Sample records for water components test

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

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2010-05-05T23:59:59.000Z

    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 experienced cladding failures as operational capabilities of the different designs were being established. In addition, numerous spills of heavy water occurred within the facility. Currently, radiation and radioactive contamination levels are low within HWCTR with most of the radioactivity contained within the reactor vessel. There are no known insults to the environment, however with the increasing deterioration of the facility, the possibility exists that contamination could spread outside the facility if it is not decommissioned. An interior panoramic view of the ground floor elevation taken in August 2009 is shown in Figure 2. The foreground shows the transfer coffin followed by the reactor vessel and control rod drive platform in the center. Behind the reactor vessel is the fuel pool. Above the ground level are the polar crane and the emergency deluge tank at the top of the dome. Note the considerable rust and degradation of the components and the interior of the containment building. Alternative studies have concluded that the most environmentally safe, cost effective option for final decommissioning is to remove the reactor vessel, steam generators, and all equipment above grade including the dome. Characterization studies along with transport models have concluded that the remaining below grade equipment that is left in place including the transfer coffin will not contribute any significant contamination to the environment in the future. The below grade space will be grouted in place. A concrete cover will be placed over the remaining footprint and the groundwater will be monitored for an indefinite period to ensure compliance with environmental regulations. The schedule for completion of decommissioning is late FY2011. This paper describes the concepts planned in order to remove the major components including the dome, the reactor vessel (RV), the two steam generators (SG), and relocating the transfer coffin (TC).

  2. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2011-10-13T23:59:59.000Z

    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 including the dome was removed, a concrete cover was to be placed over the remaining footprint and the groundwater monitored for an indefinite period to ensure compliance with environmental regulations.

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

    SciTech Connect (OSTI)

    Vinson, Dennis

    2010-06-01T23:59:59.000Z

    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.

  4. Durability testing of medium speed diesel engine components designed for operating on coal/water slurry fuel

    SciTech Connect (OSTI)

    McDowell, R.E.; Giammarise, A.W.; Johnson, R.N.

    1994-04-01T23:59:59.000Z

    Over 200 operating cylinder hours were run on critical wearing engine parts. The main components tested included cylinder liners, piston rings, and fuel injector nozzles for coal/water slurry fueled operation. The liners had no visible indication of scoring nor major wear steps found on their tungsten carbide coating. While the tungsten carbide coating on the rings showed good wear resistance, some visual evidence suggests adhesive wear mode was present. Tungsten carbide coated rings running against tungsten carbide coated liners in GE 7FDL engines exhibit wear rates which suggest an approximate 500 to 750 hour life. Injector nozzle orifice materials evaluated were diamond compacts, chemical vapor deposited diamond tubes, and thermally stabilized diamond. Based upon a total of 500 cylinder hours of engine operation (including single-cylinder combustion tests), diamond compact was determined to be the preferred orifice material.

  5. Analysis of removal alternatives for the Heavy Water Components Test Reactor at the Savannah River Site. Revision 1

    SciTech Connect (OSTI)

    Owen, M.B.

    1997-04-01T23:59:59.000Z

    This engineering study evaluates different alternatives for decontamination and decommissioning of the Heavy Water Components Test Reactor (HWCTR). Cooled and moderated with pressurized heavy water, this uranium-fueled nuclear reactor was designed to test fuel assemblies for heavy water power reactors. It was operated for this purpose from march of 1962 until December of 1964. Four alternatives studied in detail include: (1) dismantlement, in which all radioactive and hazardous contaminants would be removed, the containment dome dismantled and the property restored to a condition similar to its original preconstruction state; (2) partial dismantlement and interim safe storage, where radioactive equipment except for the reactor vessel and steam generators would be removed, along with hazardous materials, and the building sealed with remote monitoring equipment in place to permit limited inspections at five-year intervals; (3) conversion for beneficial reuse, in which most radioactive equipment and hazardous materials would be removed and the containment building converted to another use such as a storage facility for radioactive materials, and (4) entombment, which involves removing hazardous materials, filling the below-ground structure with concrete, removing the containment dome and pouring a concrete cap on the tomb. Also considered was safe storage, but this approach, which has, in effect, been followed for the past 30 years, did not warrant detailed evaluation. The four other alternatives were evaluate, taking into account factors such as potential effects on the environment, risks, effectiveness, ease of implementation and cost. The preferred alternative was determined to be dismantlement. This approach is recommended because it ranks highest in the comparative analysis, would serve as the best prototype for the site reactor decommissioning program and would be most compatible with site property reuse plans for the future.

  6. Component evaluation testing and analysis algorithms.

    SciTech Connect (OSTI)

    Hart, Darren M.; Merchant, Bion John

    2011-10-01T23:59:59.000Z

    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.

  7. Abrasion Testing of Critical Components of Hydrokinetic Devices

    SciTech Connect (OSTI)

    Worthington, Monty [ORPC Alaska] [ORPC Alaska; Ali, Muhammad [Ohio University] [Ohio University; Ravens, Tom [University of Alaska Anchorage] [University of Alaska Anchorage

    2013-12-06T23:59:59.000Z

    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.

  8. DOE Cell Component Accelerated Stress Test Protocols for PEM...

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

    Cell Component Accelerated Stress Test Protocols for PEM Fuel Cells DOE Cell Component Accelerated Stress Test Protocols for PEM Fuel Cells This document describes test protocols...

  9. Cell Component Accelerated Stress Test Protocols for PEM Fuel...

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

    Cell Component Accelerated Stress Test Protocols for PEM Fuel Cells Cell Component Accelerated Stress Test Protocols for PEM Fuel Cells Accelerated Stress Test Protocols for PEM...

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

    Office of Science (SC) Website

    Heavy-ion Accelerators for Testing Microelectronic Components at LBNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of...

  11. DOE Cell Component Accelerated Stress Test Protocols for PEM...

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

    CELL COMPONENT ACCELERATED STRESS TEST PROTOCOLS FOR PEM FUEL CELLS (Electrocatalysts, Supports, Membranes, and Membrane Electrode Assemblies) March 2007 Fuel cells, especially for...

  12. Cell Component Accelerated Stress Test Protocols for PEM Fuel...

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

    USCAR FUEL CELL TECH TEAM CELL COMPONENT ACCELERATED STRESS TEST PROTOCOLS FOR PEM FUEL CELLS (Electrocatalysts, Supports, Membranes, and Membrane Electrode Assemblies) Revised May...

  13. Quality Assurance Program Application for the Component Test Capability

    SciTech Connect (OSTI)

    Stephanin L. Austad

    2009-06-01T23:59:59.000Z

    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.

