup *}?0.17),P{sub crit}{sup *}?0.39, where specific volume v* = 1/?{sup 3} and reduced temperature T{sup *} = ?{sup ?1}.

  9. (Critical topics of plasma facing materials/plasma facing component data for the next step fusion devices)

    SciTech Connect (OSTI)

    Burchell, T.D.

    1991-01-04

    The Unites States-Japan Workshop P-165 brought together approximately 60 scientists and engineers to discuss critical topics of plasma facing materials and components for the next-step fusion device. In addition to the United States and Japanese participants, there were several guest attendees from Europe. The international makeup of the participants greatly enhanced the success of the workshop. The author jointly chaired a workshop session entitled Impact of Neutron Effects to Plasma Facing Materials and Plasma Facing Component (PFC) Feasibilities for the International Thermonuclear Experimental Reactor (ITER),'' and presented an overview paper on neutron effects and materials selection for the next-step plasma facing devices. The author presented his work on the effects of neutron irradiation on graphites and carbon-carbon (c/c) composite materials, which are strong candidate materials for PFC's in ITER. The workshop addressed many issues of current concern to the PFC/PFM community including: plasma erosion of PFM's; trapping/detrapping of hydrogen isotopes; large machine operating experience; and extent of the materials database.

  10. Concentrating Solar Power Central Receiver Panel Component Fabrication and Testing FINAL REPORT

    SciTech Connect (OSTI)

    McDowell, Michael W; Miner, Kris

    2013-03-30

    The objective of this project is to complete a design of an advanced concentrated solar panel and demonstrate the manufacturability of key components. Then confirm the operation of the key components under prototypic solar flux conditions. This work is an important step in reducing the levelized cost of energy (LCOE) from a central receiver solar power plant. The key technical risk to building larger power towers is building the larger receiver systems. Therefore, this proposed technology project includes the design of an advanced molten salt prototypic sub-scale receiver panel that can be utilized into a large receiver system. Then complete the fabrication and testing of key components of the receive design that will be used to validate the design. This project shall have a significant impact on solar thermal power plant design. Receiver panels of suitable size for utility scale plants are a key element to a solar power tower plant. Many subtle and complex manufacturing processes are involved in producing a reliable, robust receiver panel. Given the substantial size difference between receiver panels manufactured in the past and those needed for large plant designs, the manufacture and demonstration on prototype receiver panel components with representative features of a full-sized panel will be important to improving the build process for commercial success. Given the thermal flux limitations of the test facility, the panel components cannot be rendered full size. Significance changes occurred in the projects technical strategies from project initiation to the accomplishments described herein. The initial strategy was to define cost improvements for the receiver, design and build a scale prototype receiver and test, on sun, with a molten salt heat transport system. DOE had committed to constructing a molten salt heat transport loop to support receiver testing at the top of the NSTTF tower. Because of funding constraints this did not happen. A subsequent plan to

  11. Coal-fired MHD test progress at the Component Development and Integration Facility

    SciTech Connect (OSTI)

    Hart, A.T.; Filius, K.D.; Micheletti, D.A.; Cashell, P.V.

    1993-12-31

    The Component Development and Integration Facility (CDIF) is a Department of Energy test facility operated by MSE, Inc. MSE personnel are responsible for integrated testing of topping cycle components for the national coal-fired magnetohydrodynamics (MHD) development program. Initial facility checkout and baseline data generation testing at the CDIF used a 50-MW{sub t}, oil-fired combustor (with ash injection to simulate coal slag carryover) coupled to the 1A{sub 1} supersonic workhorse channel. In the fall of 1984, a 50-MW{sub t}, pressurized, slag rejecting coal-fired workhorse combustor replaced the oil-fired combustor in the test train. In the spring of 1989, a coal-fired precombustor was added to the test hardware, and current controls were installed in the spring of 1990. In the fall of 1990, the slag rejector was installed. In the spring of 1992, a 50-MW{sub t} pressurized, slag rejecting coal-fired prototypical combustor replaced the workhorse combustor in the test train. A 1A{sub 4} supersonic prototypical channel replaced the 1A{sub 1} workhorse channel in the fall of 1993. This prototypical hardware is slated to be used for the proof-of-concept (POC) testing. Improved facility systems targeting longer duration testing and more reliable operation will be discussed, including the air emissions control and monitoring hardware, oxygen and nitrogen expansion, coal and seed system upgrades, A-Bay modifications, and new solid suspension injection equipment.

  12. CMI Unique Facility: Pilot-Scale Separations Test Bed Facility | Critical

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

    Materials Institute Pilot-Scale Separations Test Bed Facility Pilot-scale separations test bed facility at Idaho National Laboratory A group tours the 30-stage mixer-settler during a meeting at Idaho National Laboratory. This technology was developed for a CMI project. The Pilot-Scale Separations Test Bed Facility is one of more than a dozen unique facilities developed by the Critical Materials Institute, an Energy Innovation Hub of the U.S. Department of Energy. Noting that the CMI Grand

  13. CHARACTERIZATION OF RADIOACTIVITY IN THE REACTOR VESSEL OF THE HEAVY WATER COMPONENT TEST REACTOR

    SciTech Connect (OSTI)

    Vinson, Dennis

    2010-06-01

    The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that was used to test candidate fuel designs for heavy water power reactors. The reactor operated at nominal power of 50 MW{sub th}. The reactor coolant loop operated at 1200 psig and 250 C. Two isolated test loop were designed into the reactor to provide special test conditions. Fig. 1 shows a cut-away view of the reactor. The two loops are contained in four inch diameter stainless steel piping. The HWCTR was operated for only a short duration, from March 1962 to December 1964 in order to test the viability of test fuel elements and other reactor components for use in a heavy water power reactor. The reactor achieved 13,882 MWd of total power while testing 36 different fuel assemblies. In the course of operation, HWCTR experienced the cladding failures of 10 separate test fuel assemblies. In each case, the cladding was breached with some release of fuel core material into the isolated test loop, causing fission product and actinide contamination in the main coolant loop and the liquid and boiling test loops. Despite the contribution of the contamination from the failed fuel, the primary source of radioactivity in the HWCTR vessel and internals is the activation products in the thermal shields, and to a lesser degree, activation products in the reactor vessel walls and liner. A detailed facility characterization report of the HWCTR facility was completed in 1996. Many of the inputs and assumptions in the 1996 characterization report were derived from the HWCTR decommissioning plan published in 1975. The current paper provides an updated assessment of the radioisotopic characteristics of the HWCTR vessel and internals to support decommissioning activities on the facility.

  14. Scaling Analysis Techniques to Establish Experimental Infrastructure for Component, Subsystem, and Integrated System Testing

    SciTech Connect (OSTI)

    Sabharwall, Piyush; O'Brien, James E.; McKellar, Michael G.; Housley, Gregory K.; Bragg-Sitton, Shannon M.

    2015-03-01

    Hybrid energy system research has the potential to expand the application for nuclear reactor technology beyond electricity. The purpose of this research is to reduce both technical and economic risks associated with energy systems of the future. Nuclear hybrid energy systems (NHES) mitigate the variability of renewable energy sources, provide opportunities to produce revenue from different product streams, and avoid capital inefficiencies by matching electrical output to demand by using excess generation capacity for other purposes when it is available. An essential step in the commercialization and deployment of this advanced technology is scaled testing to demonstrate integrated dynamic performance of advanced systems and components when risks cannot be mitigated adequately by analysis or simulation. Further testing in a prototypical environment is needed for validation and higher confidence. This research supports the development of advanced nuclear reactor technology and NHES, and their adaptation to commercial industrial applications that will potentially advance U.S. energy security, economy, and reliability and further reduce carbon emissions. Experimental infrastructure development for testing and feasibility studies of coupled systems can similarly support other projects having similar developmental needs and can generate data required for validation of models in thermal energy storage and transport, energy, and conversion process development. Experiments performed in the Systems Integration Laboratory will acquire performance data, identify scalability issues, and quantify technology gaps and needs for various hybrid or other energy systems. This report discusses detailed scaling (component and integrated system) and heat transfer figures of merit that will establish the experimental infrastructure for component, subsystem, and integrated system testing to advance the technology readiness of components and systems to the level required for commercial

  15. Testing, Manufacturing, and Component Development Projects for Utility-Scale and Distributed Wind Energy, Fiscal Years 2006-2014

    SciTech Connect (OSTI)

    None, None

    2014-04-01

    This report covers the Wind and Water Power Technologies Office's Testing, Manufacturing, and Component Development Projects for Utility-Scale and Distributed Wind Energy from 2006 to 2014.

  16. Developing standard performance testing procedures for material control and accounting components at a site

    SciTech Connect (OSTI)

    Scherer, Carolynn P; Bushlya, Anatoly V; Efimenko, Vladimir F; Ilyanstev, Anatoly; Regoushevsky, Victor I

    2010-01-01

    The condition of a nuclear material control and accountability system (MC&A) and its individual components, as with any system combining technical elements and documentation, may be characterized through an aggregate of values for the various parameters that determine the system's ability to perform. The MC&A system's status may be functioning effectively, marginally or not functioning based on a summary of the values of the individual parameters. This work included a review of the following subsystems, MC&A and Detecting Material Losses, and their respective elements for the material control and accountability system: (a) Elements of the MC&A Subsystem - Information subsystem (Accountancy/Inventory), Measurement subsystem, Nuclear Material Access subsystem, including tamper-indicating device (TID) program, and Automated Information-gathering subsystem; (b) Elements for Detecting Nuclear Material Loses Subsystem - Inventory Differences, Shipper/receiver Differences, Confirmatory Measurements and differences with accounting data, and TID or Seal Violations. In order to detect the absence or loss of nuclear material there must be appropriate interactions among the elements and their respective subsystems from the list above. Additionally this work includes a review of regulatory requirements for the MC&A system component characteristics and criteria that support the evaluation of the performance of the listed components. The listed components had performance testing algorithms and procedures developed that took into consideration the regulatory criteria. The developed MC&A performance-testing procedures were the basis for a Guide for MC&A Performance Testing at the material balance areas (MBAs) of State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering (SSC RF-IPPE).

  17. Phosphorylated SAP155, the spliceosomal component, is localized to chromatin in postnatal mouse testes

    SciTech Connect (OSTI)

    Eto, Ko; Sonoda, Yoshiyuki; Jin, Yuji; Abe, Shin-ichi

    2010-03-19

    SAP155 is an essential component of the spliceosome and its phosphorylation is required for splicing catalysis, but little is known concerning its expression and regulation during spermatogenesis in postnatal mouse testes. We report that SAP155 is ubiquitously expressed in nuclei of germ and Sertoli cells within the seminiferous tubules of 6- and 35-day postpartum (dpp) testes. Analyses by fractionation of testes revealed that (1) phosphorylated SAP155 was found in the fraction containing nuclear structures at 6 dpp in amounts much larger than that at other ages; (2) non-phosphorylated SAP155 was detected in the fraction containing nucleoplasm; and (3) phosphorylated SAP155 was preferentially associated with chromatin. Our findings suggest that the active spliceosome, containing phosphorylated SAP155, performs pre-mRNA splicing on chromatin concomitant with transcription during testicular development.

  18. Seawater test results of open-cycle ocean thermal energy conversion (OC-OTEC) components

    SciTech Connect (OSTI)

    Zangrando, F.; Bharathan, D.; Link, H. ); Panchal, C.B. )

    1994-01-01

    Key components of open-cycle ocean thermal energy conversion systems--the flash evaporator, mist eliminator, passive predeaerator, two surface condenser stages, and two direct-contact condenser stages--have been tested using seawater. These components operate at lower steam pressures and higher inlet noncondensable gas concentrations than do conventional power plant heat exchangers. The rate of heat exchanged between the evaporator and the condenser is on the order of 1.25MW-thermal, requiring a warm seawater flow of about 0.1 m[sup 3]/s; the cold seawater flow is on the order of half the warm water flow. In addition to characterizing the performance of the various components, the system has produced potable water from condensation of the steam produced in the evaporator. The information obtained in these tests is being used to design a larger scale experiment in which net power production is expected to be demonstrate for the first time using OC-OTEC technology.

  19. Criticality Model

    SciTech Connect (OSTI)

    A. Alsaed

    2004-09-14

    The ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003) presents the methodology for evaluating potential criticality situations in the monitored geologic repository. As stated in the referenced Topical Report, the detailed methodology for performing the disposal criticality analyses will be documented in model reports. Many of the models developed in support of the Topical Report differ from the definition of models as given in the Office of Civilian Radioactive Waste Management procedure AP-SIII.10Q, ''Models'', in that they are procedural, rather than mathematical. These model reports document the detailed methodology necessary to implement the approach presented in the Disposal Criticality Analysis Methodology Topical Report and provide calculations utilizing the methodology. Thus, the governing procedure for this type of report is AP-3.12Q, ''Design Calculations and Analyses''. The ''Criticality Model'' is of this latter type, providing a process evaluating the criticality potential of in-package and external configurations. The purpose of this analysis is to layout the process for calculating the criticality potential for various in-package and external configurations and to calculate lower-bound tolerance limit (LBTL) values and determine range of applicability (ROA) parameters. The LBTL calculations and the ROA determinations are performed using selected benchmark experiments that are applicable to various waste forms and various in-package and external configurations. The waste forms considered in this calculation are pressurized water reactor (PWR), boiling water reactor (BWR), Fast Flux Test Facility (FFTF), Training Research Isotope General Atomic (TRIGA), Enrico Fermi, Shippingport pressurized water reactor, Shippingport light water breeder reactor (LWBR), N-Reactor, Melt and Dilute, and Fort Saint Vrain Reactor spent nuclear fuel (SNF). The scope of this analysis is to document the criticality computational method. The criticality

  20. The large-area hybrid-optics CLAS12 RICH detector: Tests of innovative components

    SciTech Connect (OSTI)

    Contalbrigo, M.; Baltzell, N.; Benmokhtar, F.; Barion, L.; Cisbani, E.; El Alaoui, A.; Hafidi, K.; Hoek, M.; Kubarovsky, V.; Lagamba, L.; Lucherini, V.; Malaguti, R.; Mirazita, M.; Montgomery, R.; Movsisyan, A.; Musico, P.; Orecchini, D.; Orlandi, A.; Pappalardo, L.L.; Pereira, S.; Perrino, R.; Phillips, J.; Pisano, S.; Rossi, P.; Squerzanti, S.; Tomassini, S.; Turisini, M.; Viticchiè, A.

    2014-07-01

    A large area ring-imaging Cherenkov detector has been designed to provide clean hadron identification capability in the momentum range from 3 GeV/c to 8 GeV/c for the CLAS12 experiments at the upgraded 12 GeV continuous electron beam accelerator facility of Jefferson Lab to study the 3D nucleon structure in the yet poorly explored valence region by deep-inelastic scattering, and to perform precision measurements in hadronization and hadron spectroscopy. The adopted solution foresees a novel hybrid optics design based on an aerogel radiator, composite mirrors and densely packed and highly segmented photon detectors. Cherenkov light will either be imaged directly (forward tracks) or after two mirror reflections (large angle tracks). The preliminary results of individual detector component tests and of the prototype performance at test-beams are reported here.

  1. Shock Desensitization Effect in the STANAG 4363 Confined Explosive Component Water Gap Test

    SciTech Connect (OSTI)

    Lefrancois, A S; Lee, R S; Tarver, C M

    2006-06-07

    The Explosive Component Water Gap Test (ECWGT) in the Stanag 4363 has been recently investigated to assess the shock sensitivity of lead and booster components having a diameter less than 5 mm. For that purpose, Pentaerythritol Tetranitrate (PETN) based pellets having a height and diameter of 3 mm have been confined by a steel annulus of wall thickness 1-3.5 mm and with the same height as the pellet. 1-mm wall thickness makes the component more sensitive (larger gap). As the wall thickness is increased to 2-mm, the gap increases a lesser amount, but when the wall thickness is increased to 3.5-mm a decrease in sensitivity is observed (smaller gap). This decrease of the water gap has been reproduced experimentally by many nations. Numerical simulations using Ignition and Growth model have been performed in this paper and have reproduced the experimental results for the steel confinement up to 2 mm thick and aluminum confinement. A stronger re-shock following the first input shock from the water is focusing on the axis due to the confinement. The double shock configuration is well-known to lead in some cases to shock desensitization.

  2. ACCELERATED TESTING OF NEUTRON-ABSORBING ALLOYS FOR NUCLEAR CRITICALITY CONTROL

    SciTech Connect (OSTI)

    Ronald E. Mizia

    2011-10-01

    The US Department of Energy requires nuclear criticality control materials be used for storage of highly enriched spent nuclear fuel used in government programs and the storage of commercial spent nuclear fuel at the proposed High-Level Nuclear Waste Geological Repository located at Yucca Mountain, Nevada. Two different metallic alloys (Ni-Cr-Mo-Gd and borated stainless steel) have been chosen for this service. An accelerated corrosion test program to validate these materials for this application is described and a performance comparison is made.

  3. Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility

    SciTech Connect (OSTI)

    S. L. Austad; L. E. Guillen; D. S. Ferguson; B. L. Blakely; D. M. Pace; D. Lopez; J. D. Zolynski; B. L. Cowley; V. J. Balls; E.A. Harvego, P.E.; C.W. McKnight, P.E.; R.S. Stewart; B.D. Christensen

    2008-04-01

    A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: • Identifies pre-conceptual design requirements • Develops test loop equipment schematics and layout • Identifies space allocations for each of the facility functions, as required • Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems • Identifies pre-conceptual utility and support system needs • Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.