  14. 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

    2009-09-01T23:59:59.000Z

    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.

  15. Application of reliability analysis method to fusion component testing

    SciTech Connect (OSTI)

    Ying, A.Y.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States)

    1994-12-31T23:59:59.000Z

    The term reliability here implies that a component satisfies a set of performance criteria while under specified conditions of use over a specified period of time. For fusion nuclear technology, the reliability goal to be pursued is the development of a mean time between failures (MTBF) for a component which is longer than its lifetime goal. While the component lifetime is mainly determined by the fluence limitation (i.e., damage level) which leads to performance degradation or failure, the MTBF represents an arithmetic average life of all units in a population. One method of assessing the reliability goal involves determining component availability needs to meet the goal plant availability, defining a test-analyze-fix development program to improve component reliability, and quantifying both test times and the number of test articles that would be required to ensure that a specified target MTBF is met. Statistically, constant failure rates and exponential life distributions are assumed for analyses and blanket component development is used as an example. However, as data are collected the probability distribution of the parameter of interest can be updated in a Bayesian fashion. The nuclear component testing program will be structured such that reliability requirements for DEMO can be achieved. The program shall not exclude the practice of a good design (such as reducing the complexity of the system to the minimum essential for the required operation), the execution of high quality manufacturing and inspection processes, and the implication of quality assurance and control for component development. In fact, the assurance of a high quality testing/development program is essential so that there is no question left for reliability.

  16. advanced components test: Topics by E-print Network

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

    components test First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 ADVANCES IN TEXTURE ANALYSIS: ENERGY...

  17. Evaluation of Integrated High Temperature Component Testing Needs

    SciTech Connect (OSTI)

    Rafael Soto; David Duncan; Vincent Tonc

    2009-05-01T23:59:59.000Z

    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.

  18. CEBAF UPGRADE CRYOMODULE COMPONENT TESTING IN THE HORIZONTAL TEST BED (HTB)*

    E-Print Network [OSTI]

    CEBAF UPGRADE CRYOMODULE COMPONENT TESTING IN THE HORIZONTAL TEST BED (HTB)* I. E. Campisi , B The planned upgrade of the CEBAF electron accelerator includes the development of an improved cryomodule. Several components differ substantially from the original CEBAF cryomodule; these include: the new 7-cell

  19. Feasibility of Using Measurements of Internal Components of Tankless Water Heaters for Field Monitoring of Energy and Water Use

    E-Print Network [OSTI]

    Lutz, Jim

    2008-01-01T23:59:59.000Z

    Test Procedures for Water Heaters; Final Rule," FederalTesting of Tankless Gas Water Heater Performance," DavisInc. , "T-K2 Instantaneous Water Heater Installation Manual

  20. Heavy Water Test Reactor Dome Removal

    SciTech Connect (OSTI)

    None

    2011-01-01T23:59:59.000Z

    A high speed look at the removal of the Heavy Water Test Reactor Dome Removal. A project sponsored by the Recovery Act on the Savannah River Site.

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

    SciTech Connect (OSTI)

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

    2013-08-01T23:59:59.000Z

    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 the walls containing the nano-PCM wallboards were performed to determine their actual impact on wall-generated heating and cooling loads. The models were first validated using field data, and then used to perform annual simulations using Typical Meteorological Year (TMY) weather data. This article presents the measured performance and numerical analysis to evaluate the energy-saving potential of the nano-PCM-enhanced building components.

  2. Single Component Sorption-Desorption Test Experimental Design Approach Discussions

    SciTech Connect (OSTI)

    Phil WInston

    2011-09-01T23:59:59.000Z

    A task was identified within the fission-product-transport work package to develop a path forward for doing testing to determine behavior of volatile fission products behavior and to engage members of the NGNP community to advise and dissent on the approach. The following document is a summary of the discussions and the specific approaches suggested for components of the testing. Included in the summary isare the minutes of the conference call that was held with INL and external interested parties to elicit comments on the approaches brought forward by the INL participants. The conclusion was that an initial non-radioactive, single component test will be useful to establish the limits of currently available chemical detection methods, and to evaluated source-dispersion uniformity. In parallel, development of a real-time low-concentration monitoring method is believed to be useful in detecting rapid dispersion as well as desorption phenomena. Ultimately, the test cycle is expected to progress to the use of radio-traced species, simply because this method will allow the lowest possible detection limits. The consensus of the conference call was that there is no need for an in-core test because the duct and heat exchanger surfaces that will be the sorption target will be outside the main neutron flux and will not be affected by irradiation. Participants in the discussion and contributors to the INL approach were Jeffrey Berg, Pattrick Calderoni, Gary Groenewold, Paul Humrickhouse, Brad Merrill, and Phil Winston. Participants from outside the INL included David Hanson of General Atomics, Todd Allen, Tyler Gerczak, and Izabela Szlufarska of the University of Wisconsin, Gary Was, of the University of Michigan, Sudarshan Loyalka and Tushar Ghosh of the University of Missouri, and Robert Morris of Oak Ridge National Laboratory.

  3. Report on fuel pool water loss tests

    SciTech Connect (OSTI)

    Zalenski, R.F. [West Valley Nuclear Services Co., West Valley, NY (United States)

    1995-12-31T23:59:59.000Z

    To resolve potential concerns on the integrity of the fuel storage pool at the West Valley Demonstration Project (WVDP), a highly accurate testing technique was developed to quantify water losses from the pool. The fuel pool is an unlined, single wall, reinforced concrete structure containing approximately 818,000 gallons of water. Since an initial test indicated that water losses could possibly be attributed solely to evaporation, a cover was suspended and sealed over the pool to block evaporation losses. High accuracy water level and temperature instrumentation was procured and installed. The conclusions of this report indicate that unaccounted-for water losses from the pool are insignificant and there is no detectable leakage within the range of test accuracy.

  4. CLSM bleed water reduction test results

    SciTech Connect (OSTI)

    Langton, C.A. [Westinghouse Savannah River Company, Aiken, SC (United States); Rajendran, N. [Bechtel Savannah River Company, Aiken, SC (United States)

    1997-04-21T23:59:59.000Z

    Previous testing by BSRI/SRTC/Raytheon indicated that the CLSM specified for the Tank 20 closure generates about 6 gallons (23 liters) of bleed water per cubic yard of material (0.76 m3).1 This amount to about 10 percent of the total mixing water. HLWE requested that the CLSM mix be optimized to reduce bleed water while maintaining flow. Elimination of bleed water from the CLSM mix specified for High-Level Waste Tank Closure will result in waste minimization, time savings and cost savings. Over thirty mixes were formulated and evaluated at the on-site Raytheon Test Laboratory. Improved low bleed water CLSM mixes were identified. Results are documented in this report.