  4. EA-1035: Relocation of the Weapons Component Testing Facility Los Alamos National Laboratory, Los Alamos, New Mexico

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to relocate the Weapons Component Testing Facility from Building 450 to Building 207, both within Technical Area 16, at the U.S....

  5. A Residual Mass Ballistic Testing Method to Compare Armor Materials or Components (Residual Mass Ballistic Testing Method)

    SciTech Connect (OSTI)

    Benjamin Langhorst; Thomas M Lillo; Henry S Chu

    2014-05-01

    A statistics based ballistic test method is presented for use when comparing multiple groups of test articles of unknown relative ballistic perforation resistance. The method is intended to be more efficient than many traditional methods for research and development testing. To establish the validity of the method, it is employed in this study to compare test groups of known relative ballistic performance. Multiple groups of test articles were perforated using consistent projectiles and impact conditions. Test groups were made of rolled homogeneous armor (RHA) plates and differed in thickness. After perforation, each residual projectile was captured behind the target and its mass was measured. The residual masses measured for each test group were analyzed to provide ballistic performance rankings with associated confidence levels. When compared to traditional V50 methods, the residual mass (RM) method was found to require fewer test events and be more tolerant of variations in impact conditions.

  6. Test Loop Demonstration and Evaluation of Slurry Transfer Line Critical Velocity Measurement Instruments

    SciTech Connect (OSTI)

    Bontha, Jagannadha R.; Jenks, Jeromy WJ; Morgen, Gerald P.; Peters, Timothy J.; Wilcox, Wayne A.; Adkins, Harold E.; Burns, Carolyn A.; Greenwood, Margaret S.; MacFarlan, Paul J.; Denslow, Kayte M.; Schonewill, Philip P.; Blanchard, Jeremy; Baer, Ellen BK

    2010-07-31

    This report presents the results of the evaluation of three ultrasonic sensors for detecting critical velocity during slurry transfer between the Hanford tank farms and the WTP.

  7. Fast and thermal data testing of {sup 233}U critical assemblies

    SciTech Connect (OSTI)

    Wright, R.Q.; Jordan, W.C.; Leal, L.C.

    1999-09-01

    Many sources have been used to obtain {sup 233}U benchmark descriptions. Unfortunately, some of these are not reliable since a thorough and complete benchmark evaluation often has not been done. For 24 yr a principal source for {sup 233}U benchmarks has been the Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications. The CSEWG specifications included only two fast benchmarks and three thermal benchmarks. The thermal benchmarks were H{sub 2}O-moderated thorium-oxide exponential lattices. Since the thorium-oxide lattices were exponential experiments, they have not been widely used. CSEWG has also used the {sup 233}U Oak Ridge National Laboratory (ORNL) spheres for many years. One advantage of the CSEWG fast benchmarks, JEZEBEL-23 and FLATTOP-23, is that experiments were done for central-reaction-rate ratios. These reaction-rate ratios provide very valuable information to data testers and evaluators that would not otherwise be available. In recent years the International Handbook of Evaluated Criticality Safety Benchmark Experiments has, in general, been a very useful and reliable source. The Handbook does not include central-reaction-rate ratio experiments, however. A new set of {sup 233}U benchmark experiments has been added to the most recent release of the Handbook, U233-SOL-THERM-004. These are paraffin-reflected cylinders of {sup 233}U uranyl-nitrate solutions. Unfortunately, the estimated benchmark uncertainties are on the order of 0.9 to 1.0% in k{sub eff}. Benchmark testing has been done for some of these U233-SOL-THERM-004 experiments. The authors have also discovered that the benchmark specifications for the Thomas uranyl-nitrate experiments given in Ref. 5 are incorrect. One problem with the Ref. 5 specifications is that the excess acid was not included. As part of this work, the authors developed revised specifications that include an excess acid correlation based on information from the experimental logbook.

  8. Results of scoping tests for open-cycle OTEC (ocean thermal energy conversion) components operating with seawater

    SciTech Connect (OSTI)

    Zangrando, F; Bharathan, D; Green, H J; Link, H F; Parsons, B K; Parsons, J M; Pesaran, A A; Panchal, C B

    1990-09-01

    This report presents comprehensive documentation of the experimental research conducted on open-cycle ocean thermal energy conversion (OC-OTEC) components operating with seawater as a working fluid. The results of this research are presented in the context of previous analysis and fresh-water testing; they provide a basis for understanding and predicting with confidence the performance of all components of an OC-OTEC system except the turbine. Seawater tests have confirmed the results that were obtained in fresh-water tests and predicted by the analytical models of the components. A sound technical basis has been established for the design of larger systems in which net power will be produced for the first time from OC-OTEC technology. Design and operation of a complete OC-OTEC system that produces power will provide sufficient confidence to warrant complete transfer of OC-OTEC technology to the private sector. Each components performance is described in a separate chapter written by the principal investigator responsible for technical aspects of the specific tests. Chapters have been indexed separately for inclusion on the data base.

  9. System Engineering Program Applicability for the High Temperature Gas-Cooled Reactor (HTGR) Component Test Capability (CTC)

    SciTech Connect (OSTI)

    Jeffrey Bryan

    2009-06-01

    This white paper identifies where the technical management and systems engineering processes and activities to be used in establishing the High Temperature Gas-cooled Reactor (HTGR) Component Test Capability (CTC) should be addressed and presents specific considerations for these activities under each CTC alternative

  10. Reliability Testing Beyond Qualification as a Key Component in Photovoltaic's Progress Toward Grid Parity: Preprint

    SciTech Connect (OSTI)

    Wohlgemuth, J. H.; Kurtz, S.

    2011-02-01

    This paper discusses why it is necessary for new lower cost PV modules to be tested using a reliability test sequence that goes beyond the Qualification test sequence now utilized for modules. Today most PV modules are warranted for 25 years, but the Qualification Test Sequence does not test for 25-year life. There is no accepted test protocol to validate a 25-year lifetime. This paper recommends the use of long term accelerated testing to compare now designs directly with older designs that have achieved long lifetimes in outdoor exposure. If the new designs do as well or better than the older ones, then it is likely that they will survive an equivalent length of time in the field.

  11. Facility for high heat flux testing of irradiated fusion materials and components using infrared plasma arc lamps

    SciTech Connect (OSTI)

    Sabau, Adrian S; Ohriner, Evan Keith; Kiggans, Jim; Harper, David C; Snead, Lance Lewis; Schaich, Charles Ross

    2014-01-01

    A new high-heat flux testing facility using water-wall stabilized high-power high-pressure argon Plasma Arc Lamps (PALs) has been developed for fusion applications. It can handle irradiated plasma facing component materials and mock-up divertor components. Two PALs currently available at ORNL can provide maximum incident heat fluxes of 4.2 and 27 MW/m2 over a heated area of 9x12 and 1x10 cm2, respectively, which are fusion-prototypical steady state heat flux conditions. The facility will be described and the main differences between the photon-based high-heat flux testing facilities, such as PALs, and the e-beam and particle beam facilities more commonly used for fusion HHF testing are discussed. The components of the test chamber were designed to accommodate radiation safety and materials compatibility requirements posed by high-temperature exposure of low levels irradiated tungsten articles. Issues related to the operation and temperature measurements during testing are presented and discussed.

  12. Multi-component testing using HZ-PAN and AgZ-PAN Sorbents for OSPREY Model validation

    SciTech Connect (OSTI)

    Garn, Troy G.; Greenhalgh, Mitchell; Lyon, Kevin L.; Law, Jack D.

    2015-04-01

    In efforts to further develop the capability of the Off-gas SeParation and RecoverY (OSPREY) model, multi-component tests were completed using both HZ-PAN and AgZ-PAN sorbents. The primary purpose of this effort was to obtain multi-component xenon and krypton capacities for comparison to future OSPREY predicted multi-component capacities using previously acquired Langmuir equilibrium parameters determined from single component isotherms. Experimental capacities were determined for each sorbent using two feed gas compositions of 1000 ppmv xenon and 150 ppmv krypton in either a helium or air balance. Test temperatures were consistently held at 220 K and the gas flowrate was 50 sccm. Capacities were calculated from breakthrough curves using TableCurve 2D software by Jandel Scientific. The HZ-PAN sorbent was tested in the custom designed cryostat while the AgZ-PAN was tested in a newly installed cooling apparatus. Previous modeling validation efforts indicated the OSPREY model can be used to effectively predict single component xenon and krypton capacities for both engineered form sorbents. Results indicated good agreement with the experimental and predicted capacity values for both krypton and xenon on the sorbents. Overall, the model predicted slightly elevated capacities for both gases which can be partially attributed to the estimation of the parameters and the uncertainty associated with the experimental measurements. Currently, OSPREY is configured such that one species adsorbs and one does not (i.e. krypton in helium). Modification of OSPREY code is currently being performed to incorporate multiple adsorbing species and non-ideal interactions of gas phase species with the sorbent and adsorbed phases. Once these modifications are complete, the sorbent capacities determined in the present work will be used to validate OSPREY multicomponent adsorption predictions.

  13. Slowly moving test charge in two-electron component non-Maxwellian plasma

    SciTech Connect (OSTI)

    Ali, S.; Eliasson, B.

    2015-08-15

    Potential distributions around a slowly moving test charge are calculated by taking into account the electron-acoustic waves in an unmagnetized plasma. Considering a neutralizing background of static positive ions, the supra-thermal hot and cold electrons are described by the Vlasov equations to account for the Kappa (power-law in velocity space) and Maxwell equilibrium distributions. Fourier analysis further leads to the derivation of electrostatic potential showing the impact of supra-thermal hot electrons. The test charge moves slowly in comparison with the hot and cold electron thermal speeds and is therefore shielded by the electrons. This gives rise to a short-range Debye-Hückel potential decaying exponentially with distance and to a far field potential decaying as inverse third power of the distance from the test charge. The results are relevant for both laboratory and space plasmas, where supra-thermal hot electrons with power-law distributions have been observed.

  14. Analytical Study of High Concentration PCB Paint at the Heavy Water Components Test Reactor

    SciTech Connect (OSTI)

    Lowry, N.J.

    1998-10-21

    This report provides results of an analytical study of high concentration PCB paint in a shutdown nuclear test reactor located at the US Department of Energy's Savannah River Site (SRS). The study was designed to obtain data relevant for an evaluation of potential hazards associated with the use of and exposure to such paints.

  15. Development of a propulsion system and component test facility for advanced radioisotope powered Mars Hopper platforms

    SciTech Connect (OSTI)

    Robert C. O'Brien; Nathan D. Jerred; Steven D. Howe

    2011-02-01

    Verification and validation of design and modeling activities for radioisotope powered Mars Hopper platforms undertaken at the Center for Space Nuclear Research is essential for proof of concept. Previous research at the center has driven the selection of advanced material combinations; some of which require specialized handling capabilities. The development of a closed and contained test facility to forward this research is discussed within this paper.

  16. DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility

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

    DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT, supports a critical component of LANL's primary mission: to...

  17. Protective structures on the surface of zirconium components of light water reactor cores: Formation, testing, and prototype equipment

    SciTech Connect (OSTI)

    Begrambekov, L. B.; Gordeev, A. A.; Evsin, A. E. Ivanova, S. V.; Kaplevsky, A. S.; Sadovskiy, Ya. A.

    2015-12-15

    The results of tests of plasma treatment of zirconium and deposition of protective yttrium coatings used as the methods of protection of zirconium components of light water reactor cores against hydrogenation are detailed. The amount of hydrogen in the treated sample exposed to superheated steam for 2500 h at temperature T = 400°C and pressure p = 1 atm was five times lower than the corresponding value for the untreated one. The amount of hydrogen in the sample coated with yttrium remained almost unchanged in 4000 h of exposure. A plasma method for rapid testing for hydrogen resistance is proposed. The hydrogenation rate provided by this method is 700 times higher than that in tests with superheated steam. The results of preliminary experiments confirm the possibility of constructing a unit for batch processing of the surfaces of fuel rod claddings.

  18. Flow Components in a NaK Test Loop Designed to Simulate Conditions in a Nuclear Surface Power Reactor

    SciTech Connect (OSTI)

    Polzin, Kurt A.; Godfroy, Thomas J.

    2008-01-21

    A test loop using NaK as the working fluid is presently in use to study material compatibility effects on various components that comprise a possible nuclear reactor design for use on the lunar surface. A DC electromagnetic (EM) pump has been designed and implemented as a means of actively controlling the NaK flow rate through the system and an EM flow sensor is employed to monitor the developed flow rate. These components allow for the matching of the flow rate conditions in test loops with those that would be found in a full-scale surface-power reactor. The design and operating characteristics of the EM pump and flow sensor are presented. In the EM pump, current is applied to a set of electrodes to produce a Lorentz body force in the fluid. A measurement of the induced voltage (back-EMF) in the flow sensor provides the means of monitoring flow rate. Both components are compact, employing high magnetic field strength neodymium magnets thermally coupled to a water-cooled housing. A vacuum gap limits the heat transferred from the high temperature NaK tube to the magnets and a magnetically-permeable material completes the magnetic circuit. The pump is designed to produce a pressure rise of 34.5 kPa, and the flow sensor's predicted output is roughly 20 mV at the loop's nominal flow rate of 0.114 m{sup 3}/hr.

  19. Integrated exposure and dose modeling and analysis system. 1. Formulation and testing of microenvironmental and pharmacokinetic components

    SciTech Connect (OSTI)

    Georgopoulos, P.G.; Walia, A.; Roy, A.; Lioy, P.J.

    1997-01-01

    The conceptual and theoretical framework for a modular integrated Exposure and Dose Modeling and Analysis System (EDMAS) has been formulated, and its stepwise implementation and testing is currently in progress. This system aims to provide state-of-the art tools for performing integrated assessments of exposure and dose for individuals and populations. The integration of modeling components with each other as well as with available environmental, exposure, and toxicological databases in being accomplished with the use of computational tools that include interactive simulation environments, Geographical information Systems, and various data retrieval, management, statistical analysis, and visualization methods. This paper overviews the structure and modular nature of this integrated modeling system and focuses specifically on two of its components: (a) a hierarchy of physiologically based pharmacokinetic models (PBPKM), representing various levels of detail and sophistication, and (b) a family of microenvironmental models, that incorporate complex physical and chemical transformations. The deterministic implementation of these components is also presented here in two test applications: (i) a case study of benzene exposure indoors resulting from the volatilization of contaminated tap water and (ii) a case study of photochemical pollution infiltration indoors, in an office building environment. 77 refs., 6 figs., 2 tabs.

  20. Effect of hydrothermal condition on the formation of multi-component oxides of Ni-based metallic glass under high temperature water near the critical point

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

    Kim, J. S.; Kim, S. Y.; Kim, D. H.; Ott, R. T.; Kim, H. G.; Lee, M. H.

    2015-07-01

    The specific feature of multi-component oxides synthesized by hydrothermal process under high temperature (633 K) and highly pressurized water (18.9 MPa) near critical point. Effects of hydrothermal processing duration times 24 hours and 72 hours, respectively, on the oxide formation of the Ni59Zr20Ti16Si2Sn3 metallic glass synthesized by powder metallurgy process were characterized by X-ray diffractometer, differential scanning calorimeter along with the particle size, morphology and crystalline phase of the oxides. The crystallization of the needle-shape NiTiO3, ZrTiO4 and ZrSnO4 ternary oxide phases observed on the surface of metallic glass at below glass transition temperature and the morphology of oxide phasesmore » changed to plate-shape around 2 μm in diameter by the increase processing time. This hydrothermal processing in subcritical water provides accelerated dense metal oxide crystals due to the reaction medium being at higher pressure than conventional oxidation processing.« less

  1. Effect of hydrothermal condition on the formation of multi-component oxides of Ni-based metallic glass under high temperature water near the critical point

    SciTech Connect (OSTI)

    Kim, J. S.; Kim, S. Y.; Kim, D. H.; Ott, R. T.; Kim, H. G.; Lee, M. H.

    2015-07-01

    The specific feature of multi-component oxides synthesized by hydrothermal process under high temperature (633 K) and highly pressurized water (18.9 MPa) near critical point. Effects of hydrothermal processing duration times 24 hours and 72 hours, respectively, on the oxide formation of the Ni59Zr20Ti16Si2Sn3 metallic glass synthesized by powder metallurgy process were characterized by X-ray diffractometer, differential scanning calorimeter along with the particle size, morphology and crystalline phase of the oxides. The crystallization of the needle-shape NiTiO3, ZrTiO4 and ZrSnO4 ternary oxide phases observed on the surface of metallic glass at below glass transition temperature and the morphology of oxide phases changed to plate-shape around 2 μm in diameter by the increase processing time. This hydrothermal processing in subcritical water provides accelerated dense metal oxide crystals due to the reaction medium being at higher pressure than conventional oxidation processing.

  2. Effect of hydrothermal condition on the formation of multi-component oxides of Ni-based metallic glass under high temperature water near the critical point

    SciTech Connect (OSTI)

    Kim, J. S.; Lee, M. H.; Kim, S. Y.; Kim, D. H.; Ott, R. T.; Kim, H. G.

    2015-07-15

    The specific feature of multi-component oxides synthesized by hydrothermal process under high temperature (633 K) and highly pressurized water (18.9 MPa) near critical point. Effects of hydrothermal processing duration times 24 hours and 72 hours, respectively, on the oxide formation of the Ni{sub 59}Zr{sub 20}Ti{sub 16}Si{sub 2}Sn{sub 3} metallic glass synthesized by powder metallurgy process were characterized by X-ray diffractometer, differential scanning calorimeter along with the particle size, morphology and crystalline phase of the oxides. The crystallization of the needle-shape NiTiO{sub 3}, ZrTiO{sub 4} and ZrSnO{sub 4} ternary oxide phases observed on the surface of metallic glass at below glass transition temperature and the morphology of oxide phases changed to plate-shape around 2 μm in diameter by the increase processing time. This hydrothermal processing in subcritical water provides accelerated dense metal oxide crystals due to the reaction medium being at higher pressure than conventional oxidation processing.

  3. Benchmark Testing of a New 56Fe Evaluation for Criticality Safety Applications

    SciTech Connect (OSTI)

    Leal, Luiz C; Ivanov, E.

    2015-01-01

    The SAMMY code was used to evaluate resonance parameters of the 56Fe cross section in the resolved resonance energy range of 0–2 MeV using transmission data, capture, elastic, inelastic, and double differential elastic cross sections. The resonance analysis was performed with the code SAMMY that fits R-matrix resonance parameters using the generalized least-squares technique (Bayes’ theory). The evaluation yielded a set of resonance parameters that reproduced the experimental data very well, along with a resonance parameter covariance matrix for data uncertainty calculations. Benchmark tests were conducted to assess the evaluation performance in benchmark calculations.

  4. THE SLUGGS SURVEY: NGC 3115, A CRITICAL TEST CASE FOR METALLICITY BIMODALITY IN GLOBULAR CLUSTER SYSTEMS

    SciTech Connect (OSTI)

    Brodie, Jean P.; Conroy, Charlie; Arnold, Jacob A.; Romanowsky, Aaron J.; Usher, Christopher; Forbes, Duncan A.; Strader, Jay

    2012-11-10

    Due to its proximity (9 Mpc) and the strongly bimodal color distribution of its spectroscopically well-sampled globular cluster (GC) system, the early-type galaxy NGC 3115 provides one of the best available tests of whether the color bimodality widely observed in GC systems generally reflects a true metallicity bimodality. Color bimodality has alternatively been attributed to a strongly nonlinear color-metallicity relation reflecting the influence of hot horizontal-branch stars. Here, we couple Subaru Suprime-Cam gi photometry with Keck/DEIMOS spectroscopy to accurately measure GC colors and a CaT index that measures the Ca II triplet. We find the NGC 3115 GC system to be unambiguously bimodal in both color and the CaT index. Using simple stellar population models, we show that the CaT index is essentially unaffected by variations in horizontal-branch morphology over the range of metallicities relevant to GC systems (and is thus a robust indicator of metallicity) and confirm bimodality in the metallicity distribution. We assess the existing evidence for and against multiple metallicity subpopulations in early- and late-type galaxies and conclude that metallicity bi/multimodality is common. We briefly discuss how this fundamental characteristic links directly to the star formation and assembly histories of galaxies.

  5. Stability of CIGS Solar Cells and Component Materials Evaluated by a Step-Stress Accelerated Degradation Test Method: Preprint

    SciTech Connect (OSTI)

    Pern, F. J.; Noufi, R.

    2012-10-01

    A step-stress accelerated degradation testing (SSADT) method was employed for the first time to evaluate the stability of CuInGaSe2 (CIGS) solar cells and device component materials in four Al-framed test structures encapsulated with an edge sealant and three kinds of backsheet or moisture barrier film for moisture ingress control. The SSADT exposure used a 15oC and then a 15% relative humidity (RH) increment step, beginning from 40oC/40%RH (T/RH = 40/40) to 85oC/70%RH (85/70) as of the moment. The voluminous data acquired and processed as of total DH = 3956 h with 85/70 = 704 h produced the following results. The best CIGS solar cells in sample Set-1 with a moisture-permeable TPT backsheet showed essentially identical I-V degradation trend regardless of the Al-doped ZnO (AZO) layer thickness ranging from standard 0.12 μm to 0.50 μm on the cells. No clear 'stepwise' feature in the I-V parameter degradation curves corresponding to the SSADT T/RH/time profile was observed. Irregularity in I-V performance degradation pattern was observed with some cells showing early degradation at low T/RH < 55/55 and some showing large Voc, FF, and efficiency degradation due to increased series Rs (ohm-cm2) at T/RH ≥ 70/70. Results of (electrochemical) impedance spectroscopy (ECIS) analysis indicate degradation of the CIGS solar cells corresponded to increased series resistance Rs (ohm) and degraded parallel (minority carrier diffusion/recombination) resistance Rp, capacitance C, overall time constant Rp*C, and 'capacitor quality' factor (CPE-P), which were related to the cells? p-n junction properties. Heating at 85/70 appeared to benefit the CIGS solar cells as indicated by the largely recovered CPE-P factor. Device component materials, Mo on soda lime glass (Mo/SLG), bilayer ZnO (BZO), AlNi grid contact, and CdS/CIGS/Mo/SLG in test structures with TPT showed notable to significant degradation at T/RH ≥ 70/70. At T/RH = 85/70, substantial blistering of BZO layers on CIGS

  6. FEM calculation of eddy current losses and forces in thin conducting sheets of test facilities for fusion reactor components

    SciTech Connect (OSTI)

    Biro, O.; Preis, K.; Richter, K.R. ); Heller, R.; Komarek, P.; Maurer, W. )

    1992-03-01

    The eddy current carrying conducting parts in fusion reactor models are frequently relatively thin sheets. To avoid the associated numerical problems, the surface current density is represented in this paper by a scalar quantity and, as a novelty, the magnetic field is described overall by a magnetic vector potential to treat multiply connected conductors easily. The method is applied to several problems involving fusion reactor components.

  7. HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2

    SciTech Connect (OSTI)

    KIRK WINTERHOLLER

    2008-02-25

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-630 Catch Tank System closure plan due to ongoing laboratory operations in the areas requiring closure actions. The TRA-604 laboratory components include the TRA-604 laboratory warm wastewater drain piping, undersink drains, subheaders, and the east TRA-604 laboratory drain header. Potentially contaminated surfaces located beneath the TRA-604 laboratory warm wastewater drain piping and beneath the island sinks located in Laboratories 126 and 128 (located in TRA-661) are also addressed in this closure plan. The TRA-604 laboratory components will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, Subparts G and J. This closure plan presents the closure performance standards and the methods for achieving those standards.

  8. System Performance Testing of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations - 13584

    SciTech Connect (OSTI)

    Denslow, Kayte M.; Bontha, Jagannadha R.; Adkins, Harold E.; Jenks, Jeromy W.J.; Hopkins, Derek F.; Thien, Michael G.; Kelly, Steven E.; Wooley, Theodore A.

    2013-07-01

    The delivery of Hanford double-shell tank waste to the Hanford Tank Waste Treatment and Immobilization Plant (WTP) is governed by specific Waste Acceptance Criteria that are identified in ICD 19 - Interface Control Document for Waste Feed. Waste must be certified as acceptable before it can be delivered to the WTP. The fluid transfer velocity at which solid particulate deposition occurs in waste slurry transport piping (critical velocity) is a key waste acceptance parameter that must be accurately characterized to determine if the waste is acceptable for transfer to the WTP. Washington River Protection Solutions and the Pacific Northwest National Laboratory have been evaluating the ultrasonic PulseEcho instrument since 2010 for its ability to detect particle settling and determine critical velocity in a horizontal slurry transport pipeline for slurries containing particles with a mean particle diameter of =14 micrometers (?m). In 2012 the PulseEcho instrument was further evaluated under WRPS' System Performance test campaign to identify critical velocities for slurries that are expected to be encountered during Hanford tank waste retrieval operations or bounding for tank waste feed. This three-year evaluation has demonstrated the ability of the ultrasonic PulseEcho instrument to detect the onset of critical velocity for a broad range of physical and rheological slurry properties that are likely encountered during the waste feed transfer operations between the Hanford tank farms and the WTP. (authors)

  9. System Performance Testing of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations - 13584

    SciTech Connect (OSTI)

    Denslow, Kayte M.; Bontha, Jagannadha R.; Adkins, Harold E.; Jenks, Jeromy WJ; Hopkins, Derek F.; Thien, Michael G.; Kelly, Steven E.; Wooley, Theodore A.

    2013-06-01

    The delivery of Hanford double-shell tank waste to the Hanford Tank Waste Treatment and Immobilization Plant (WTP) is governed by specific Waste Acceptance Criteria that are identified in ICD 19 - Interface Control Document for Waste Feed. Waste must be certified as acceptable before it can be delivered to the WTP. The fluid transfer velocity at which solid particulate deposition occurs in waste slurry transport piping (critical velocity) is a key waste acceptance parameter that must be accurately characterized to determine if the waste is acceptable for transfer to the WTP. Washington River Protection Solutions and the Pacific Northwest National Laboratory have been evaluating the ultrasonic PulseEcho instrument since 2010 for its ability to detect particle settling and determine critical velocity in a horizontal slurry transport pipeline for slurries containing particles with a mean particle diameter of ?14 micrometers (?m). In 2012 the PulseEcho instrument was further evaluated under WRPS System Performance test campaign to identify critical velocities for slurries that are expected to be encountered during Hanford tank waste retrieval operations or bounding for tank waste feed. This three-year evaluation has demonstrated the ability of the ultrasonic PulseEcho instrument to detect the onset of critical velocity for a broad range of physical and rheological slurry properties that are likely encountered during the waste feed transfer operations between the Hanford tank farms and the WTP.

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

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

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

  11. The Mission and Technology of a Gas Dynamic Trap Neutron Source for Fusion Material and Component Testing and Qualification

    SciTech Connect (OSTI)

    Ivanov, A; Kulcinski, J; Molvik, A; Ryutov, D; Santarius, J; Simonen, T; Wirth, B D; Ying, A

    2009-11-23

    The successful operation (with {beta} {le} 60%, classical ions and electrons with Te = 250 eV) of the Gas Dynamic Trap (GDT) device at the Budker Institute of Nuclear Physics (BINP) in Novosibirsk, Russia, extrapolates to a 2 MW/m{sup 2} Dynamic Trap Neutron Source (DTNS), which burns only {approx}100 g of tritium per full power year. The DTNS has no serious physics, engineering, or technology obstacles; the extension of neutral beam lines to steady state can use demonstrated engineering; and it supports near-term tokamaks and volume neutron sources. The DTNS provides a neutron spectrum similar to that of ITER and satisfies the missions specified by the materials community to test fusion materials (listed as one of the top grand challenges for engineering in the 21st century by the U.S. National Academy of Engineering) and subcomponents (including tritium-breeding blankets) needed to construct DEMO. The DTNS could serve as the first Fusion Nuclear Science Facility (FNSF), called for by ReNeW, and could provide the data necessary for licensing subsequent FSNFs.

  12. Rocky Flats CAAS System Recalibrated, Retested, and Analyzed to Install in the Criticality Experiments Facility at the Nevada Test Site

    SciTech Connect (OSTI)

    Kim, S; Heinrichs, D; Biswas, D; Huang, S; Dulik, G; Scorby, J; Boussoufi, M; Liu, B; Wilson, R

    2009-05-27

    Neutron detectors and control panels transferred from the Rocky Flats Plant (RFP) were recalibrated and retested for redeployment to the CEF. Testing and calibration were successful with no failure to any equipment. Detector sensitivity was tested at a TRIGA reactor, and the response to thermal neutron flux was satisfactory. MCNP calculated minimum fission yield ({approx} 2 x 10{sup 15} fissions) was applied to determine the thermal flux at selected detector positions at the CEF. Thermal flux levels were greater than 6.39 x 10{sup 6} (n/cm{sup 2}-sec), which was about four orders of magnitude greater than the minimum alarm flux. Calculations of detector survivable distances indicate that, to be out of lethal area, a detector needs to be placed greater than 15 ft away from a maximum credible source. MCNP calculated flux/dose results were independently verified by COG. CAAS calibration and the testing confirmed that the RFP CAAS system is performing its functions as expected. New criteria for the CAAS detector placement and 12-rad zone boundaries at the CEF are established. All of the CAAS related documents and hardware have been transferred from LLNL to NSTec for installation at the CEF high bay areas.

  13. Technical Letter Report, An Evaluation of Ultrasonic Phased Array Testing for Reactor Piping System Components Containing Dissimilar Metal Welds, JCN N6398, Task 2A

    SciTech Connect (OSTI)

    Diaz, Aaron A.; Cinson, Anthony D.; Crawford, Susan L.; Anderson, Michael T.

    2009-11-30

    Research is being conducted for the U.S. Nuclear Regulatory Commission at the Pacific Northwest National Laboratory to assess the effectiveness and reliability of advanced nondestructive examination (NDE) methods for the inspection of light-water reactor components. The scope of this research encom¬passes primary system pressure boundary materials including dissimilar metal welds (DMWs), cast austenitic stainless steels (CASS), piping with corrosion-resistant cladding, weld overlays, inlays and onlays, and far-side examinations of austenitic piping welds. A primary objective of this work is to evaluate various NDE methods to assess their ability to detect, localize, and size cracks in steel components that challenge standard and/or conventional inspection methodologies. This interim technical letter report provides a summary of a technical evaluation aimed at assessing the capabilities of phased-array (PA) ultrasonic testing (UT) methods as applied to the inspection of small-bore DMW components that exist in the reactor coolant systems (RCS) of pressurized water reactors (PWRs). Operating experience and events such as the circumferential cracking in the reactor vessel nozzle-to-RCS hot leg pipe at V.C. Summer nuclear power station, identified in 2000, show that in PWRs where primary coolant water (or steam) are present under normal operation, Alloy 82/182 materials are susceptible to pressurized water stress corrosion cracking. The extent and number of occurrences of DMW cracking in nuclear power plants (domestically and internationally) indicate the necessity for reliable and effective inspection techniques. The work described herein was performed to provide insights for evaluating the utility of advanced NDE approaches for the inspection of DMW components such as a pressurizer surge nozzle DMW, a shutdown cooling pipe DMW, and a ferritic (low-alloy carbon steel)-to-CASS pipe DMW configuration.

  14. Ability of the Confined Explosive Component Water Gap Test STANAG 4363 to Assess the Shock Sensitivity of MM-Scale Detonators

    SciTech Connect (OSTI)

    Lefrancois, A S; Roeske, F; Benterou, J; Tarver, C M; Lee, R S; Hannah, B

    2006-02-10

    The Explosive Component Water Gap Test (ECWGT) has been validated to assess the shock sensitivity of lead and booster components having a diameter larger than 5 mm. Several countries have investigated by experiments and numerical simulations the effect of confinement on the go/no go threshold for Pentaerythritol Tetranitrate (PETN) pellets having a height and diameter of 3 mm, confined by a steel annulus of wall thickness 1-3.5 mm. Confinement of the PETN by a steel annulus of the same height of the pellet with 1-mm wall thickness makes the component more sensitive (larger gap). As the wall thickness is increased to 2-mm, the gap increases a lesser amount, but when the wall thickness is increased to 3.5-mm a decrease in sensitivity is observed (smaller gap). This decrease of the water gap has been reproduced experimentally. Recent numerical simulations using Ignition and Growth model [1] for the PETN Pellet have reproduced the experimental results for the steel confinement up to 2 mm thick [2]. The presence of a stronger re-shock following the first input shock from the water and focusing on the axis have been identified in the pellet due to the steel confinement. The double shock configuration is well-known to lead in some cases to shock desensitization. This work presents the numerical simulations using Ignition and Growth model for LX16 (PETN based HE) and LX19 (CL20 based HE) Pellets [3] in order to assess the shock sensitivity of mm-scale detonators. The pellets are 0.6 mm in diameter and 3 mm length with different type of steel confinement 2.2 mm thick and 4.7 mm thick. The influence of an aluminum confinement is calculated for the standard LX 16 pellet 3 mm in diameter and 3 mm in height. The question of reducing the size of the donor charge is also investigated to small scale the test itself.

  15. Technique for Measuring Hybrid Electronic Component Reliability

    SciTech Connect (OSTI)

    Green, C.C.; Hernandez, C.L.; Hosking, F.M.; Robinson, D.; Rutherford, B.; Uribe, F.

    1999-01-01

    Materials compatibility studies of aged, engineered materials and hardware are critical to understanding and predicting component reliability, particularly for systems with extended stockpile life requirements. Nondestructive testing capabilities for component reliability would significantly enhance lifetime predictions. For example, if the detection of crack propagation through a solder joint can be demonstrated, this technique could be used to develop baseline information to statistically determine solder joint lifelengths. This report will investigate high frequency signal response techniques for nondestructively evaluating the electrical behavior of thick film hybrid transmission lines.

  16. Design and Construction of a 500 KW CW, 400 MHZ Klystron To Be Used As RF Power Source For LHC/RF Component Tests

    SciTech Connect (OSTI)

    Pearson, Chris

    2003-05-05

    A 500 kW cw klystron operating at 400 MHz was developed and constructed jointly by CERN and SLAC for use as a high-power source at CERN for testing LHC/RF components such as circulators, RF absorbers and superconducting cavities with their input couplers. The design is a modification of the 353 MHz SLAC PEP-I klystron. More than 80% of the original PEP-I tube parts could thus be incorporated in the LHC test klystron which resulted in lower engineering costs as well as reduced development and construction time. The physical length between cathode plane and upper pole plate was kept unchanged so that a PEP-I tube focusing solenoid, available at CERN, could be re-used. With the aid of the klystron simulation codes JPNDISK and CONDOR, the design of the LHC tube was accomplished, which resulted in a tube with noticeably higher efficiency than its predecessor, the PEP-I klystron. The integrated cavities were redesigned using SUPERFISH and the output coupling circuit, which also required redesigning, was done with the aid of MAFIA. Details of the tube development and test results are presented.