  5. Concentrator E-F11 water test

    SciTech Connect (OSTI)

    Ethington, P.R.

    1994-02-25T23:59:59.000Z

    This document is the Process Test Report for performing operation testing with water of the modified E-F11 concentrator in PUREX on water. The test was performed to determine the effects of the following concentrator modifications; routing concentrator off-gasses via the PUREX air tunnel to the main stack, blanking of condenser cooling water, blanking of process condensate route to a crib, restricting flow to steam tube bundles, and routing of steam condensate to TK-F12. The test was successful. Concentrator boil-off rates of 6--7 gpm were achieved while the overheads exited the PUREX plant in vapor form. With minor recommended modifications, this process is recommended for use in processing PUREX deactivation flush solutions and other miscellaneous wastes accumulated during the completion of the deactivation project.

  6. Neogene overflow of Northern Component Water at the Greenland-Scotland Ridge

    E-Print Network [OSTI]

    Samworth, Richard

    Neogene overflow of Northern Component Water at the Greenland-Scotland Ridge H. R. Poore Department counterpart Northern Component Water (NCW), across the Greenland-Scotland Ridge (GSR) is thought to have,280 words, 12 figures, 3 tables. Keywords: Northern Component Water; Greenland-Scotland Ridge; Iceland

  7. Trip Report-Produced-Water Field Testing

    SciTech Connect (OSTI)

    Sullivan, Enid J. [Los Alamos National Laboratory

    2012-05-25T23:59:59.000Z

    Los Alamos National Laboratory (LANL) conducted field testing of a produced-water pretreatment apparatus with assistance from faculty at the Texas A&M University (TAMU) protein separation sciences laboratory located on the TAMU main campus. The following report details all of the logistics surrounding the testing. The purpose of the test was to use a new, commercially-available filter media housing containing modified zeolite (surfactant-modified zeolite or SMZ) porous medium for use in pretreatment of oil and gas produced water (PW) and frac-flowback waters. The SMZ was tested previously in October, 2010 in a lab-constructed configuration ('old multicolumn system'), and performed well for removal of benzene, toluene, ethylbenzene, and xylenes (BTEX) from PW. However, a less-expensive, modular configuration is needed for field use. A modular system will allow the field operator to add or subtract SMZ filters as needed to accommodate site specific conditions, and to swap out used filters easily in a multi-unit system. This test demonstrated the use of a commercial filter housing with a simple flow modification and packed with SMZ for removing BTEX from a PW source in College Station, Texas. The system will be tested in June 2012 at a field site in Pennsylvania for treating frac-flowback waters. The goals of this test are: (1) to determine sorption efficiency of BTEX in the new configuration; and (2) to observe the range of flow rates, backpressures, and total volume treated at a given flow rate.

  8. Moving Bed, Granular Bed Filter Development Program: Option 1, Component Test Facility. Task 3, Test plan

    SciTech Connect (OSTI)

    Haas, J.C.; Purdhomme, J.W.; Wilson, K.B.

    1994-04-01T23:59:59.000Z

    In the base contract, Combustion Power Co. developed commercial designs for a moving granular-bed filter (GBF). The proposed filter is similar to previous designs in terms of its shape and method of filtration. The commercial designs have scaled the filter from a 5 ft diameter to as large as a 20 ft diameter filter. In Task 2 of the Moving Bed-Granular Filter Development Program, all technical concerns related to the further development of the filter are identified. These issues are discussed in a Topical Report which has been issued as part of Task 2. Nineteen issues are identified in this report. Along with a discussion of these issues are the planned approaches for resolving each of these issues. These issues will be resolved in either a cold flow component test facility or in pilot scale testing at DOE`s Power System Development Facility (PSDF) located at Southem Company Services` Wilsonville facility. Task 3 presents a test plan for resolving those issues which can be addressed in component test facilities. The issues identified in Task 2 which will be addressed in the component test facilities are: GBF scale-up; effect of filter cone angle and sidewall materials on medium flow and ash segregation; maximum gas filtration rate; lift pipe wear; GBF media issues; mechanical design of the gas inlet duct; and filter pressure drop. This document describes a test program to address these issues, with testing to be performed at Combustion Power Company`s facility in Belmont, California.

  9. A component test facility based on the spherical tokamak

    SciTech Connect (OSTI)

    Peng, Yueng Kay Martin [ORNL; Fogarty, P. J. [Oak Ridge National Laboratory (ORNL); Burgess, Thomas W [ORNL; Strickler, Dennis J [ORNL; Nelson, Brad E [ORNL; Tsai, C. C. [Oak Ridge National Laboratory (ORNL)

    2005-01-01T23:59:59.000Z

    Recent experiments (Synakowski et al 2004 Nucl. Fusion 43 1648, Lloyd et al 2004 Plasma Phys. Control. Fusion 46 13477) on the Spherical Tokamak (or Spherical Torus, ST) (Peng 2000 Phys. Plasmas 7 1681) have discovered robust plasma conditions, easing shaping, stability limits, energy confinement, self-driven current and sustainment. This progress has encouraged an update of the plasma conditions and engineering of a Component Test Facility (CTF), (Cheng 1998 Fusion Eng. Des. 38 219) which is a very valuable step in the development of practical fusion energy. The testing conditions in a CTF are characterized by high fusion neutron fluxes Gamma(n) approximate to 8.8 x 10(13) n s(-1) cm(-2) ('wall loading' W-L approximate to 2 MW m(-2)), over size-scale > 10(5) cm(2) and depth-scale > 50 cm, delivering > 3 accumulated displacement per atom per year ('neutron fluence' > 0.3 MW yr(-1) m(-2)) (Abdou et al 1999 Fusion Technol. 29 1). Such conditions are estimated to be achievable in a CTF with R-0 = 1.2 m, A = 1.5, elongation similar to 3, I-p similar to 12 MA, B-T similar to 2.5 T, producing a driven fusion burn using 47 MW of combined neutral beam and RF heating power. A design concept that allows straight-line access via remote handling to all activated fusion core components is developed and presented. The ST CTF will test the lifetime of single-turn, copper alloy centre leg for the toroidal field coil without an induction solenoid and neutron shielding and require physics data on solenoid-free plasma current initiation, ramp-up to and sustainment at multiple megaampere level. A systems code that combines the key required plasma and engineering science conditions of CTF has been prepared and utilized as part of this study. The results show high potential for a family of relatively low cost CTF devices to suit a range of fusion engineering and technology test missions.

  10. Retrofitting Combined Space and Water Heating Systems: Laboratory Tests

    SciTech Connect (OSTI)

    Schoenbauer, B.; Bohac, D.; Huelman, P.; Olson, R.; Hewitt, M.

    2012-10-01T23:59:59.000Z

    Better insulated and tighter homes can often use a single heating plant for both space and domestic water heating. These systems, called dual integrated appliances (DIA) or combination systems, can operate at high efficiency and eliminate combustion safety issues associated by using a condensing, sealed combustion heating plant. Funds were received to install 400 DIAs in Minnesota low-income homes. The NorthernSTAR DIA laboratory was created to identify proper system components, designs, operating parameters, and installation procedures to assure high efficiency of field installed systems. Tests verified that heating loads up to 57,000 Btu/hr can be achieved with acceptable return water temperatures and supply air temperatures.

  11. E-Print Network 3.0 - advanced components test facility Sample...

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

    of components for the new de- signs being tested underground at the Nevada Test Site. Small- scale recycling... Alam- os. Finally there was a modest capability to design,...

  12. Isotropic and Nonisotropic Components of Earthquakes and Nuclear Explosions on the Lop Nor Test Site, China

    E-Print Network [OSTI]

    Ritzwolle, Mike

    Isotropic and Nonisotropic Components of Earthquakes and Nuclear Explosions on the Lop Nor Test and 1996 following events (seven nuclear explosions, three earthquakes) that occurred on the Lop Nor test Abstract Ð We test the hypothesis that the existence of an observable non-zero isotropic component

  13. Identication of Major Water-Soluble Fluorescent Components of Some

    E-Print Network [OSTI]

    Myrick, Michael Lenn

    . MUROSKI and M. L. MYRICK* Department of Chemistry and Biochemistry, University of South Carolina, 630 the ultraviolet (UV) ¯uorescence of water after exposure to gasoline, diesel fuel and crude oil are pre- sented- naphthalene and methylstyrene are the major ¯uorescent species in water following exposure to gasoline

  14. COTS FPGA/SRAM Irradiations Using a Dedicated Testing Infrastructure for Characterization of Large Component Batches

    E-Print Network [OSTI]

    Slawosz, Uznanski; Johannes, Walter; Andrea, Vilar-Villanueva

    2015-01-01T23:59:59.000Z

    This paper introduces a new testing platform for irradiation of large batches of COTS FPGA and SRAMs. The main objective is measurement of component radiation response and assessment of component-to-component variability within one batch. The first validation and test results using the testing platform are presented for 150nm TFT SRAM (Renesas) and different sizes of the 130nm ProASIC3 FPGA (Microsemi).

  15. Initial Component Testing for a Germanium Array Cryostat

    SciTech Connect (OSTI)

    Keillor, Martin E.; Aalseth, Craig E.; Day, Anthony R.; Fast, James E.; Hoppe, Eric W.; Hyronimus, Brian J.; Hossbach, Todd W.; Seifert, Allen

    2009-07-25T23:59:59.000Z

    This report describes progress on the construction of two ultra-low-background cryostats that are part of the NA-22 funded “Radionuclide Laboratories” (RN Labs) project. Each cryostat will house seven high-purity germanium crystals (HPGe). These cryostats are being built from a limited set of materials that are known to have very low levels of radioactive impurities. The RN Labs instrument is designed to take advantage of low background performance, high detection efficiency, and ?-? coincidence signatures to provide unprecedented gamma spectroscopy sensitivity. The project is focused on improving gamma analysis capabilities for nuclear detonation detection (NDD) applications. The instrument also has the potential for basic nuclear physics research. Section 1 provides the background for the project. Section 2 discusses germanium crystal acceptance testing. Design problems were found after the first delivery of new detectors from the vendor, Canberra Semiconductors. The first four crystals were returned for repair, resulting in a delay in crystal procurement. Section 3 provides an update on copper electroforming. In general, electroforming parts for RN Labs has proceeded smoothly, but there have been recent problems in electroforming three large copper parts necessary for the project. Section 4 describes the first round of testing for the instrument: anti-cosmic scintillator testing, electronics testing, and initial vacuum testing. Section 5 concludes with an overall description of the state of the project and challenges that remain.

  16. Warm Water Oxidation Verification - Scoping and Stirred Reactor Tests

    SciTech Connect (OSTI)

    Braley, Jenifer C.; Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.

    2011-06-15T23:59:59.000Z

    Scoping tests to evaluate the effects of agitation and pH adjustment on simulant sludge agglomeration and uranium metal oxidation at {approx}95 C were performed under Test Instructions(a,b) and as per sections 5.1 and 5.2 of this Test Plan prepared by AREVA. (c) The thermal testing occurred during the week of October 4-9, 2010. The results are reported here. For this testing, two uranium-containing simulant sludge types were evaluated: (1) a full uranium-containing K West (KW) container sludge simulant consisting of nine predominant sludge components; (2) a 50:50 uranium-mole basis mixture of uraninite [U(IV)] and metaschoepite [U(VI)]. This scoping study was conducted in support of the Sludge Treatment Project (STP) Phase 2 technology evaluation for the treatment and packaging of K-Basin sludge. The STP is managed by CH2M Hill Plateau Remediation Company (CHPRC) for the U.S. Department of Energy. Warm water ({approx}95 C) oxidation of sludge, followed by immobilization, has been proposed by AREVA and is one of the alternative flowsheets being considered to convert uranium metal to UO{sub 2} and eliminate H{sub 2} generation during final sludge disposition. Preliminary assessments of warm water oxidation have been conducted, and several issues have been identified that can best be evaluated through laboratory testing. The scoping evaluation documented here was specifically focused on the issue of the potential formation of high strength sludge agglomerates at the proposed 95 C process operating temperature. Prior hydrothermal tests conducted at 185 C produced significant physiochemical changes to genuine sludge, including the formation of monolithic concretions/agglomerates that exhibited shear strengths in excess of 100 kPa (Delegard et al. 2007).

  17. eCrash: a Framework for Performing Evolutionary Testing on Third-Party Java Components

    E-Print Network [OSTI]

    Fernandez, Thomas

    eCrash: a Framework for Performing Evolutionary Testing on Third-Party Java Components José Carlos fcofdez@unex.es Abstract The focus of this paper is on presenting a tool for generating test data of the instrumented test object. The main objective of this approach is that of evolving a set of test cases

  18. Component failures at pressurized water reactors. Final report

    SciTech Connect (OSTI)

    Reisinger, M.F.