  17. Crack growth rates and metallographic examinations of Alloy 600 and Alloy 82/182 from field components and laboratory materials tested in PWR environments.

    SciTech Connect (OSTI)

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

    2008-05-05

    In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the order of 220-230 kJ/mol, higher than the 130 kJ/mol commonly used for Alloy 600. The consequences of using a larger value of activation energy for SCC CGR data analysis are discussed.

  18. Argonne Liquid-Metal Advanced Burner Reactor : components and in-vessel system thermal-hydraulic research and testing experience - pathway forward.

    SciTech Connect (OSTI)

    Kasza, K.; Grandy, C.; Chang, Y.; Khalil, H.; Nuclear Engineering Division

    2007-06-30

    This white paper provides an overview and status report of the thermal-hydraulic nuclear research and development, both experimental and computational, conducted predominantly at Argonne National Laboratory. Argonne from the early 1970s through the early 1990s was the Department of Energy's (DOE's) lead lab for thermal-hydraulic development of Liquid Metal Reactors (LMRs). During the 1970s and into the mid-1980s, Argonne conducted thermal-hydraulic studies and experiments on individual reactor components supporting the Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and the Clinch River Breeder Reactor (CRBR). From the mid-1980s and into the early 1990s, Argonne conducted studies on phenomena related to forced- and natural-convection thermal buoyancy in complete in-vessel models of the General Electric (GE) Prototype Reactor Inherently Safe Module (PRISM) and Rockwell International (RI) Sodium Advanced Fast Reactor (SAFR). These two reactor initiatives involved Argonne working closely with U.S. industry and DOE. This paper describes the very important impact of thermal hydraulics dominated by thermal buoyancy forces on reactor global operation and on the behavior/performance of individual components during postulated off-normal accident events with low flow. Utilizing Argonne's LMR expertise and design knowledge is vital to the further development of safe, reliable, and high-performance LMRs. Argonne believes there remains an important need for continued research and development on thermal-hydraulic design in support of DOE's and the international community's renewed thrust for developing and demonstrating the Global Nuclear Energy Partnership (GNEP) reactor(s) and the associated Argonne Liquid Metal-Advanced Burner Reactor (LM-ABR). This white paper highlights that further understanding is needed regarding reactor design under coolant low-flow events. These safety-related events are associated with the transition from normal high

  19. Use of system code to estimate equilibrium tritium inventory in fusion DT machines, such as ARIES-AT and components testing facilities

    SciTech Connect (OSTI)

    C.P.C. Wong; B. Merrill

    2014-10-01

    ITER is under construction and will begin operation in 2020. This is the first 500 MWfusion class DT device, and since it is not going to breed tritium, it will consume most of the limited supply of tritium resources in the world. Yet, in parallel, DT fusion nuclear component testing machines will be needed to provide technical data for the design of DEMO. It becomes necessary to estimate the tritium burn-up fraction and corresponding initial tritium inventory and the doubling time of these machines for the planning of future supply and utilization of tritium. With the use of a system code, tritium burn-up fraction and initial tritium inventory for steady state DT machines can be estimated. Estimated tritium burn-up fractions of FNSF-AT, CFETR-R and ARIES-AT are in the range of 1–2.8%. Corresponding total equilibrium tritium inventories of the plasma flow and tritium processing system, and with the DCLL blanket option are 7.6 kg, 6.1 kg, and 5.2 kg for ARIES-AT, CFETR-R and FNSF-AT, respectively.

  20. Simulation of the passive condensation cooling tank of the PASCAL test facility using the component thermal-hydraulic analysis code CUPID

    SciTech Connect (OSTI)

    Cho, H. K.; Lee, S. J.; Kang, K. H.; Yoon, H. Y.

    2012-07-01

    For the analysis of transient two-phase flows in nuclear reactor components, a three-dimensional thermal hydraulics code, named CUPID, has been being developed. In the present study, the CUPID code was applied for the simulation of the PASCAL (PAFS Condensing Heat Removal Assessment Loop) test facility constructed with an aim of validating the cooling and operational performance of the PAFS (Passive Auxiliary Feedwater System). The PAFS is one of the advanced safety features adopted in the APR+ (Advanced Power Reactor +), which is intended to completely replace the conventional active auxiliary feedwater system. This paper presents the preliminary simulation results of the PASCAL facility performed with the CUPID code in order to verify its applicability to the thermal-hydraulic phenomena inside the system. A standalone calculation for the passive condensation cooling tank was performed by imposing a heat source boundary condition and the transient thermal-hydraulic behaviors inside the system, such as the water level, temperature and velocity, were qualitatively investigated. The simulation results verified that the natural circulation and boiling phenomena in the water pool can be well reproduced by the CUPID code. (authors)

  1. Conceptual Engineering Method for Attenuating He Ion Interactions on First Wall Components in the Fusion Test Facility (FTF) Employing a Low-Pressure Noble Gas

    SciTech Connect (OSTI)

    C.A.Gentile, W.R.Blanchard, T.Kozub, C.Priniski, I.Zatz, S.Obenschain

    2009-09-21

    It has been shown that post detonation energetic helium ions can drastically reduce the useful life of the (dry) first wall of an IFE reactor due to the accumulation of implanted helium. For the purpose of attenuating energetic helium ions from interacting with first wall components in the Fusion Test Facility (FTF) target chamber, several concepts have been advanced. These include magnetic intervention (MI), deployment of a dynamically moving first wall, use of a sacrificial shroud, designing the target chamber large enough to mitigate the damage caused by He ions on the target chamber wall, and the use of a low pressure noble gas resident in the target chamber during pulse power operations. It is proposed that employing a low-pressure (~ 1 torr equivalent) noble gas in the target chamber will thermalize energetic helium ions prior to interaction with the wall. The principle benefit of this concept is the simplicity of the design and the utilization of (modified) existing technologies for pumping and processing the noble ambient gas. Although the gas load in the system would be increased over other proposed methods, the use of a "gas shield" may provide a cost effective method of greatly extending the first wall of the target chamber. An engineering study has been initiated to investigate conceptual engineering metmethods for implementing a viable gas shield strategy in the FTF.

  2. Evaluation of critical pathways, radionuclides, and remedial measures for reducing the radiological dose to returning populations at a former nuclear test site

    SciTech Connect (OSTI)

    Robison, W. L., LLNL

    1997-11-01

    Bikini Island, the major residence island at Bikini Atoll, was contaminated with radioactive fallout as a result of the BRAVO test conducted on March 1, 1954. We have identified the critical radionuclides and supplied radiological data needed to develop dose estimates for all possible exposure pathways. These estimates show that the major dose to returning populations would result from ingestion of cesium-137 (137 Cs) in locally grown terrestrial foods where the predicted population average effective dose exceeds current federal guidelines. Consequently, we designed several long-term field experiments to develop and evaluate methods to reduce the 137 Cs content in locally grown foods.This paper gives a general outline of the remediation experiments with a more detailed description of a preferred combined option. Our comparative evaluation on various remedial methods show that the combined option--potassium treatment of the entire islands with limited excavation of soil in village an d housing areas--will be effective in reducing the dose to about 10% of pretreatment levels, and offers very significant benefits with respect to adverse environmental impacts as well as savings in overall costs, time, and required expert resources.

  3. Critical Issues in NPH Categorization and Limit State Selection...

    Office of Environmental Management (EM)

    Critical Issues in NPH Categorization and Limit State Selection of Structures, Systems, and Components Quazi Hossain Lawrence Livermore National Laboratory Critical Issues in NPH ...

  4. U-019: Oracle Critical Patch Update Advisory- October 2011

    Broader source: Energy.gov [DOE]

    October 2011 Critical Patch Update, security vulnerability fixes for proprietary components of Oracle Linux will be announced in Oracle Critical Patch Updates.

  5. V-004: Oracle Critical Patch Update Advisory- October 2012

    Broader source: Energy.gov [DOE]

    October 2012 Critical Patch Update, security vulnerability fixes for proprietary components of Oracle Linux will be announced in Oracle Critical Patch Updates.

  6. An Assessment of Visual Testing

    SciTech Connect (OSTI)

    Cumblidge, Stephen E.; Anderson, Michael T.; Doctor, Steven R.

    2004-11-01

    In response to increasing interest from nuclear utilities in replacing some volumetric examinations of nuclear reactor components with remote visual testing, the Pacific Northwest National Laboratory has examined the capabilities of remote visual testing for the Nuclear Regulatory Commission. This report describes visual testing and explores the visual acuities of the camera systems used to examine nuclear reactor components. The types and sizes of cracks typically found in nuclear reactor components are reviewed. The current standards in visual testing are examined critically, and several suggestions for improving these standards are proposed. Also proposed for future work is a round robin test to determine the effectiveness of visual tests and experimental studies to determine the values for magnification and resolution needed to reliably image very tight cracks.

  7. Infrastructure, Components and System Level Testing and Analysis of Electric Vehicles: Cooperative Research and Development Final Report, CRADA Number CRD-09-353

    SciTech Connect (OSTI)

    Neubauer, J.

    2013-05-01

    Battery technology is critical for the development of innovative electric vehicle networks, which can enhance transportation sustainability and reduce dependence on petroleum. This cooperative research proposed by Better Place and NREL will focus on predicting the life-cycle economics of batteries, characterizing battery technologies under various operating and usage conditions, and designing optimal usage profiles for battery recharging and use.

  8. Critical Materials:

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

    Critical Materials: 1 Technology Assessment 2 Contents 3 1. Introduction to the Technology/System ............................................................................................... 2 4 2. Technology Assessment and Potential ................................................................................................. 5 5 2.1 Major Trends in Selected Clean Energy Application Areas ........................................................... 5 6 2.1.1 Permanent Magnets for Wind

  9. Vulnerability of critical infrastructures : identifying critical nodes.

    SciTech Connect (OSTI)

    Cox, Roger Gary; Robinson, David Gerald

    2004-06-01

    The objective of this research was the development of tools and techniques for the identification of critical nodes within critical infrastructures. These are nodes that, if disrupted through natural events or terrorist action, would cause the most widespread, immediate damage. This research focuses on one particular element of the national infrastructure: the bulk power system. Through the identification of critical elements and the quantification of the consequences of their failure, site-specific vulnerability analyses can be focused at those locations where additional security measures could be effectively implemented. In particular, with appropriate sizing and placement within the grid, distributed generation in the form of regional power parks may reduce or even prevent the impact of widespread network power outages. Even without additional security measures, increased awareness of sensitive power grid locations can provide a basis for more effective national, state and local emergency planning. A number of methods for identifying critical nodes were investigated: small-world (or network theory), polyhedral dynamics, and an artificial intelligence-based search method - particle swarm optimization. PSO was found to be the only viable approach and was applied to a variety of industry accepted test networks to validate the ability of the approach to identify sets of critical nodes. The approach was coded in a software package called Buzzard and integrated with a traditional power flow code. A number of industry accepted test networks were employed to validate the approach. The techniques (and software) are not unique to power grid network, but could be applied to a variety of complex, interacting infrastructures.

  10. Materials & Components Compatibility

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

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

  11. Development of wear-resistant ceramic coatings for diesel engine components. Volume 1, Coating development and tribological testing: Final report: DOE/ORNL Ceramic Technology Project

    SciTech Connect (OSTI)

    Naylor, M.G.S.

    1992-06-01

    The tribological properties of a variety of advanced coating materials have been evaluated under conditions which simulate the piston ring -- cylinder liner environment near top ring reversal in a heavy duty diesel engine. Coated ``ring`` samples were tested against a conventional pearlitic grey cast iron liner material using a high temperature reciprocating wear test rig. Tests were run with a fresh CE/SF 15W40lubricant at 200 and 350{degrees}C, with a high-soot, engine-tested oil at 200{degrees}C and with no lubrication at 200{degrees}C. For lowest wear under boundary lubricated conditions, the most promising candidates to emerge from this study were high velocity oxy-fuel (HVOF) Cr{sub 3} C{sub 2} - 20% NiCr and WC - 12% Co cermets, low temperature arc vapor deposited (LTAVD) CrN and plasma sprayed chromium oxides. Also,plasma sprayed Cr{sub 2}O{sub 3} and A1{sub 2}O{sub 3}-ZrO{sub 2} materials were found to give excellent wear resistance in unlubricated tests and at extremely high temperatures (450{degrees}C) with a syntheticoil. All of these materials would offer substantial wear reductions compared to the conventional electroplated hard chromium ring facing and thermally sprayed metallic coatings, especially at high temperatures and with high-soot oils subjected to degradation in diesel environments. The LTAVD CrN coating provided the lowest lubricated wear rates of all the materials evaluated, but may be too thin (4 {mu}m) for use as a top ring facing. Most of the coatings evaluated showed higher wear rates with high-soot, engine-tested oil than with fresh oil, with increases of more than a factor of ten in some cases. Generally, metallic materials were found to be much more sensitive to soot/oil degradation than ceramic and cermet coatings. Thus, decreased ``soot sensitivity`` is a significant driving force for utilizing ceramic or cermet coatings in diesel engine wear applications.

  12. Critical Materials Workshop

    Office of Energy Efficiency and Renewable Energy (EERE)

    Presentations during the Critical Materials Workshop held on April 3, 2012 overviewing critical materials strategies

  13. Development and setting of a new system for advanced rheocast components

    SciTech Connect (OSTI)

    Rosso, Mario; Peter, I.; Calosso, F.

    2011-05-04

    This paper presents an overview of alternative methods of production of enhanced performance Al-based alloys components for critical areas. In particular, a new rheocasting system, suitable for the manufacturing of high performance industrial components has been considered. The aforementioned method allows obtaining component quickly and results a more convenient process, from economical point of view than other innovative processes. Two series of components have been produced with A356 and A357 alloys, then have been heat treated using T5 and T6 treatments. On polished transverse sections of samples the microstructure of the alloy has been observed. Their soundness has been previously certified by non destructive tests. Samples for tensile and three point bending tests have been machined directly from the produced components. On the fractured samples, fracture surface analysis has been performed in order to analyze and evaluate the influence of the process and of the alloy on the fracture behaviour.

  14. Enabling Technologies for Ceramic Hot Section Components

    SciTech Connect (OSTI)

    Venkat Vedula; Tania Bhatia

    2009-04-30

    Silicon-based ceramics are attractive materials for use in gas turbine engine hot sections due to their high temperature mechanical and physical properties as well as lower density than metals. The advantages of utilizing ceramic hot section components include weight reduction, and improved efficiency as well as enhanced power output and lower emissions as a result of reducing or eliminating cooling. Potential gas turbine ceramic components for industrial, commercial and/or military high temperature turbine applications include combustor liners, vanes, rotors, and shrouds. These components require materials that can withstand high temperatures and pressures for long duration under steam-rich environments. For Navy applications, ceramic hot section components have the potential to increase the operation range. The amount of weight reduced by utilizing a lighter gas turbine can be used to increase fuel storage capacity while a more efficient gas turbine consumes less fuel. Both improvements enable a longer operation range for Navy ships and aircraft. Ceramic hot section components will also be beneficial to the Navy's Growth Joint Strike Fighter (JSF) and VAATE (Versatile Affordable Advanced Turbine Engines) initiatives in terms of reduced weight, cooling air savings, and capability/cost index (CCI). For DOE applications, ceramic hot section components provide an avenue to achieve low emissions while improving efficiency. Combustors made of ceramic material can withstand higher wall temperatures and require less cooling air. Ability of the ceramics to withstand high temperatures enables novel combustor designs that have reduced NO{sub x}, smoke and CO levels. In the turbine section, ceramic vanes and blades do not require sophisticated cooling schemes currently used for metal components. The saved cooling air could be used to further improve efficiency and power output. The objectives of this contract were to develop technologies critical for ceramic hot section

  15. Addressing the Manufacturing Issues Associated with the use of Ceramic Materials for Diesel Engine Components.

    SciTech Connect (OSTI)

    McSpadden, SB

    2001-09-12

    This CRADA supports the objective of selecting appropriate ceramic materials for manufacturing several diesel engine components and addressing critical manufacturing issues associated with these components. Materials that were evaluated included several varieties of silicon nitride and stabilized zirconia. The critical manufacturing issues that were addressed included evaluation of the effect of grain size and the effect of the grinding process on mechanical properties, mechanical performance, reliability, and expected service life. The CRADA comprised four tasks: (1) Machining of Zirconia and Silicon Nitride Materials; (2) Mechanical Properties Characterization and Performance Testing; (3) Tribological Studies; and (4) Residual Stress Studies. Using instrumented equipment at the High Temperature Materials Laboratory (HTML) Machining and Inspection Research User Center (MIRUC), zirconia and silicon nitride materials were ground into simulated component geometries. These components were subsequently evaluated for mechanical properties, wear, and residual stress characteristics in tasks two, three, and four.

  16. Damage rates for FFTF structural components and surveillance assemblies

    SciTech Connect (OSTI)

    Simons, R.L.

    1993-08-01

    The Fast Flux Test Facility (FFTF) surveillance program provides coupon surveillance materials that are irradiated to the expected lifetime damage dose that the represented component will experience. This methodology requires a knowledge of the damage dose rates to the surveillance assemblies and to the critical locations of the structural components. This analysis updates the predicted exposures from a total fluence to a displacement per atom (dpa) basis using Monte Carlo (computer code for) neutron photon (transport) code (MCNP). The MCNP calculation improves the relative consistency and lowers the predicted damage rates uncertainty in a number of out-of-core locations. The results were used an part of the evaluation to extend the lifetime of the invessel components to 30 years in support of multiple missions for FFTF.