    1980-10-01T23:59:59.000Z

    Objectives of this study were to identify those systems having major impact on safety and availability (i.e. to identify those systems and components whose failures have historically caused the greatest number of challenges to the reactor protective systems and which have resulted in greatest loss of electric generation time). These problems were identified for engineering solutions and recommendations made for areas and programs where research and development should be concentrated. The program was conducted in three major phases: Data Analysis, Engineering Evaluation, Cost Benefit Analysis.

  19. Testing Components of New Community Isopycnal Ocean Circulation Model

    SciTech Connect (OSTI)

    Bryan, Kirk

    2008-05-09T23:59:59.000Z

    The ocean and atmosphere are both governed by the same physical laws and models of the two media have many similarities. However, there are critical differences that call for special methods to provide the best simulation. One of the most important difference is that the ocean is nearly opaque to radiation in the visible and infra-red part of the spectrum. For this reason water mass properties in the ocean are conserved along trajectories for long distances and for long periods of time. For this reason isopycnal coordinate models would seem to have a distinct advantage in simulating ocean circulation. In such a model the coordinate surfaces are aligned with the natural paths of near adiabatic, density conserving flow in the main thermocline. The difficulty with this approach is at the upper and lower boundaries of the ocean, which in general do not coincide with density surfaces. For this reason hybrid coordinate models were proposed by Bleck and Boudra (1981) in which Cartesian coordinates were used near the ocean surface and isopycnal coordinates were used in the main thermocline. This feature is now part of the HICOM model (Bleck, 2002).

  20. Liquid-Water Uptake and Removal in PEM Fuel-Cell Components

    E-Print Network [OSTI]

    Das, Prodip K.

    2013-01-01T23:59:59.000Z

    Uptake and Removal in PEM Fuel-Cell Components Prodip K. DasWater management in PEM fuel cells is critical for optimumof droplet dynamics in PEM fuel-cell gas flow channels has

  1. Comparison of thorium-based fuels with different fissile components in existing boiling water reactors

    E-Print Network [OSTI]

    Demazière, Christophe

    Comparison of thorium-based fuels with different fissile components in existing boiling water, SE-412 96 Göteborg, Sweden Keywords: Thorium BWR Neutronics a b s t r a c t With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Water Reactor) with thorium

  2. 225-kW Dynamometer for Testing Small Wind Turbine Components: Preprint

    SciTech Connect (OSTI)

    Green, J.

    2006-06-01T23:59:59.000Z

    This paper describes NREL's new 225-kW dynamometer facility that is suitable for testing a variety of components and subsystems for small wind turbines and discusses opportunities for industry partnerships with NREL for use of the facility.

  3. Design and testing of components for a low cost laser cutter

    E-Print Network [OSTI]

    Ramos, Joshua D

    2011-01-01T23:59:59.000Z

    The main goal of this thesis is to document the design and testing of various components for use in a low cost laser cutting mechanism for hobbyists and recreational designers. Different electronics were used to assess the ...

  4. USCAR FUEL CELL TECH TEAM CELL COMPONENT ACCELERATED STRESS TEST PROTOCOLS

    E-Print Network [OSTI]

    USCAR FUEL CELL TECH TEAM CELL COMPONENT ACCELERATED STRESS TEST PROTOCOLS FOR PEM FUEL CELLS of polymer electrolyte membrane (PEM) fuel cell components under simulated automotive drive cycle conditions of PEM fuel cells. Corrosion of high-surface area carbon supports poses significant concerns at high

  5. Improving the Water Component of an Agricultural Climate Change Assessment : Issues from the Standpoint of Agricultural Economists

    E-Print Network [OSTI]

    McCarl, Bruce A.

    Improving the Water Component of an Agricultural Climate Change Assessment : Issues from The National Global Climate Change Research Program is supporting appraisals of water and agriculture among assessment. Key Terms; Economics, Climate Change Assessment, Agriculture, Irrigation, Water use tradeoffs

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

    SciTech Connect (OSTI)

    McEntire, B.J. [Norton Co., Northboro, MA (United States). Advanced Ceramics Div.; Willis, R.W.; Southam, R.E. [TRW, Inc., Cleveland, OH (United States)

    1994-10-01T23:59:59.000Z

    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.

  7. Optimum combined test plans for systems and components JAYANT RAJGOPAL, MAINAK MAZUMDAR and SUBBA RAO V. MAJETY

    E-Print Network [OSTI]

    Mazumdar, Mainak

    Optimum combined test plans for systems and components JAYANT RAJGOPAL, MAINAK MAZUMDAR and SUBBA on the reliability of a system could be made on the basis of tests of its constituent components. Prior research in the area of system-based component testing has for the most part addressed the development of plans

  8. Extensive remote handling and conservative plasma conditions to enable fusion nuclear science R&D using a component testing facility

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    nuclear science R&D using a component testing facility Y.K.M. Peng 1), T.W. Burgess 1), A.J. Carroll 1), C. This use aims to test components in an integrated fusion nuclear environment, for the first time@ornl.gov Abstract. The use of a fusion component testing facility to study and establish, during the ITER era

  9. Final report : testing and evaluation for solar hot water reliability.

    SciTech Connect (OSTI)

    Caudell, Thomas P. (University of New Mexico, Albuquerque, NM) [University of New Mexico, Albuquerque, NM; He, Hongbo (University of New Mexico, Albuquerque, NM) [University of New Mexico, Albuquerque, NM; Menicucci, David F. (Building Specialists, Inc., Albuquerque, NM) [Building Specialists, Inc., Albuquerque, NM; Mammoli, Andrea A. (University of New Mexico, Albuquerque, NM) [University of New Mexico, Albuquerque, NM; Burch, Jay (National Renewable Energy Laboratory, Golden CO) [National Renewable Energy Laboratory, Golden CO

    2011-07-01T23:59:59.000Z

    Solar hot water (SHW) systems are being installed by the thousands. Tax credits and utility rebate programs are spurring this burgeoning market. However, the reliability of these systems is virtually unknown. Recent work by Sandia National Laboratories (SNL) has shown that few data exist to quantify the mean time to failure of these systems. However, there is keen interest in developing new techniques to measure SHW reliability, particularly among utilities that use ratepayer money to pay the rebates. This document reports on an effort to develop and test new, simplified techniques to directly measure the state of health of fielded SHW systems. One approach was developed by the National Renewable Energy Laboratory (NREL) and is based on the idea that the performance of the solar storage tank can reliably indicate the operational status of the SHW systems. Another approach, developed by the University of New Mexico (UNM), uses adaptive resonance theory, a type of neural network, to detect and predict failures. This method uses the same sensors that are normally used to control the SHW system. The NREL method uses two additional temperature sensors on the solar tank. The theories, development, application, and testing of both methods are described in the report. Testing was performed on the SHW Reliability Testbed at UNM, a highly instrumented SHW system developed jointly by SNL and UNM. The two methods were tested against a number of simulated failures. The results show that both methods show promise for inclusion in conventional SHW controllers, giving them advanced capability in detecting and predicting component failures.