  17. Exascale Supercomputing and Materials DARHT: A Critical Component

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

    ... A linear- induction accelerator uses magnetic cores to ... such as NNSA's LANSCE Linac Risk Mitigation Effort ... MaRIE's proposed x-ray free-electron laser and proton radiography ...

  18. Energetic component treatability study

    SciTech Connect (OSTI)

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

    1997-11-01

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

  19. Critical Materials Institute

    ScienceCinema (OSTI)

    Alex King

    2013-06-05

    Ames Laboratory Director Alex King talks about the goals of the Critical Materials Institute in diversifying the supply of critical materials, developing substitute materials, developing tools and techniques for recycling critical materials, and forecasting materials needs to avoid future shortages.

  20. Investigation of properties and performance of ceramic composite components

    SciTech Connect (OSTI)

    Stinchcomb, W.W.; Reifsnider, K.L.; Dunyak, T.J.

    1992-06-15

    The objective of the work reported herein is to develop an understanding of the mechanical behavior of advanced ceramic composites subjected to elevated temperature and dynamic (cyclic) loading, to develop a test system and test methods to obtain the properties and performance information required to design engineering components made from ceramic composite materials, and to provide critical and comprehensive evaluations of such materials to material synthesizers and developers to support and enhance progress in ceramic composite material development. The accomplishments of the investigation include the design, development, and demonstration of a high temperature, biaxial mechanical test facility for ceramic composite tubes and the development and validation of a performance simulation model (MRLife) for ceramic composites.

  1. W88 warhead program performs successful tests | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) W88 warhead program performs successful tests Tuesday, October 28, 2014 - 1:21pm The first flight and drop tests for the latest variant of the W88 nuclear warhead are providing data for Sandia National Laboratories to validate designs, improve computer modeling and update component specifications. The two successful tests, which were conducted this summer, provide data for the program, the W88 ALT 370 (alteration), to move forward, The Critical Radar Arming and Fuzing

  2. DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility

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

    DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT, supports a critical component of LANL's primary mission: to ensure the safety, security, and effectiveness of nuclear weapons in our nation's stockpile. Los Alamos scientists built DARHT, the world's most powerful x-ray machine, to analyze mockups of nuclear weapons. At the Los Alamos National Laboratory (LANL), the Dual-Axis Radiographic Hydrodynamic Test Facility, or DARHT,

  3. Office of River Protection Prepares for Critical Waste Treatment...

    Office of Environmental Management (EM)

    Prepares for Critical Waste Treatment Plant Testing Office of River Protection Prepares for Critical Waste Treatment Plant Testing May 16, 2016 - 12:40pm Addthis Workers remove the ...

  4. Nuclear criticality safety guide

    SciTech Connect (OSTI)

    Pruvost, N.L.; Paxton, H.C.

    1996-09-01

    This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

  5. Improved Accelerated Stress Tests Based on Fuel Cell Vehicle Data

    SciTech Connect (OSTI)

    Patterson, Timothy; Motupally, Sathya

    2012-06-01

    UTC will led a top-tier team of industry and national laboratory participants to update and improve DOE’s Accelerated Stress Tests (AST’s) for hydrogen fuel cells. This in-depth investigation will focused on critical fuel cell components (e.g. membrane electrode assemblies - MEA) whose durability represented barriers for widespread commercialization of hydrogen fuel cell technology. UTC had access to MEA materials that had accrued significant load time under real-world conditions in PureMotion® 120 power plant used in transit buses. These materials are referred to as end-of-life (EOL) components in the rest of this document. Advanced characterization techniques were used to evaluate degradation mode progress using these critical cell components extracted from both bus power plants and corresponding materials tested using the DOE AST’s. These techniques were applied to samples at beginning-of-life (BOL) to serve as a baseline. These comparisons advised the progress of the various failure modes that these critical components were subjected to, such as membrane degradation, catalyst support corrosion, platinum group metal dissolution, and others. Gaps in the existing ASTs predicted the degradation observed in the field in terms of these modes were outlined. Using the gaps, new AST’s were recommended and tested to better reflect the degradation modes seen in field operation. Also, BOL components were degraded in a test vehicle at UTC designed to accelerate the bus field operation.

  6. Bibliography for nuclear criticality accident experience, alarm systems, and emergency management

    SciTech Connect (OSTI)

    Putman, V.L.

    1995-09-01

    The characteristics, detection, and emergency management of nuclear criticality accidents outside reactors has been an important component of criticality safety for as long as the need for this specialized safety discipline has been recognized. The general interest and importance of such topics receives special emphasis because of the potentially lethal, albeit highly localized, effects of criticality accidents and because of heightened public and regulatory concerns for any undesirable event in nuclear and radiological fields. This bibliography lists references which are potentially applicable to or interesting for criticality alarm, detection, and warning systems; criticality accident emergency management; and their associated programs. The lists are annotated to assist bibliography users in identifying applicable: industry and regulatory guidance and requirements, with historical development information and comments; criticality accident characteristics, consequences, experiences, and responses; hazard-, risk-, or safety-analysis criteria; CAS design and qualification criteria; CAS calibration, maintenance, repair, and testing criteria; experiences of CAS designers and maintainers; criticality accident emergency management (planning, preparedness, response, and recovery) requirements and guidance; criticality accident emergency management experience, plans, and techniques; methods and tools for analysis; and additional bibliographies.

  7. Major Components of Lending

    Broader source: Energy.gov [DOE]

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

  8. Reactor component automatic grapple

    DOE Patents [OSTI]

    Greenaway, Paul R.

    1982-01-01

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

  9. The Critical Materials Institute | Critical Materials Institute

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

    The Critical Materials Institute Director Alex King, Operations Manager Cynthia Feller, Jenni Brockpahler and Melinda Thach. Photo left to right: CMI Director Alex King, Operations Manager Cynthia Feller, Jenni Brockpahler and Melinda Thach. Not pictured: Carol Bergman. CMI staff phone 515-296-4500, e-mail CMIdirector@ameslab.gov 2332 Pammel Drive, 134 Wilhelm Hall, Iowa State University, Ames, IA 50011-1025 The Critical Materials Institute focuses on technologies that make better use of

  10. Critical Materials Workshop

    Broader source: Energy.gov [DOE]

    AMO hosted a public workshop on Tuesday, April 3, 2012 in Arlington, VA to provide background information on critical materials assessment, the current research within DOE related to critical...

  11. Critical Point Finder

    Energy Science and Technology Software Center (OSTI)

    2007-03-15

    The program robustly finds the critical points in the electric field generated by a specified collection of point charges.

  12. Energy Storage Components and Systems

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

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

  13. TESTING OF TMR SAND MANTIS FINAL REPORT

    SciTech Connect (OSTI)

    Krementz, D; William Daugherty, W

    2007-06-12

    Screening tests of Sand Mantis candidate materials selected for erosion resistance have been completed. The results of this testing identified that over a relatively short period of operation (<1 hour), measurable erosion will occur in each of the candidate zoom tube materials given equal operating exposure. Additionally, this testing has shown that erosion of the rubber discharge hose directly downstream of the vehicle could be expected to limit the service life of the discharge hose. On the basis of these test results, SRNL recommends the following; {lg_bullet} redesign of critical system components (e.g., zoom tube, discharge hose) should be conducted to improve system characteristics relative to erosion and capitalize on the results of this testing, {lg_bullet} continued efforts to deploy the Sand Mantis should include testing to better define and optimize operating parameters, and gain an understanding of system dynamics, {lg_bullet} discontinue wear testing with the selected materials pending redesign of critical system components (1st recommendation) and inclusion of other candidate materials. The final selection of additional candidate materials should be made following design changes, but might include a Stellite alloy or zirconia.

  14. Criticality Model Report

    SciTech Connect (OSTI)

    J.M. Scaglione

    2003-03-12

    The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's ability to accurately predict the effective neutron multiplication factor (k{sub eff}) for a range of conditions spanned by various critical configurations representative of the potential configurations commercial reactor assemblies stored in a waste package may take. Results of this work are an indication of the accuracy of MCNP for calculating eigenvalues, which will be used as input for criticality analyses for spent nuclear fuel (SNF) storage at the proposed Monitored Geologic Repository. The scope of this report is to document the development and validation of the criticality model. The scope of the criticality model is only applicable to commercial pressurized water reactor fuel. Valid ranges are established as part of the validation of the criticality model. This model activity follows the description in BSC (2002a).

  15. Critical Materials Workshop

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

    Critical Materials Workshop U.S. Department of Energy April 3, 2012 eere.energy.gov Dr. Leo Christodoulou Program Manager Advanced Manufacturing Office Energy Efficiency and...

  16. CRITICAL MATERIALS MUSEUM DISPLAY

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

    critical materials, rare earth elements (REE), and the national purpose of the CMI. The CSM Geology Museum is the second most visited geology museum at an American university. ...

  17. Resources | Critical Materials Institute

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

    National Laboratories Links to national laboratories and other facilities with research related to rare earth elements or critical materials. National Energy Technology Laboratory ...

  18. Timelines | Critical Materials Institute

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

    A listing of timelines about various materials of interest to rare earths and critical materials, organized by those specific to rare earth elements, general chemistry and uses. ...

  19. Careers | Critical Materials Institute

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

    Careers The Critical Materials Institute at the The Ames Laboratory, a Department of Energy national laboratory affiliated with Iowa State University, offers a variety of career ...

  20. Reference handbook: Nuclear criticality

    SciTech Connect (OSTI)

    Not Available

    1991-12-06

    The purpose for this handbook is to provide Rocky Flats personnel with the information necessary to understand the basic principles underlying a nuclear criticality.

  1. Ceramic component for electrodes

    DOE Patents [OSTI]

    Marchant, David D.

    1979-01-01

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

  2. Office of River Protection Prepares for Critical Waste Treatment Plant

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

    Testing | Department of Energy Prepares for Critical Waste Treatment Plant Testing Office of River Protection Prepares for Critical Waste Treatment Plant Testing May 16, 2016 - 12:40pm Addthis Workers remove the old test vessel from the Full-Scale Vessel Test Facility. Workers remove the old test vessel from the Full-Scale Vessel Test Facility. RICHLAND, Wash. - EM's Office of River Protection (ORP) removed a 30-ton stainless steel vessel to make way for a new one to fulfill a critical role

  3. Montena Components | Open Energy Information

    Open Energy Info (EERE)

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

  4. Integrating Program Component Executables

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

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

  5. Critical Materials Hub

    Office of Energy Efficiency and Renewable Energy (EERE)

    Critical materials, including some rare earth elements that possess unique magnetic, catalytic, and luminescent properties, are key resources needed to manufacture products for the clean energy economy. These materials are so critical to the technologies that enable wind turbines, solar panels, electric vehicles, and energy-efficient lighting that DOE's 2010 and 2011 Critical Materials Strategy reported that supply challenges for five rare earth metals—dysprosium, neodymium, terbium, europium, and yttrium—could affect clean energy technology deployment in the coming years.1, 2

  6. Components in the Pipeline

    SciTech Connect (OSTI)

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

    2011-02-24

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

  7. Ceramic component for electrodes

    DOE Patents [OSTI]

    Marchant, David D.; Bates, J. Lambert

    1980-01-01

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

  8. Critical Materials Workshop Agenda

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

    Critical Materials Workshop Sheraton Crystal City 1800 Jefferson Davis Highway, Arlington, VA April 3, 2012, 8 am - 5 pm Time (EDT) Activity Speaker 8:00 am - 9:00 am Registration ...

  9. Resources | Critical Materials Institute

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

    Resources The Critical Materials Institute offers connections to resources, including: List of resources U.S. Rare Earth Magnet Patents Table Government agency contacts CMI unique facilities CMI recent presentations Photographs via Flick'r: Critical Materials Institute, The Ames Laboratory Videos from The Ames Laboratory Webinars from Colorado School of Mines To offer comments on the CMI website or to ask questions, please contact us via e-mail at CMIdirector@ameslab.gov or call 515-296-4500.

  10. R&D ERL: G5 test and commissioning plan

    SciTech Connect (OSTI)

    Kayran, D.; Pozdeyev, E.

    2010-02-10

    Gun-to-5-cell cavity (G5) setup (Fig 1-2) can be considered as the first stage of the final BNL ERL design. The goal of the G5 setup is to test critical ERL components with the beam and characterize the beam produced by the gun. Also, this test will be used to assess effectiveness of the zigzag merger, which will be installed later in the ERL setup. The major components under the test will include the SRF gun, the five-cell SRF cavity, vacuum components, parts of the control and diagnostic systems. G5 is designed to measure the following beam parameters: (1) projected bunch emittance (?) and Twiss parameters ({alpha}, {beta}); (2) slice emittance; (3) bunch length; and (4) longitudinal and transverse halo.

  11. Decontamination of Anthrax spores in critical infrastructure and critical assets.

    SciTech Connect (OSTI)

    Boucher, Raymond M.; Crown, Kevin K.; Tucker, Mark David; Hankins, Matthew Granholm

    2010-05-01

    Decontamination of anthrax spores in critical infrastructure (e.g., subway systems, major airports) and critical assets (e.g., the interior of aircraft) can be challenging because effective decontaminants can damage materials. Current decontamination methods require the use of highly toxic and/or highly corrosive chemical solutions because bacterial spores are very difficult to kill. Bacterial spores such as Bacillus anthracis, the infectious agent of anthrax, are one of the most resistant forms of life and are several orders of magnitude more difficult to kill than their associated vegetative cells. Remediation of facilities and other spaces (e.g., subways, airports, and the interior of aircraft) contaminated with anthrax spores currently requires highly toxic and corrosive chemicals such as chlorine dioxide gas, vapor- phase hydrogen peroxide, or high-strength bleach, typically requiring complex deployment methods. We have developed a non-toxic, non-corrosive decontamination method to kill highly resistant bacterial spores in critical infrastructure and critical assets. A chemical solution that triggers the germination process in bacterial spores and causes those spores to rapidly and completely change to much less-resistant vegetative cells that can be easily killed. Vegetative cells are then exposed to mild chemicals (e.g., low concentrations of hydrogen peroxide, quaternary ammonium compounds, alcohols, aldehydes, etc.) or natural elements (e.g., heat, humidity, ultraviolet light, etc.) for complete and rapid kill. Our process employs a novel germination solution consisting of low-cost, non-toxic and non-corrosive chemicals. We are testing both direct surface application and aerosol delivery of the solutions. A key Homeland Security need is to develop the capability to rapidly recover from an attack utilizing biological warfare agents. This project will provide the capability to rapidly and safely decontaminate critical facilities and assets to return them to

  12. Predictive based monitoring of nuclear plant component degradation using support vector regression

    SciTech Connect (OSTI)

    Agarwal, Vivek; Alamaniotis, Miltiadis; Tsoukalas, Lefteri H.

    2015-02-01

    Nuclear power plants (NPPs) are large installations comprised of many active and passive assets. Degradation monitoring of all these assets is expensive (labor cost) and highly demanding task. In this paper a framework based on Support Vector Regression (SVR) for online surveillance of critical parameter degradation of NPP components is proposed. In this case, on time replacement or maintenance of components will prevent potential plant malfunctions, and reduce the overall operational cost. In the current work, we apply SVR equipped with a Gaussian kernel function to monitor components. Monitoring includes the one-step-ahead prediction of the component’s respective operational quantity using the SVR model, while the SVR model is trained using a set of previous recorded degradation histories of similar components. Predictive capability of the model is evaluated upon arrival of a sensor measurement, which is compared to the component failure threshold. A maintenance decision is based on a fuzzy inference system that utilizes three parameters: (i) prediction evaluation in the previous steps, (ii) predicted value of the current step, (iii) and difference of current predicted value with components failure thresholds. The proposed framework will be tested on turbine blade degradation data.

  13. Investigations into High Temperature Components and Packaging

    SciTech Connect (OSTI)

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

    2007-12-31

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

  14. Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks

    SciTech Connect (OSTI)

    Richard, R.F.

    1996-10-09

    This Criticality Safety Evaluation allows a mix of up to five pin containers plus two assemblies in the same Core Component Container.

  15. Component for thermoelectric generator

    DOE Patents [OSTI]

    Purdy, David L.

    1977-01-01

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

  16. Solid state lighting component

    DOE Patents [OSTI]

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

    2010-10-26

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

  17. Solid state lighting component

    DOE Patents [OSTI]

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

    2012-07-10

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

  18. Injection molded component

    DOE Patents [OSTI]

    James, Allister W; Arrell, Douglas J

    2014-09-30

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

  19. Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Radulescu, Georgeta; Mueller, Don; Goluoglu, Sedat; Hollenbach, Daniel F; Fox, Patricia B

    2007-10-01

    The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform postclosure criticality calculations. The validation process applies the criticality analysis methodology approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report. The application systems for this validation consist of waste packages containing transport, aging, and disposal canisters (TAD) loaded with commercial spent nuclear fuel (CSNF) of varying assembly types, initial enrichments, and burnup values that are expected from the waste stream and of varying degree of internal component degradation that may occur over the 10,000-year regulatory time period. The criticality computational tool being evaluated is the general-purpose Monte Carlo N-Particle (MCNP) transport code. The nuclear cross-section data distributed with MCNP 5.1.40 and used to model the various physical processes are based primarily on the Evaluated Nuclear Data File/B Version VI (ENDF/B-VI) library. Criticality calculation bias and bias uncertainty and lower bound tolerance limit (LBTL) functions for CSNF waste packages are determined based on the guidance in ANSI/ANS 8.1-1998 (Ref. 4) and ANSI/ANS 8.17-2004 (Ref. 5), as described in Section 3.5.3 of Ref. 1. The development of this report is consistent with Test Plan for: Range of Applicability and Bias Determination for Postclosure Criticality. This calculation report has been developed in support of licensing activities for the proposed repository at Yucca Mountain, Nevada, and the results of the calculation may be used in the criticality evaluation for CSNF waste packages based on a conceptual TAD canister.