  10. In-situ parameter estimation for solar domestic hot water heating systems components. Final report, June 1995--May 1996

    SciTech Connect (OSTI)

    Smith, T.R.

    1997-03-01T23:59:59.000Z

    Three different solar domestic hot water systems are being tested at the Colorado State University Solar Energy Applications Laboratory; an unpressurized drain-back system with a load side heat exchanger, an integral collector storage system, and an ultra low flow natural convection heat exchanger system. The systems are fully instrumented to yield data appropriate for in-depth analyses of performance. The level of detail allows the observation of the performance of the total system and the performance of the individual components. This report evaluates the systems based on in-situ experimental data and compares the performances with simulated performances. The verification of the simulations aids in the rating procedure. The whole system performance measurements are also used to analyze the performance of individual components of a solar hot water system and to develop improved component models. The data are analyzed extensively and the parameters needed to characterize the systems fully are developed. Also resulting from this indepth analysis are suggested design improvements wither to the systems or the system components.

  11. Should you have your water tested?

    E-Print Network [OSTI]

    O'Laughlin, Jay

    dissolved solids (TDS), corrosion index, and other parameters depending on proximity to potential sources guests have recurrent incidents of gastrointestinal illness. Household water plumbing contains lead pipes, fittings, or solder joints. You are buying a home and wish to assess the safety and quality of the existing

  12. How to Make Appliance Standards Work: Improving Energy and Water Efficiency Test Procedures

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    Hill. 1996. “Energy test procedures for appliances. ” EnergyWater Efficiency Test Procedures Jim Lutz, Peter Biermayer,Water Efficiency Test Procedures Jim Lutz, Peter Biermayer,

  13. 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. [NASA Marshall Space Flight Center Propulsion Research and Technology Applications Branch/ER24, MSFC, AL 35812 (United States)

    2008-01-21T23:59:59.000Z

    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.

  14. Methods for nondestructive testing of austenitic high-temperature gas-cooled reactor components

    SciTech Connect (OSTI)

    Gobbels, K.; Kapitza, H.

    1984-09-01T23:59:59.000Z

    Safety-relevant components of high-temperature gas-cooled reactor components are mostly fabricated in nickel-based alloys and austenitic materials like Inconel-617, Hastelloy-X, Nimonic-86, or Incoloy-800H. Compared to ferritic steels, these austenitic materials can have a coarse-grained microstructure, especially in weldments and castings. Coarse-grained or elastic anisotropic materials are difficult to inspect with ultrasonics due to strong attenuation, high noise level (scattering, ''grass'' indications), and sound beam distortions (skewing, splitting, and mode conversion). Only few results dealing with the nondestructive testing of nickel-based alloys are known. The problem area, solutions, and first experiences are reported.

  15. Disinfection Procedure for Water Distribution Pipelines Drinking water contamination can be prevented by hydrostatic testing and disinfection of

    E-Print Network [OSTI]

    de Lijser, Peter

    Disinfection Procedure for Water Distribution Pipelines Drinking water contamination can pipeline connections to the system, and respond to requests for drinking water assessments. And, any be prevented by hydrostatic testing and disinfection of potable water distribution pipelines before connecting

  16. Dynamics of the fast component of nano-confined water under electric field

    SciTech Connect (OSTI)

    Omar Diallo, Souleymane [ORNL; Mamontov, Eugene [ORNL; Podlesnyak, Andrey A [ORNL; Ehlers, Georg [ORNL; Wada, Nobuo [Nagoya University, Japan; Inagaki, S [Toyota Central Research and Development Labs. Inc.; Fukushima, Y [Toyota Central Research and Development Labs. Inc.

    2013-01-01T23:59:59.000Z

    We report the diffusion of water molecules confined in the pores of folded silica materials (FSM-12 with average pore diameter of $\\sim$ 16 \\AA), measured by means of quasielastic neutron scattering using the cold neutron chopper spectrometer (CNCS). The goal is to investigate the effect of electric field on the previously observed fast component of nano-confined water. The measurements were taken at temperatures between 220 K and 245 K, and at two electric field values, 0 kV/mm and 2 kV/mm. Similar to the recently observed electric field induced enhancement of the slow translational motion of confined water, there is a an equally important impact of the field on the faster diffusion.

  17. Fusion Nuclear Schience Facility-AT: A Material And Component Testing Device

    SciTech Connect (OSTI)

    Wong, C. P.; Chan, V. S.; Garofalo, A. M.; Stambaugh, Ron; Sawan, M.; Kurtz, Richard J.; Merrill, Brad

    2012-07-01T23:59:59.000Z

    A Fusion Nuclear Science Facility (FNSF) is a necessary complement to ITER, especially in the area of materials and components testing, needed for DEMO design development. FNSF-AT, which takes advantage of advanced tokamak (AT) physics should have neutron wall loading of 1-2 MW/m2, continuous operation for periods of up to two weeks, a duty factor goal of 0.3 per year and an accumulated fluence of 3-6 MW-yr/m2 (~30-60 dpa) in ten years to enable the qualification of structural, blanket and functional materials, components and corresponding ancillary equipment necessary for the design and licensing of a DEMO. Base blankets with a ferritic steel structure and selected tritium blanket materials will be tested and used for the demonstration of tritium sufficiency. Additional test ports at the outboard mid-plane will be reserved for test blankets with advanced designs or exotic materials, and electricity production for integrated high fluence testing in a DT fusion spectrum. FNSF-AT will be designed using conservative implementations of all elements of AT physics to produce 150-300 MW fusion power with modest energy gain (Q<7) in a modest sized normal conducting coil device. It will demonstrate and help to select the DEMO plasma facing, structural, tritium breeding, functional materials and ancillary equipment including diagnostics. It will also demonstrate the necessary tritium fuel cycle, design and cooling of the first wall chamber and divertor components. It will contribute to the knowledge on material qualification, licensing, operational safety and remote maintenance necessary for DEMO design

  18. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.3 Check Upload Integrity

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.3 Check Upload Integrity Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.3 Check Upload Integrity

  19. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.3 Check Upload Integrity

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.3 Check Upload Integrity Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.3 Check Upload Integrity

  20. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.2.2 Download Data Timing

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.2.2 Download Data Timing Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.2.2 Download Data Timing

  1. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.1a Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.1a Watchdog Date: February 13, 2001 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement-0049 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  2. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.2a Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.2a Watchdog Date: February 13, 2001 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.09 Component Test Results Requirement-0019 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  3. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.2.2 Download Data Timing

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.2.2 Download Data Timing Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.2.2 Download Data Timing

  4. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.1b Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.1b Watchdog Date: February 13, 2001 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.09 Component Test Results Requirement-0018 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  5. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.1a Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.1a Watchdog Date: February 13, 2001 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.09 Component Test Results Requirement-0017 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  6. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.1b Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.1b Watchdog Date: February 13, 2001 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement-0050 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  7. Acceptance test procedure for High Pressure Water Jet System

    SciTech Connect (OSTI)

    Crystal, J.B.

    1995-05-30T23:59:59.000Z

    The overall objective of the acceptance test is to demonstrate a combined system. This includes associated tools and equipment necessary to perform cleaning in the 105 K East Basin (KE) for achieving optimum reduction in the level of contamination/dose rate on canisters prior to removal from the KE Basin and subsequent packaging for disposal. Acceptance tests shall include necessary hardware to achieve acceptance of the cleaning phase of canisters. This acceptance test procedure will define the acceptance testing criteria of the high pressure water jet cleaning fixture. The focus of this procedure will be to provide guidelines and instructions to control, evaluate and document the acceptance testing for cleaning effectiveness and method(s) of removing the contaminated surface layer from the canister presently identified in KE Basin. Additionally, the desired result of the acceptance test will be to deliver to K Basins a thoroughly tested and proven system for underwater decontamination and dose reduction. This report discusses the acceptance test procedure for the High Pressure Water Jet.

  8. Design requirements for the supercritical water oxidation test bed

    SciTech Connect (OSTI)

    Svoboda, J.M.; Valentich, D.J.

    1994-05-01T23:59:59.000Z

    This report describes the design requirements for the supercritical water oxidation (SCWO) test bed that will be located at the Idaho National Engineering Laboratory (INEL). The test bed will process a maximum of 50 gph of waste plus the required volume of cooling water. The test bed will evaluate the performance of a number of SCWO reactor designs. The goal of the project is to select a reactor that can be scaled up for use in a full-size waste treatment facility to process US Department of Energy mixed wastes. EG&G Idaho, Inc. will design and construct the SCWO test bed at the Water Reactor Research Test Facility (WRRTF), located in the northern region of the INEL. Private industry partners will develop and provide SCWO reactors to interface with the test bed. A number of reactor designs will be tested, including a transpiring wall, tube, and vessel-type reactor. The initial SCWO reactor evaluated will be a transpiring wall design. This design requirements report identifies parameters needed to proceed with preliminary and final design work for the SCWO test bed. A flow sheet and Process and Instrumentation Diagrams define the overall process and conditions of service and delineate equipment, piping, and instrumentation sizes and configuration Codes and standards that govern the safe engineering and design of systems and guidance that locates and interfaces test bed hardware are provided. Detailed technical requirements are addressed for design of piping, valves, instrumentation and control, vessels, tanks, pumps, electrical systems, and structural steel. The approach for conducting the preliminary and final designs and environmental and quality issues influencing the design are provided.

  9. Applications Tests of Commercial Heat Pump Water Heaters

    E-Print Network [OSTI]

    Oshinski, J. N..; Abrams, D. W.

    1987-01-01T23:59:59.000Z

    Field application tests have been conducted on three 4 to 6-ton commercial heat pump water heater systems in a restaurant, a coin-operated laundry, and an office building cafeteria in Atlanta. The units provide space cooling while rejecting heat...

  10. 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.

    2014-07-01T23:59:59.000Z

    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.

  11. Review of International Methods of Test to Rate the Efficiency of Water Heaters

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    associated with the EU water heater test procedure loadEU test procedure for water heaters. Load No. Delivered Max.period to allow the water heater to adjust completely to

  12. 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

    2008-04-01T23:59:59.000Z

    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.

  13. 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....

  14. Fundamental Understanding of Crack Growth in Structural Components of Generation IV Supercritical Light Water Reactors

    SciTech Connect (OSTI)

    Iouri I. Balachov; Takao Kobayashi; Francis Tanzella; Indira Jayaweera; Palitha Jayaweera; Petri Kinnunen; Martin Bojinov; Timo Saario

    2004-11-17T23:59:59.000Z

    This work contributes to the design of safe and economical Generation-IV Super-Critical Water Reactors (SCWRs) by providing a basis for selecting structural materials to ensure the functionality of in-vessel components during the entire service life. During the second year of the project, we completed electrochemical characterization of the oxide film properties and investigation of crack initiation and propagation for candidate structural materials steels under supercritical conditions. We ranked candidate alloys against their susceptibility to environmentally assisted degradation based on the in situ data measure with an SRI-designed controlled distance electrochemistry (CDE) arrangement. A correlation between measurable oxide film properties and susceptibility of austenitic steels to environmentally assisted degradation was observed experimentally. One of the major practical results of the present work is the experimentally proven ability of the economical CDE technique to supply in situ data for ranking candidate structural materials for Generation-IV SCRs. A potential use of the CDE arrangement developed ar SRI for building in situ sensors monitoring water chemistry in the heat transport circuit of Generation-IV SCWRs was evaluated and proved to be feasible.

  15. Results of the DF-4 BWR (boiling water reactor) control blade-channel box test

    SciTech Connect (OSTI)

    Gauntt, R.O.; Gasser, R.D.