  20. Surface mount component jig

    DOE Patents [OSTI]

    Kronberg, James W.

    1990-08-07

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

  1. Human Resources at Critical Materials Institute | Critical Materials...

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

    Human Resources at Critical Materials Institute Each partner within the Critical Materials Institute manages its own hiring. Use these links to find key contacts for CMI partners ...

  2. Follow-up Audit on Stockpile Surveillance Testing, IG-0744 |...

    Energy Savers [EERE]

    Surveillance Testing Program---laboratory tests, flight tests, and component tests---as of September 30? 2005. Laboratory tests are conducted on weapons' non-nuclear systems to ...

  3. Critical Assessment of Function Annotation Meeting, 2011

    SciTech Connect (OSTI)

    Friedberg, Iddo

    2015-01-21

    The Critical Assessment of Function Annotation meeting was held July 14-15, 2011 at the Austria Conference Center in Vienna, Austria. There were 73 registered delegates at the meeting. We thank the DOE for this award. It helped us organize and support a scientific meeting AFP 2011 as a special interest group (SIG) meeting associated with the ISMB 2011 conference. The conference was held in Vienna, Austria, in July 2011. The AFP SIG was held on July 15-16, 2011 (immediately preceding the conference). The meeting consisted of two components, the first being a series of talks (invited and contributed) and discussion sections dedicated to protein function research, with an emphasis on the theory and practice of computational methods utilized in functional annotation. The second component provided a large-scale assessment of computational methods through participation in the Critical Assessment of Functional Annotation (CAFA).

  4. Field Testing: Independent, Accredited Testing and Validation for the Wind Industry (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-11-01

    This fact sheet describes the field testing capabilities at the National Wind Technology Center (NWTC). NREL's specialized facilities and personnel at the NWTC provide the U.S. wind industry with scientific and engineering support that has proven critical to the development of wind energy for U.S. energy needs. The NWTC's specialized field-testing capabilities have evolved over 30 years of continuous support by the U.S. Department of Energy Wind and Hydropower Technologies Program and long standing industry partnerships. The NWTC provides wind industry manufacturers, developers, and operators with turbine and component testing all in one convenient location. Although industry utilizes sophisticated modeling tools to design and optimize turbine configurations, there are always limitations in modeling capabilities, and testing is a necessity to ensure performance and reliability. Designs require validation and testing is the only way to determine if there are flaws. Prototype testing is especially important in capturing manufacturing flaws that might require fleet-wide retrofits. The NWTC works with its industry partners to verify the performance and reliability of wind turbines that range in size from 400 Watts to 3 megawatts. Engineers conduct tests on components and full-scale turbines in laboratory environments and in the field. Test data produced from these tests can be used to validate turbine design codes and simulations that further advance turbine designs.

  5. Sandia_HighTemperatureComponentEvaluation_2015.

    SciTech Connect (OSTI)

    Cashion, Avery T.

    2015-03-01

    The objective of this project is to perform independent evaluation of high temperature components to determine their suitability for use in high temperature geothermal tools. Development of high temperature components has been increasing rapidly due to demand from the high temperature oil and gas exploration and aerospace industries. Many of these new components are at the late prototype or first production stage of development and could benefit from third party evaluation of functionality and lifetime at elevated temperatures. In addition to independent testing of new components, this project recognizes that there is a paucity of commercial-off-the-shelf COTS components rated for geothermal temperatures. As such, high-temperature circuit designers often must dedicate considerable time and resources to determine if a component exists that they may be able to knead performance out of to meet their requirements. This project aids tool developers by characterization of select COTS component performances beyond published temperature specifications. The process for selecting components includes public announcements of project intent (e.g., FedBizOps), direct discussions with candidate manufacturers,and coordination with other DOE funded programs.

  6. AVLIS Criticality risk assessment

    SciTech Connect (OSTI)

    Brereton, S.J., LLNL

    1998-04-29

    Evaluation of criticality safety has become an important task in preparing for the Atomic Vapor Laser Isotope Separation (AVLIS) uranium enrichment runs that will take place during the Integrated Process Demonstration (IPD) at Lawrence Livermore National Laboratory (LLNL). This integrated operation of AVLIS systems under plant-like conditions will be used to verify the performance of process equipment and to demonstrate the sustained integrated enrichment performance of these systems using operating parameters that are similar to production plant specifications. Because of the potential criticality concerns associated with enriched uranium, substantial effort has been aimed towards understanding the potential system failures of interest from a criticality standpoint, and evaluating them in detail. The AVLIS process is based on selective photoionization of uranium atoms of atomic weight 235 (U-235) in a vapor stream, followed by electrostatic extraction. The process is illustrated in Figure 1. Two major subsystems are involved: the uranium separator and the laser system. In the separator, metallic uranium is fed into a crucible where it is heated and vaporized by an electron beam. The atomic U-235/U-238 vapor stream moves away from the molten uranium and is illuminated by precisely tuned beams of dye laser light. Upon absorption of the tuned dye laser light, the U-235 atoms become excited and eject electrons (become photoionized), giving them a net positive charge. The ions of U-235 are moved preferentially by an electrostatic field to condense on the product collector, forming the enriched uranium product. The remaining vapor, which is depleted in U-235 (tails), passes unaffected through the photoionization/extractor zone and accumulates on collectors in the top of the separator. Tails and product collector surfaces operate at elevated temperatures so that deposited materials flow as segregated liquid streams. The separated uranium condensates (uranium enriched in

  7. Further testing and development of an 11-watt Stirling converter

    SciTech Connect (OSTI)

    Ross, B.A.; Montgomery, W.L.

    1995-12-31

    Three previous IECEC papers describe the development of an 11-watt Radioisotope Stirling Generator (RSG) intended for remote power applications. This paper describes more recent testing and development activities. Testing of the engineering model (EM) was performed to determine the effect of heat rejection temperature, thermal input and initial charge pressure on thermal efficiency. Shock testing of the generator included a drop test and 3 hours of testing in a random vibration environment where g{sup 2}/Hz = 0.04. Endurance testing of a complete Stirling converter continues, with over 15,000 maintenance-free operating hours. Endurance testing of critical subsystems and components has achieved 14,000 to 26,000 hours of operation without failure. Minor changes to the RSG prototype design, based on the development of the EM, are described.

  8. Critical Infrastructure Modeling: An Approach to Characterizing Interdependencies of Complex Networks & Control Systems

    SciTech Connect (OSTI)

    Stuart Walsh; Shane Cherry; Lyle Roybal

    2009-05-01

    Critical infrastructure control systems face many challenges entering the 21st century, including natural disasters, cyber attacks, and terrorist attacks. Revolutionary change is required to solve many existing issues, including gaining greater situational awareness and resiliency through embedding modeling and advanced control algorithms in smart sensors and control devices instead of in a central controller. To support design, testing, and component analysis, a flexible simulation and modeling capability is needed. Researchers at Idaho National Laboratory are developing and evaluating such a capability through their CIPRsim modeling and simulation framework.

  9. History of critical experiments at Pajarito Site

    SciTech Connect (OSTI)

    Paxton, H.C.

    1983-03-01

    This account describes critical and subcritical assemblies operated remotely at the Pajarito Canyon Site at the Los Alamos National Laboratory. Earliest assemblies, directed exclusively toward the nuclear weapons program, were for safety tests. Other weapon-related assemblies provided neutronic information to check detailed weapon calculations. Topsy, the first of these critical assemblies, was followed by Lady Godiva, Jezebel, Flattop, and ultimately Big Ten. As reactor programs came to Los Alamos, design studies and mockups were tested at Pajarito Site. For example, nearly all 16 Rover reactors intended for Nevada tests were preceded by zero-power mockups and proof tests at Pajarito Site. Expanded interest and capability led to fast-pulse assemblies, culminating in Godiva IV and Skua, and to the Kinglet and Sheba solution assemblies.

  10. Test and Demonstration Assets of New Mexico

    SciTech Connect (OSTI)

    2008-03-31

    This document was developed by the Arrowhead Center of New Mexico State University as part of the National Security Preparedness Project (NSPP), funded by a DOE/NNSA grant. The NSPP has three primary components: business incubation, workforce development, and technology demonstration and validation. The document contains a survey of test and demonstration assets in New Mexico available for external users such as small businesses with security technologies under development. Demonstration and validation of national security technologies created by incubator sources, as well as other sources, are critical phases of technology development. The NSPP will support the utilization of an integrated demonstration and validation environment.

  11. Utility advanced turbine systems (ATS) technology readiness testing -- Phase 3. Annual report, October 1, 1996--September 30, 1997

    SciTech Connect (OSTI)

    1997-12-31

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown.

  12. Utility advanced turbine systems (ATS) technology readiness testing and pre-commercial demonstration. Quarterly report, January 1--March 31, 1997

    SciTech Connect (OSTI)

    1997-12-31

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which will be sited and operated in Phase 4. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown. This report summarizes work accomplished in 1Q97.

  13. Utility advanced turbine systems (ATS) technology readiness testing and pre-commercial demonstration. Quarterly report, April 1--June 30, 1997

    SciTech Connect (OSTI)

    1997-12-31

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which will be sited and operated in Phase 4. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown. This report summarizes work accomplished in 2Q97.

  14. Utility Advanced Turbine Systems (ATS) technology readiness testing and pre-commercialization demonstration. Quarterly report, October 1--December 31, 1996

    SciTech Connect (OSTI)

    1997-06-01

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the U.S. Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which will be sited and operated in Phase 4. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue.

  15. CMI Unique Facilities | Critical Materials Institute

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

    CMI Unique Facilities The Critical Materials Institute has created unique facilities that are available for additional research and collaboration. These include the following. There are hotlinks for some of the infrastructure and equipment listed. Those links provide information about the unique facility, where it was developed within CMI and who to contact for more information. Pilot-Scale Separations Test Bed Facility Filtration Test Facility Bulk Combinatoric Materials Synthesis Facility

  16. Only critical information was scanned

    Office of Legacy Management (LM)

    Only critical information was scanned. Entire document is available upon request - Click here to email a

  17. Critical Skills Master's Program

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

    Skills Master's Program (CSMP): The Critical Skills Master's Program (CSMP) provides exceptional bachelor's-level candidates with the opportunity to pursue a fully funded Master's of Science degree. Successful applicants will become regular full-time Sandia employees and join multidisciplinary teams that are advancing the frontiers of science and technology to solve the world's greatest challenges. Program Requirements: * Apply to a minimum of 3 nationally accredited universities. * Successfully

  18. Sprayed skin turbine component

    DOE Patents [OSTI]

    Allen, David B

    2013-06-04

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

  19. Component failure data handbook

    SciTech Connect (OSTI)

    Gentillon, C.D.

    1991-04-01

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

  20. Influence of fast magnetic pulses on the superconducting magnet test facility TOSKA

    SciTech Connect (OSTI)

    Biro, O.; Maurer, W.

    1994-09-01

    An overview is given about the influence of fast magnetic field pulses (up to 40 T/s) on components of the TOSKA magnet test facility at KfK, Karlsruhe. Such fast magnetic field changes occur during the operation of poloidal field coils and accidental plasma disruptions in a Tokamak and also during safety discharges of superconducting magnets. Induced eddy currents in surrounding conductive components can cause some detrimental damage. FEM calculations were performed in order to study the influence on critical components of TOSKA and to identify necessary modifications of the facility. The paper presents the results of these calculations.

  1. NREL: Hydrogen and Fuel Cells Research - Hydrogen System Component

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

    Validation System Component Validation NREL's hydrogen system component validation studies focus on improving the reliability of compressors and other hydrogen system components. Reliable components are needed to ensure the success of hydrogen fueling stations and support the commercial deployment of fuel cell electric vehicles and material handling equipment. NREL's technology validation team is collaborating with industry to test and validate the commercial readiness of hydrogen system

  2. Canister Transfer Facility Criticality Calculations

    SciTech Connect (OSTI)

    J.E. Monroe-Rammsy

    2000-10-13

    The objective of this calculation is to evaluate the criticality risk in the surface facility for design basis events (DBE) involving Department of Energy (DOE) Spent Nuclear Fuel (SNF) standardized canisters (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M&O] 2000a). Since some of the canisters will be stored in the surface facility before they are loaded in the waste package (WP), this calculation supports the demonstration of concept viability related to the Surface Facility environment. The scope of this calculation is limited to the consideration of three DOE SNF fuels, specifically Enrico Fermi SNF, Training Research Isotope General Atomic (TRIGA) SNF, and Mixed Oxide (MOX) Fast Flux Test Facility (FFTF) SNF.

  3. CMI Social Media | Critical Materials Institute

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

    Social Media Facebook: Critical Materials Institute Twitter: CMI_hub LinkedIn: Critical Materials Institute Flickr: Critical Materials Institute

  4. CMI Webinar: Energy Materials and Criticality, 2015-2030 | Critical...

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

    CMI Webinar: Energy Materials and Criticality, 2015-2030 The CMI Webinar series includes a CMI-only presentation "CMI Webinar: Energy Materials and Criticality, 2015-2030" by Rod...

  5. Utility advanced turbine systems (ATS) technology readiness testing

    SciTech Connect (OSTI)

    2000-09-15

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of a highly efficient, environmentally superior, and cost-competitive utility ATS for base-load utility-scale power generation, the GE 7H (60 Hz) combined cycle power system, and related 9H (50 Hz) common technology. The major effort will be expended on detail design. Validation of critical components and technologies will be performed, including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially by GE. This change has resulted from DOE's request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include full speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown.

  6. Utility Advanced Turbine Systems (ATS) technology readiness testing

    SciTech Connect (OSTI)

    1999-05-01

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed, including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially by GE. This change has resulted horn DOE's request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include fill speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown.

  7. Utility Advanced Turbine Systems (ATS) Technology Readiness Testing

    SciTech Connect (OSTI)

    1998-10-29

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the U.S. Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed, including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially by GE. This change has resulted from DOE's request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include full speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown in Figure 1-1. This report summarizes work accomplished in 2Q98. The most significant accomplishments are listed in the report.

  8. UTILITY ADVANCED TURBINE SYSTEMS (ATS) TECHNOLOGY READINESS TESTING

    SciTech Connect (OSTI)

    Unknown

    1998-10-01

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between Ge and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed, including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially be GE. This change has resulted from DOE's request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include full speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown. This report summarizes work accomplished from 4Q97 through 3Q98.

  9. CMI Develops Critical Materials Museum Exhibit | Critical Materials

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

    Institute Develops Critical Materials Museum Exhibit People view CMI exhibit at Colorado School of Mines Geology Museum The Critical Materials Institute developed a museum exhibit at the Colorado School of Mines Geology Museum. The Critical Materials Museum Exhibit is a prototype exhibit for education professionals interested in building a similar exhibit. A series of "how to" reports is being generated at key stages of the design-build process: First report: Critical Materials

  10. Cooling system for electronic components

    DOE Patents [OSTI]

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

    2015-12-15

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

  11. Critical Infrastructure Modeling System

    Energy Science and Technology Software Center (OSTI)

    2004-10-01

    The Critical Infrastructure Modeling System (CIMS) is a 3D modeling and simulation environment designed to assist users in the analysis of dependencies within individual infrastructure and also interdependencies between multiple infrastructures. Through visual cuing and textual displays, a use can evaluate the effect of system perturbation and identify the emergent patterns that evolve. These patterns include possible outage areas from a loss of power, denial of service or access, and disruption of operations. Method ofmore » Solution: CIMS allows the user to model a system, create an overlay of information, and create 3D representative images to illustrate key infrastructure elements. A geo-referenced scene, satellite, aerial images or technical drawings can be incorporated into the scene. Scenarios of events can be scripted, and the user can also interact during run time to alter system characteristics. CIMS operates as a discrete event simulation engine feeding a 3D visualization.« less

  12. Critical Magnetic Field Determination of Superconducting Materials

    SciTech Connect (OSTI)

    Canabal, A.; Tajima, T.; Dolgashev, V.A.; Tantawi, S.G.; Yamamoto, T.; /Tsukuba, Natl. Res. Lab. Metrol.

    2011-11-04

    Superconducting RF technology is becoming more and more important. With some recent cavity test results showing close to or even higher than the critical magnetic field of 170-180 mT that had been considered a limit, it is very important to develop a way to correctly measure the critical magnetic field (H{sup RF}{sub c}) of superconductors in the RF regime. Using a 11.4 GHz, 50-MW, <1 {mu}s, pulsed power source and a TE013-like mode copper cavity, we have been measuring critical magnetic fields of superconductors for accelerator cavity applications. This device can eliminate both thermal and field emission effects due to a short pulse and no electric field at the sample surface. A model of the system is presented in this paper along with a discussion of preliminary experimental data.

  13. Initial Component Testing for a Germanium Array Cryostat (Technical...

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

    ... Close Cite: Bibtex Format Close 0 pages in this document matching the terms "" Search For Terms: Enter terms in the toolbar above to search the full text of this document for ...

  14. Annular Core Research Reactor - Critical to Science-Based Weapons...

    National Nuclear Security Administration (NNSA)

    environments needed to simulate nuclear weapons effects on full-scale systems. This test capability is critical to science-based weapons design and certification. The ACRR is a ...

  15. PNNL Results from 2009 Silene Criticality Accident Dosimeter Intercomparison Exercise

    SciTech Connect (OSTI)

    Hill, Robin L.; Conrady, Matthew M.

    2010-06-30

    This document reports the results of testing of the Hanford Personnel Nuclear Accident Dosimeter (PNAD) during a criticality accident dosimeter intercomparison exercise at the CEA Valduc Center on October 13, 14, and 15, 2009.

  16. Utility Advanced Turbine System (ATS) technology readiness testing and pre-commercial demonstration -- Phase 3. Quarterly report, April 1--June 30, 1996

    SciTech Connect (OSTI)

    1996-12-31

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detailed design. Validation of critical components and technologies will be performed including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which will be sited and operated in Phase 4. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. This report summarizes work accomplished during the period 2Q96.

  17. The role of troublesome components in plutonium vitrification

    SciTech Connect (OSTI)

    Li, Hong; Vienna, J.D.; Peeler, D.K.; Hrma, P.; Schweiger, M.J.

    1996-05-01

    One option for immobilizing surplus plutonium is vitrification in a borosilicate glass. Two advantages of the glass form are (1) high tolerance to feed variability and, (2) high solubility of some impurity components. The types of plutonium-containing materials in the United States inventory include: pits, metals, oxides, residues, scrap, compounds, and fuel. Many of them also contain high concentrations of carbon, chloride, fluoride, phosphate, sulfate, and chromium oxide. To vitrify plutonium-containing scrap and residues, it is critical to understand the impact of each component on glass processing and chemical durability of the final product. This paper addresses glass processing issues associated with these troublesome components. It covers solubility limits of chlorine, fluorine, phosphate, sulfate, and chromium oxide in several borosilicate based glasses, and the effect of each component on vitrification (volatility, phase segregation, crystallization, and melt viscosity). Techniques (formulation, pretreatment, removal, and/or dilution) to mitigate the effect of these troublesome components are suggested.

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

    SciTech Connect (OSTI)

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

    1992-10-01

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

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

    SciTech Connect (OSTI)

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

    1992-10-01

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

  20. Multi-tipped optical component

    DOE Patents [OSTI]

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

    2010-04-13

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

  1. Multi-component assembly casting

    DOE Patents [OSTI]

    James, Allister W.

    2015-10-13

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

  2. Dynamic strain gages analysis of critical welds used in power plant circuit breakers

    SciTech Connect (OSTI)

    MacDougall, E.A. ); Wilhelm, W.G. )

    1990-01-01

    A history of failures in power plant circuit breakers associated with critical welds in the internal pole shafts has been investigated. This paper describes the test, equipment, and instrumentation and summarized the preliminary results of testing performed on these breakers at Brookhaven National Laboratory. It includes the description of the instrumentation including the use of a full bridge strain gage sensor and instrumentation amplifier connected to an oscilloscope. The combination provided a sensitive instrument capable of revealing subtle changes in circuit breaker performance. The strain gages were attached to pole shafts and monitored dynamically. The observed changes in wave signature were recorded as a function of accumulated operating cycles. Complex changes in wave shape recorded on an oscillograph indicate patterns related to impending weld failure. The life expectancy measured in the number of circuit breaker open and closing cycles is compared with the weld and other component failures. 8 refs., 4 figs.

  3. Review of Yucca Mountain Disposal Criticality Studies

    SciTech Connect (OSTI)

    Scaglione, John M; Wagner, John C

    2011-01-01

    The U.S. Department of Energy (DOE), Office of Civilian Radioactive Waste Management, submitted a license application for construction authorization of a deep geologic repository at Yucca Mountain, Nevada, in June of 2008. The license application is currently under review by the U.S. Nuclear Regulatory Commission. However,on March 3, 2010 the DOE filed a motion requesting withdrawal of the license application. With the withdrawal request and the development of the Blue Ribbon Commission to seek alternative strategies for disposing of spent fuel, the status of the proposed repository at Yucca Mountain is uncertain. What is certain is that spent nuclear fuel (SNF) will continue to be generated and some long-lived components of the SNF will eventually need a disposition path(s). Strategies for the back end of the fuel cycle will continue to be developed and need to include the insights from the experience gained during the development of the Yucca Mountain license application. Detailed studies were performed and considerable progress was made in many key areas in terms of increased understanding of relevant phenomena and issues regarding geologic disposal of SNF. This paper reviews selected technical studies performed in support of the disposal criticality analysis licensing basis and the use of burnup credit. Topics include assembly misload analysis, isotopic and criticality validation, commercial reactor critical analyses, loading curves, alternative waste package and criticality control studies, radial burnup data and effects, and implementation of a conservative application model in the criticality probabilistic evaluation as well as other information that is applicable to operations regarding spent fuel outside the reactor. This paper summarizes the work and significant accomplishments in these areas and provides a resource for future, related activities.

  4. Vehicle Technologies Office: Integration, Validation and Testing...

    Energy Savers [EERE]

    Integration Laboratory to integrate, validate, and test advanced vehicle technologies. ... To integrate and test vehicle components and subsystems, DOE's national laboratories use ...

  5. Accelerators for Testing Radiation Tolerances of Electronics...

    Office of Science (SC) Website

    Accelerated beams test semiconductor devices for tolerances to space radiation. ... The ability to test in air makes it possible to quickly change components and to easily ...

  6. Upcoming H2USA Workshop: Hydrogen Fueling Station Component Listings

    Broader source: Energy.gov [DOE]

    H2USA will host an online workshop about hydrogen fueling station component listings on April 22 from 2 to 3:30 p.m. Eastern Daylight Time. This workshop will focus on the need for components for hydrogen fueling stations to be listed by Nationally Recognized Testing Laboratories (NRTLs).

  7. Heat treating of manufactured components

    SciTech Connect (OSTI)

    Ripley, Edward B.

    2012-05-22

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

  8. CMI Factsheet | Critical Materials Institute

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

    CMI Factsheet 3D printer uses laser and metals to build new combinations of materials What is the Energy Innovation Hub for Critical Materials? Created by the U.S. Department of Energy, the Energy Innovation Hub is operated under the name the Critical Materials Institute. CMI is led by the DOE's Ames Laboratory, and managed by DOE's Advanced Manufacturing Office. It brings together the expertise of DOE national laboratories, universities, and industry partners to eliminate materials criticality

  9. Criticality Safety Basics for INL Emergency Responders

    SciTech Connect (OSTI)

    Valerie L. Putman

    2012-08-01

    This document is a modular self-study guide about criticality safety principles for Idaho National Laboratory emergency responders. This guide provides basic criticality safety information for people who, in response to an emergency, might enter an area that contains much fissionable (or fissile) material. The information should help responders understand unique factors that might be important in responding to a criticality accident or in preventing a criticality accident while responding to a different emergency.

    This study guide specifically supplements web-based training for firefighters (0INL1226) and includes information for other Idaho National Laboratory first responders. However, the guide audience also includes other first responders such as radiological control personnel.

    For interested readers, this guide includes clearly marked additional information that will not be included on tests. The additional information includes historical examples (Been there. Done that.), as well as facts and more in-depth information (Did you know …).

    INL criticality safety personnel revise this guide as needed to reflect program changes, user requests, and better information. Revision 0, issued May 2007, established the basic text. Revision 1 incorporates operation, program, and training changes implemented since 2007. Revision 1 increases focus on first responders because later responders are more likely to have more assistance and guidance from facility personnel and subject matter experts. Revision 1 also completely reorganized the training to better emphasize physical concepts behind the criticality controls that help keep emergency responders safe. The changes are based on and consistent with changes made to course 0INL1226.

  10. My Account | Critical Materials Institute

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

    My Account Primary tabs Log in(active tab) Request new password Username * Enter your Critical Materials Institute username. Password * Enter the password that accompanies your ...

  11. Criticality Safety | Department of Energy

    Office of Environmental Management (EM)

    Contact Garrett Smith 301-903-7440 DOE Employee Concerns Program Environment Worker Health & Safety Facility Safety Nuclear Safety Criticality Safety Quality Assurance Risk ...

  12. An assessment of criticality safety at the Department of Energy Rocky Flats Plant, Golden, Colorado, July--September 1989

    SciTech Connect (OSTI)

    Mattson, Roger J.

    1989-09-01

    This is a report on the 1989 independent Criticality Safety Assessment of the Rocky Flats Plant, primarily in response to public concerns that nuclear criticality accidents involving plutonium may have occurred at this nuclear weapon component fabrication and processing plant. The report evaluates environmental issues, fissile material storage practices, ventilation system problem areas, and criticality safety practices. While no evidence of a criticality accident was found, several recommendations are made for criticality safety improvements. 9 tabs.

  13. Energy Systems High Pressure Test Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01

    This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Energy Systems High Pressure Test Laboratory at the Energy Systems Integration Facility. The purpose of the Energy Systems High Pressure Test Laboratory at NREL's Energy Systems Integration Facility (ESIF) is to provide space where high pressure hydrogen components can be safely tested. High pressure hydrogen storage is an integral part of energy storage technology for use in fuel cell and in other distributed energy scenarios designed to effectively utilize the variability inherent with renewable energy sources. The high pressure storage laboratory is co-located with energy storage activities such as ultra-capacitors, super conducting magnetic flywheel and mechanical energy storage systems laboratories for an integrated approach to system development and demonstration. Hazards associated with hydrogen storage at pressures up to 10,000 psi include oxygen displacement, combustion, explosion, and pressurization of room air due to fast release and physical hazards associated with burst failure modes. A critical understanding of component failure modes is essential in developing reliable, robust designs that will minimize failure risk beyond the end of service life. Development of test protocol for accelerated life testing to accurately scale to real world operating conditions is essential for developing regulations, codes and standards required for safe operation. NREL works closely with industry partners in providing support of advanced hydrogen technologies. Innovative approaches to product design will accelerate commercialization into new markets. NREL works with all phases of the product design life cycle from early prototype development to final certification testing. High pressure tests are performed on hydrogen components, primarily for the validation of developing new codes and standards for high pressure hydrogen applications. The

  14. CMI Webinar: Critical Elements in Phosphate | Critical Materials Institute

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

    Critical Elements in Phosphate The CMI Webinar series began with a presentation on Critical Elements in Phosphate by Patrick Zhang, Florida Industrial and Phosphate Research Institute (FIPR), on March 24, 2015. The recording of the webinar runs nearly 38 minutes (37:54

  15. Apparatus and method for critical current measurements

    DOE Patents [OSTI]

    Martin, Joe A.; Dye, Robert C.

    1992-01-01

    An apparatus for the measurement of the critical current of a superconductive sample, e.g., a clad superconductive sample, the apparatus including a conductive coil, a means for maintaining the coil in proximity to a superconductive sample, an electrical connection means for passing a low amplitude alternating current through the coil, a cooling means for maintaining the superconductive sample at a preselected temperature, a means for passing a current through the superconductive sample, and, a means for monitoring reactance of the coil, is disclosed, together with a process of measuring the critical current of a superconductive material, e.g., a clad superconductive material, by placing a superconductive material into the vicinity of the conductive coil of such an apparatus, cooling the superconductive material to a preselected temperature, passing a low amplitude alternating current through the coil, the alternating current capable of generating a magnetic field sufficient to penetrate, e.g., any cladding, and to induce eddy currents in the superconductive material, passing a steadily increasing current through the superconductive material, the current characterized as having a different frequency than the alternating current, and, monitoring the reactance of the coil with a phase sensitive detector as the current passed through the superconductive material is steadily increased whereby critical current of the superconductive material can be observed as the point whereat a component of impedance deviates.

  16. : The Resumption of Criticality Experiments Facility Operations...

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

    nuclear criticality experiments and hands-on training in nuclear safeguards, criticality safety and emergency response in support of the National Criticality Safety Program. ...

  17. Getting It Right: Accurate Testing and Assessments Critical to...

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

    called the Coordinating Research Council (CRC), released a report on the effects of E15 ... We believe the study is significantly flawed. The CRC failed to establish a proper control ...

  18. Apparatus for remotely handling components

    DOE Patents [OSTI]

    Szkrybalo, Gregory A.; Griffin, Donald L.

    1994-01-01

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

  19. Development of a structural health monitoring system for the life assessment of critical transportation infrastructure.

    SciTech Connect (OSTI)

    Roach, Dennis Patrick; Jauregui, David Villegas; Daumueller, Andrew Nicholas

    2012-02-01

    Recent structural failures such as the I-35W Mississippi River Bridge in Minnesota have underscored the urgent need for improved methods and procedures for evaluating our aging transportation infrastructure. This research seeks to develop a basis for a Structural Health Monitoring (SHM) system to provide quantitative information related to the structural integrity of metallic structures to make appropriate management decisions and ensuring public safety. This research employs advanced structural analysis and nondestructive testing (NDT) methods for an accurate fatigue analysis. Metal railroad bridges in New Mexico will be the focus since many of these structures are over 100 years old and classified as fracture-critical. The term fracture-critical indicates that failure of a single component may result in complete collapse of the structure such as the one experienced by the I-35W Bridge. Failure may originate from sources such as loss of section due to corrosion or cracking caused by fatigue loading. Because standard inspection practice is primarily visual, these types of defects can go undetected due to oversight, lack of access to critical areas, or, in riveted members, hidden defects that are beneath fasteners or connection angles. Another issue is that it is difficult to determine the fatigue damage that a structure has experienced and the rate at which damage is accumulating due to uncertain history and load distribution in supporting members. A SHM system has several advantages that can overcome these limitations. SHM allows critical areas of the structure to be monitored more quantitatively under actual loading. The research needed to apply SHM to metallic structures was performed and a case study was carried out to show the potential of SHM-driven fatigue evaluation to assess the condition of critical transportation infrastructure and to guide inspectors to potential problem areas. This project combines the expertise in transportation infrastructure at New

  20. Ceramic component for MHD electrode

    DOE Patents [OSTI]

    Marchant, David D.; Bates, Junior L.

    1981-01-01

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

  1. Characteristics, finite element analysis, test description, and preliminary test results of the STM4-120 kinematic Stirling engine

    SciTech Connect (OSTI)

    Linker, K.L.; Rawlinson, K.S.; Smith, G.

    1991-10-01

    The Department of Energy's Solar Thermal Program has as one of its program elements the development and evaluation of conversion device technologies applicable to dish-electric systems. The primary research and development combines a conversion device (heat engine), solar receiver, and generator mounted at the focus of a parabolic dish concentrator. The Stirling-cycle heat engine was identified as the conversion device for dish-electric with the most potential for meeting the program's goals for efficiency, reliability, and installed cost. To advance the technology toward commercialization, Sandia National Laboratories has acquired a Stirling Thermal Motors, Inc., kinematic Stirling engine, STM4-120, for evaluation. The engine is being bench-tested at Sandia's Engine Test Facility and will be combined later with a solar receiver for on-sun evaluation. This report presents the engine characteristics, finite element analyses of critical engine components, test system layout, instrumentation, and preliminary performance results from the bench test.

  2. Advanced Component Research Facility (ACRES)

    SciTech Connect (OSTI)

    Bohn, M.

    1980-07-01

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

  3. Microsoft Word - Critical Infrastructure Security and Resilience...

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

    Presidential Proclamation -- Critical Infrastructure Security and Resilience Month, 2013 CRITICAL INFRASTRUCTURE SECURITY AND RESILIENCE MONTH, 2013 - - - - - - - BY THE ...

  4. CMI Offers Webinars on Critical Materials and Rare Earths | Critical

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

    Materials Institute Offers Webinars on Critical Materials and Rare Earths CMI at Mines offers webinars about critical materials at no charge. Registration is required to obtain a link to the webinar. September 21: Parans Paranthaman, Oak Ridge National Laboratory, "Additive Manufacturing of NdFeB Magnets" Registration is open August 23: CMI Director Alex King, "CMI Director's Perspective." A recording of the webinar is available. July 20: Corby Anderson, Colorado School

  5. Design and cost study of critical OC-OTEC plant components: Final subcontract report

    SciTech Connect (OSTI)

    Valenzuela, J.A.; Jasinski, T.; Stacey, W.D.; Patel, B.R.; Dolan, F.Y.

    1988-06-01

    During the FY 1983-84, system analysis studies were performed by the Florida Solar Energy Center and Creare Inc. to assess the economic and technological viability of the OC-OTEC concept for producing both electricity and fresh water on a small scale. A major conclusion of the study was that land-based OC-OTEC plants as small as 10 MWe may be economically feasible in island communities if cost credits are taken for the fresh water produced. The present study builds upon and extends the results of that work. Assess the effect of the seasonal variation in the ocean surface water temperature on the performance of OC-OTEC plants; evaluate the technical feasibility of building small scale OC-OTEC plants using existing low pressure steam turbine rotor designs; refine the plant structure model developed during the Phase I study; and develop background information and analyses to evaluate the various alternative strategies for handling noncondensible gases in OC-OTEC plants. Refinements in OC-OTEC plant performance and cost models performed during the present study have reduced the estimated cost of a 10 MW baseline plant from 99 to 72M$. Further cost reduction of 5 to 10M$ is anticipated from the revised structure cost model and the implementation of barometric leg deaeration and hydraulic compression. Therefore, the results from this study reinforce the earlier conclusion that small-scale OC-OTEC plants are competitive at present for the production of electricity and fresh water in the Caribbean and Pacific Islands. OC-OTEC represents a technology with significant potential. We recommend that it be aggressively pursued. 33 refs., 67 figs., 20 tabs.

  6. Instrumentation of Current Technology Testing and Replicating Harsh Environments

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

    Abrasion Testing of Critical Components of Hydrokinetic Devices 10/17/2012 University of Alaska Anchorage 2 Project Team o Ocean Renewable Power Company (ORPC) o Jarlath McEntee o Monty Worthington o University of Alaska Anchorage (UAA) o Faculty o Thomas Ravens o Todd Petersen o Muhammad Ali o Research Assistants o Tim Kirk o Jacob Clark o Angus Bromaghin 10/17/2012 University of Alaska Anchorage 3 ORPC Technology o TideGen Power System (TGU) o Designed to generate electricity at water depths

  7. ZEST flight test experiments, Kauai Test Facility, Hawaii. Test report

    SciTech Connect (OSTI)

    Cenkci, M.J.

    1991-07-01

    The Strategic Defense Initiative Organization (SDIO) is proposing to execute two ZEST flight experiments to obtain information related to the following objectives: validation of payload modeling; characterization of a high energy release cloud; and documentation of scientific phenomena that may occur as a result of releasing a high energy cloud. The proposed action is to design, develop, launch, and detonate two payloads carrying high energy explosives. Activities required to support this proposal include: (1) execution of component assembly tests at Space Data Division (SDD) in Chandler, Arizona and Los Alamos National Laboratory (LANL) in Los Alamos, New Mexico, and (2) execution of pre-flight flight test activities at Kauai Test Facility.

  8. CriTi-CAL: A computer program for Critical Coiled Tubing Calculations

    SciTech Connect (OSTI)

    He, X.

    1995-12-31

    A computer software package for simulating coiled tubing operations has been developed at Rogaland Research. The software is named CriTiCAL, for Critical Coiled Tubing Calculations. It is a PC program running under Microsoft Windows. CriTi-CAL is designed for predicting force, stress, torque, lockup, circulation pressure losses and along-hole-depth corrections for coiled tubing workover and drilling operations. CriTi-CAL features an user-friendly interface, integrated work string and survey editors, flexible input units and output format, on-line documentation and extensive error trapping. CriTi-CAL was developed by using a combination of Visual Basic and C. Such an approach is an effective way to quickly develop high quality small to medium size software for the oil industry. The software is based on the results of intensive experimental and theoretical studies on buckling and post-buckling of coiled tubing at Rogaland Research. The software has been validated by full-scale test results and field data.

  9. Severe shock and vibration environments for electronic components

    SciTech Connect (OSTI)

    Martinez, D.R.

    1990-01-01

    Electronic components used in system applications must be qualified to mechanical shock and vibration environments. Often these environments are severe, requiring the development and use of special test techniques and procedures. Environmental specifications are based upon analytical model predictions and measured test data. Test specifications are determined after careful consideration of simulation techniques, input levels, dynamic behavior of the test fixturing, as well as an assessment of the degree of conservatism imposed by the specification and testing procedures. The process of determining component shock and vibration specifications is discussed, beginning with the initial description of system and subsystem level environments, and concluding with component level test specifications. Included is a discussion of the difference between environmental specifications and test specifications, and the instrumentation/measurement problems associated with obtaining valid field measurements for severe shock data. The role of finite element analysis in predicting the dynamic structural response of components is also explained. Shock data analysis techniques are described including both time-domain and frequency-domain characterizations of the data. The resonant plate shock testing technique for simulating severe shock environments is presented, including difficulties that arise in practical applications. 18 refs., 10 figs.

  10. Autoclave nuclear criticality safety analysis

    SciTech Connect (OSTI)

    D`Aquila, D.M.; Tayloe, R.W. Jr.

    1991-12-31

    Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

  11. CRAD, NNSA- Criticality Safety (CS)

    Broader source: Energy.gov [DOE]

    CRAD for Criticality Safety (CS). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  12. invention disclosures | Critical Materials Institute

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

    invention disclosures CMI Invention Disclosures Success for the Critical Materials Institute will be defined by how well it meets its mission to assure supply chains of materials critical to clean energy technologies. To enable innovation in U.S. manufacturing and to enhance U.S. energy security, CMI must develop, demonstrate, and deploy clean energy technology. To direct research in a way to minimize the time to discovery and the time between discovery and deployment, the CMI team includes both

  13. Lecture notes for criticality safety

    SciTech Connect (OSTI)

    Fullwood, R.

    1992-03-01

    These lecture notes for criticality safety are prepared for the training of Department of Energy supervisory, project management, and administrative staff. Technical training and basic mathematics are assumed. The notes are designed for a two-day course, taught by two lecturers. Video tapes may be used at the options of the instructors. The notes provide all the materials that are necessary but outside reading will assist in the fullest understanding. The course begins with a nuclear physics overview. The reader is led from the macroscopic world into the microscopic world of atoms and the elementary particles that constitute atoms. The particles, their masses and sizes and properties associated with radioactive decay and fission are introduced along with Einstein's mass-energy equivalence. Radioactive decay, nuclear reactions, radiation penetration, shielding and health-effects are discussed to understand protection in case of a criticality accident. Fission, the fission products, particles and energy released are presented to appreciate the dangers of criticality. Nuclear cross sections are introduced to understand the effectiveness of slow neutrons to produce fission. Chain reactors are presented as an economy; effective use of the neutrons from fission leads to more fission resulting in a power reactor or a criticality excursion. The six-factor formula is presented for managing the neutron budget. This leads to concepts of material and geometric buckling which are used in simple calculations to assure safety from criticality. Experimental measurements and computer code calculations of criticality are discussed. To emphasize the reality, historical criticality accidents are presented in a table with major ones discussed to provide lessons-learned. Finally, standards, NRC guides and regulations, and DOE orders relating to criticality protection are presented.

  14. Latest News | Critical Materials Institute

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

    News News releases CMI in the news News archive CMI social media Latest News News about CMI: Critical Materials Institute, Oddello Industries pursue recovery of rare-earth magnets from used hard drives, August 16, 2016 Solar panels power materials exhibit at Geology Museum, August 2, 2016 New alloy promises to boost rare earth production while improving energy efficiency of engines, June 3, 2016 Critical Materials Institute gains ten industrial and research affiliates, April 11, 2016 On

  15. UTILITY ADVANCED TURBINE SYSTEMS (ATS) TECHNOLOGY READINESS TESTING

    SciTech Connect (OSTI)

    Unknown

    1999-04-01

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the U.S. Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed, including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer conflation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially by GE. This change has resulted from DOE's request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include full speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. The objective of this task is to design 7H and 9H compressor rotor and stator structures with the goal of achieving high efficiency at lower cost and greater durability by applying proven GE Power Systems (GEPS) heavy-duty use design practices. The designs will be based on the GE Aircraft Engines (GEAE) CF6-80C2 compressor. Transient and steady-state thermo-mechanical stress analyses will be run to ensure compliance with GEPS life standards. Drawings will be prepared for forgings, castings, machining, and instrumentation for full speed, no load (FSNL) tests of the first unit on both 9H and 7H applications.

  16. Transducer for downhole drilling components

    DOE Patents [OSTI]

    Hall, David R; Fox, Joe R

    2006-05-30

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

  17. NNSA lab stops bad guys from weaseling into critical infrastructure |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) lab stops bad guys from weaseling into critical infrastructure Tuesday, March 15, 2016 - 11:39am Sandia's John Mulder puts the WeaselBoard through its paces on a test apparatus. Weasels are adaptable, active predators known for being aggressive despite their small size, often threatening animals much larger than themselves. WeaselBoard, the latest technology from NNSA for protecting critical infrastructure, is thus aptly named. Charged with

  18. Critical speed measurements in the Tevatron cold compressors

    SciTech Connect (OSTI)

    DeGraff, B.; Bossert, R.; Martinez, A.; Soyars, W.M.; /Fermilab

    2006-01-01

    The Fermilab Tevatron cryogenic system utilizes high-speed centrifugal cold compressors, manufactured by Ishikawajima-Harima Heavy Industries Co. Ltd. (IHI), for high energy operations. Nominal operating range for these compressors is 43,000 to 85,000 rpm. Past foil bearing failures prompted investigation to determine if critical speeds for operating compressors fall within operating range. Data acquisition hardware and software settings will be discussed for measuring liftoff, first critical and second critical speeds. Several tests provided comparisons between an optical displacement probe and accelerometer measurements. Vibration data and analysis of the 20 Tevatron ring cold compressors will be presented.

  19. Flexibility in Testing Configurations

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

    in Testing Configurations PSEL's infrastructure allows researchers to address critical issues of PV reliability and power availability. The lab offers four different load configuration capabilities, combining various levels of system amps, volts, and watts, and both indoor and outdoor testing and calibration facilities where laboratory-controlled experiments can be conducted with a wide variety of realistic PV systems scenarios. Expertise, Knowledge, & Partnerships PSEL's systems-level

  20. Commercial Off-the-Shelf (COTS) Components and Enterprise Component Information System (eCIS)

    SciTech Connect (OSTI)

    John Minihan; Ed Schmidt; Greg Enserro; Melissa Thompson

    2008-06-30

    The purpose of the project was to develop the processes for using commercial off-the-shelf (COTS) parts for WR production and to put in place a system for implementing the data management tools required to disseminate, store, track procurement, and qualify vendors. Much of the effort was devoted to determining if the use of COTS parts was possible. A basic question: How does the Nuclear Weapons Complex (NWC) begin to use COTS in the weapon Stockpile Life Extension Programs with high reliability, affordability, while managing risk at acceptable levels? In FY00, it was determined that a certain weapon refurbishment program could not be accomplished without the use of COTS components. The elements driving the use of COTS components included decreased cost, greater availability, and shorter delivery time. Key factors that required implementation included identifying the best suppliers and components, defining life cycles and predictions of obsolescence, testing the feasibility of using COTS components with a test contractor to ensure capability, as well as quality and reliability, and implementing the data management tools required to disseminate, store, track procurement, and qualify vendors. The primary effort of this project then was to concentrate on the risks involved in the use of COTS and address the issues of part and vendor selection, procurement and acceptance processes, and qualification of the parts via part and sample testing. The Enterprise Component Information System (eCIS) was used to manage the information generated by the COTS process. eCIS is a common interface for both the design and production of NWC components and systems integrating information between SNL National Laboratory (SNL) and the Kansas City Plant (KCP). The implementation of COTS components utilizes eCIS from part selection through qualification release. All part related data is linked across an unclassified network for access by both SNL and KCP personnel. The system includes not

  1. Large Component Removal/Disposal

    SciTech Connect (OSTI)

    Wheeler, D. M.

    2002-02-27

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

  2. OPSAID Initial Design and Testing Report.

    SciTech Connect (OSTI)

    Hurd, Steven A.; Stamp, Jason Edwin; Chavez, Adrian R.

    2007-11-01

    Process Control System (PCS) security is critical to our national security. Yet, there are a number of technological, economic, and educational impediments to PCS owners implementing effective security on their systems. OPSAID (Open PCS Security Architecture for Interoperable Design), a project sponsored by the US Department of Energy's Office of Electricity Delivery and Reliability, aims to address this issue through developing and testing an open source architecture for PCS security. Sandia National Laboratories, along with a team of PCS vendors and owners, have developed and tested this PCS security architecture. This report describes their progress to date.2 AcknowledgementsThe authors acknowledge and thank their colleagues for their assistance with the OPSAID project.Sandia National Laboratories: Alex Berry, Charles Perine, Regis Cassidy, Bryan Richardson, Laurence PhillipsTeumim Technical, LLC: Dave TeumimIn addition, the authors are greatly indebted to the invaluable help of the members of the OPSAID Core Team. Their assistance has been critical to the success and industry acceptance of the OPSAID project.Schweitzer Engineering Laboratory: Rhett Smith, Ryan Bradetich, Dennis GammelTelTone: Ori Artman Entergy: Dave Norton, Leonard Chamberlin, Mark AllenThe authors would like to acknowledge that the work that produced the results presented in this paper was funded by the U.S. Department of Energy/Office of Electricity Delivery and Energy Reliability (DOE/OE) as part of the National SCADA Test Bed (NSTB) Program. Executive SummaryProcess control systems (PCS) are very important for critical infrastructure and manufacturing operations, yet cyber security technology in PCS is generally poor. The OPSAID (Open PCS (Process Control System) Security Architecture for Interoperable Design) program is intended to address these security shortcomings by accelerating the availability and deployment of comprehensive security technology for PCS, both for existing PCS and

  3. Kauai Test Facility

    SciTech Connect (OSTI)

    Hay, R.G.

    1982-01-01

    The Kauai Test Facility (KTF) is a Department of Energy rocket launch facility operated by Sandia National Laboratories. Originally it was constructed in support of the high altitude atmospheric nuclear test phase of operation Dominic in the early 1960's. Later, the facility went through extensive improvement and modernization to become an integral part of the Safeguard C readiness to resume nuclear testing program. Since its inception and build up, in the decade of the sixties and the subsequent upgrades of the seventies, range test activities have shifted from full scale test to emphasis on research and development of materials and components, and to making high altitude scientific measurements. Primarily, the facility is intended to be utilized in support of development programs at the DOE weapons laboratories, however, other organizations may make use of the facility on a non-interface basis. The physical components at KTF and their operation are described.

  4. Seismic ruggedness of aged electrical components: Final report (Phase 2)

    SciTech Connect (OSTI)

    Gleason, J.F.

    1987-01-01

    Seismic tests on new and aged components have shown that, for many types of commonly used nuclear plant electrical components, deterioration due to aging does not significantly affect the ability of the components to function during and after a seismic event. This was demonstrated for capacitors, circuit breakers, contactors (motor starters), control station assemblies, electronic alarms, electronics, fuses, fuse blocks, inductors, meters, motors, pressure transmitters, power supplies, relays, RTDs, solenoid valves, terminal blocks, time delay relays, transformers and switches. A few switch types (limit, pressure and rotary) were observed to be more prone to contact chatter in an aged condition than in an unaged condition. However, the ability of these devices to switch during and after shaking was not affected by aging. These results can be referenced to eliminate the cost of aging prior to seismic qualification testing for many types of electrical components.

  5. Utility advanced turbine systems (ATS) technology readiness testing. Technical progress report, January 1--March 31, 1998

    SciTech Connect (OSTI)

    1998-08-01

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially by GE. This change has resulted from DOE`s request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include full speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. This report summarizes work accomplished in 1Q98.

  6. UTILITY ADVANCED TURBINE SYSTEMS (ATS) TECHNOLOGY READINESS TESTING: PHASE 3R

    SciTech Connect (OSTI)

    1999-09-01

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the US Department of Energy (DOE) is the development of the GE 7H and 9H combined cycle power systems. The major effort will be expended on detail design. Validation of critical components and technologies will be performed, including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially by GE. This change has resulted from DOE's request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include full speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown. This report summarizes work accomplished in 2Q99.

  7. UTILITY ADVANCED TURBINE SYSTEMS (ATS) TECHNOLOGY READINESS TESTING

    SciTech Connect (OSTI)

    Unknown

    1999-10-01

    The overall objective of the Advanced Turbine System (ATS) Phase 3 Cooperative Agreement between GE and the U.S. Department of Energy (DOE) is the development of a highly efficient, environmentally superior, and cost-competitive utility ATS for base-load utility-scale power generation, the GE 7H (60 Hz) combined cycle power system, and related 9H (50 Hz) common technology. The major effort will be expended on detail design. Validation of critical components and technologies will be performed, including: hot gas path component testing, sub-scale compressor testing, steam purity test trials, and rotational heat transfer confirmation testing. Processes will be developed to support the manufacture of the first system, which was to have been sited and operated in Phase 4 but will now be sited and operated commercially by GE. This change has resulted from DOE's request to GE for deletion of Phase 4 in favor of a restructured Phase 3 (as Phase 3R) to include full speed, no load (FSNL) testing of the 7H gas turbine. Technology enhancements that are not required for the first machine design but will be critical for future ATS advances in performance, reliability, and costs will be initiated. Long-term tests of materials to confirm design life predictions will continue. A schematic of the GE H machine is shown in Figure 1-1. Information specifically related to 9H production is presented for continuity in H program reporting, but lies outside the ATS program. This report summarizes work accomplished from 4Q98 through 3Q99. The most significant accomplishments are listed.

  8. PRECLOSURE CRITICALITY ANALYSIS PROCESS REPORT

    SciTech Connect (OSTI)

    A.E. Danise

    2004-10-25

    This report describes a process for performing preclosure criticality analyses for a repository at Yucca Mountain, Nevada. These analyses will be performed from the time of receipt of fissile material until permanent closure of the repository (preclosure period). The process describes how criticality safety analyses will be performed for various configurations of waste in or out of waste packages that could occur during preclosure as a result of normal operations or event sequences. The criticality safety analysis considers those event sequences resulting in unanticipated moderation, loss of neutron absorber, geometric changes, or administrative errors in waste form placement (loading) of the waste package. The report proposes a criticality analyses process for preclosure to allow a consistent transition from preclosure to postclosure, thereby possibly reducing potential cost increases and delays in licensing of Yucca Mountain. The proposed approach provides the advantage of using a parallel regulatory framework for evaluation of preclosure and postclosure performance and is consistent with the U.S. Nuclear Regulatory Commission's approach of supporting risk-informed, performance-based regulation for fuel cycle facilities, ''Yucca Mountain Review Plan, Final Report'', and 10 CFR Part 63. The criticality-related criteria for ensuring subcriticality are also described as well as which guidance documents will be utilized. Preclosure operations and facilities have significant similarities to existing facilities and operations currently regulated by the U.S. Nuclear Regulatory Commission; therefore, the design approach for preclosure criticality safety will be dictated by existing regulatory requirements while using a risk-informed approach with burnup credit for in-package operations.

  9. Component Modeling Approach Software Tool

    SciTech Connect (OSTI)

    2010-08-23

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

  10. Nuclear component horizontal seismic restraint

    DOE Patents [OSTI]

    Snyder, Glenn J.

    1988-01-01

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