    1990-10-01T23:59:59.000Z

    The DF-4 in-pile fuel damage experiment investigated the behavior of boiling water reactor (BWR) fuel canisters and control blades in the high temperature environment of an unrecovered reactor accident. This experiment, which was carried out in the Annular Core Research Reactor (ACRR) at Sandia National Laboratories, was performed under the USNRC's internationally sponsored severe fuel damage (SFD) program. The DF-4 test is described herein and results from the experiment are presented. Important findings from the DF-4 test include the low temperature melting of the stainless steel control blade caused by reaction with the B{sub 4}C, and the subsequent low temperature attack of the Zr-4 channel box by the relocating molten blade components. Hydrogen generation was found to continue throughout the experiment, diminishing slightly following the relocation of molten oxidizing zircaloy to the lower extreme of the test bundle. A large blockage which was formed from this material continued to oxidize while steam was being fed into the the test bundle. The results of this test have provided information on the initial stages of core melt progression in BWR geometry involving the heatup and cladding oxidation stages of a severe accident and terminating at the point of melting and relocation of the metallic core components. The information is useful in modeling melt progression in BWR core geometry, and provides engineering insight into the key phenomena controlling these processes. 12 refs., 12 figs.

  16. Field Validation of Toxicity Tests to Evaluate the Potential for Beneficial Use of Produced Water

    SciTech Connect (OSTI)

    Joseph Bidwell; Jonathan Fisher; Naomi Cooper

    2008-03-31T23:59:59.000Z

    This study investigated potential biological effects of produced water contamination derived from occasional surface overflow and possible subsurface intrusion at an oil production site along the shore of Skiatook Lake, Oklahoma. We monitored basic chemistry and acute toxicity to a suite of standard aquatic test species (fathead minnow-Pimephales promelas, Daphnia pulex, Daphnia magna, and Ceriodaphnia dubia) in produced water and in samples taken from shallow groundwater wells on the site. Toxicity identification evaluations and ion toxicity modeling were used to identify toxic constituents in the samples. Lake sediment at the oil production site and at a reference site were also analyzed for brine intrusion chemically and by testing sediment toxicity using the benthic invertebrates, Chironomus dilutus, and Hyallela azteca. Sediment quality was also assessed with in situ survival and growth studies with H. azteca and the Asian clam, Corbicula fluminea, and by benthic macroinvertebrate community sampling. The produced water was acutely toxic to the aquatic test organisms at concentrations ranging from 1% to 10% of the whole produced water sample. Toxicity identification evaluation and ion toxicity modeling indicated major ion salts and hydrocarbons were the primary mixture toxicants. The standardized test species used in the laboratory bioassays exhibited differences in sensitivity to these two general classes of contaminants, which underscores the importance of using multiple species when evaluating produced water toxicity. Toxicity of groundwater was greater in samples from wells near a produced water injection well and an evaporation pond. Principle component analyses (PCA) of chemical data derived from the groundwater wells indicated dilution by lake water and possible biogeochemical reactions as factors that ameliorated groundwater toxicity. Elevated concentrations of major ions were found in pore water from lake sediments, but toxicity from these ions was limited to sediment depths of 10 cm or greater, which is outside of the primary zone of biological activity. Further, exposure to site sediments did not have any effects on test organisms, and macroinvertebrate communities did not indicate impairment at the oil production site as compared to a reference site. In situ experiments with H. azteca and C. fluminea, indicated a sublethal site effect (on growth of both species), but these could not be definitively linked with produced water infiltration. Severe weather conditions (drought followed by flooding) negatively influenced the intensity of lake sampling aimed at delineating produced water infiltration. Due to the lack of clear evidence of produced water infiltration into the sub-littoral zone of the lake, it was not possible to assess whether the laboratory bioassays of produced water effectively indicate risk in the receiving system. However, the acutely toxic nature of the produced water and general lack of biological effects in the lake at the oil production site suggest minimal to no produced water infiltration into surficial lake sediments and the near-shore water column. This study was able to demonstrate the utility of ion toxicity modeling to support data from toxicity identification evaluations aimed at identifying key toxic constituents in produced water. This information could be used to prioritize options for treating produced water in order to reduce toxic constituents and enhance options for reuse. The study also demonstrated how geographic information systems, toxicity modeling, and toxicity assessment could be used to facilitate future site assessments.

  17. Hazard classification for the supercritical water oxidation test bed. Revision 1

    SciTech Connect (OSTI)

    Ramos, A.G.

    1994-10-01T23:59:59.000Z

    A hazard classification of ``routinely accepted by the public`` has been determined for the operation of the supercritical water oxidation test bed at the Idaho National Engineering Laboratory. This determination is based on the fact that the design and proposed operation meet or exceed appropriate national standards so that the risks are equivalent to those present in similar activities conducted in private industry. Each of the 17 criteria for hazards ``routinely accepted by the public,`` identified in the EG and G Idaho, Inc., Safety Manual, were analyzed. The supercritical water oxidation (SCWO) test bed will treat simulated mixed waste without the radioactive component. It will be designed to operate with eight test wastes. These test wastes have been chosen to represent a broad cross-section of candidate mixed wastes anticipated for storage or generation by DOE. In particular, the test bed will generate data to evaluate the ability of the technology to treat chlorinated waste and other wastes that have in the past caused severe corrosion and deposition in SCWO reactors.

  18. Supercritical water oxidation test bed effluent treatment study

    SciTech Connect (OSTI)

    Barnes, C.M.

    1994-04-01T23:59:59.000Z

    This report presents effluent treatment options for a 50 h Supercritical Water Test Unit. Effluent compositions are calculated for eight simulated waste streams, using different assumed cases. Variations in effluent composition with different reactor designs and operating schemes are discussed. Requirements for final effluent compositions are briefly reviewed. A comparison is made of two general schemes. The first is one in which the effluent is cooled and effluent treatment is primarily done in the liquid phase. In the second scheme, most treatment is performed with the effluent in the gas phase. Several unit operations are also discussed, including neutralization, mercury removal, and evaporation.

  19. Wave-Energy Company Looks to Test Prototypes in Maine Waters...

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

    Wave-Energy Company Looks to Test Prototypes in Maine Waters Wave-Energy Company Looks to Test Prototypes in Maine Waters April 9, 2010 - 4:19pm Addthis Lindsay Gsell Resolute...

  20. Field Testing of Pre-Production Prototype Residential Heat Pump Water Heaters

    Broader source: Energy.gov [DOE]

    Provides and overview of field testing of 18 pre-production prototype residential heat pump water heaters

  1. Comment submitted by the Alliance for Water Efficiency (AWE) regarding the Energy Star Verification Testing Program

    Broader source: Energy.gov [DOE]

    This document is a comment submitted by the Alliance for Water Efficiency (AWE) regarding the Energy Star Verification Testing Program

  2. R t f N l C t T ti Di i GReport of Nuclear Component Testing Discussion Group National Spherical Torus ProgramNational Spherical Torus Program

    E-Print Network [OSTI]

    Office of Science R t f N l C t T ti Di i GReport of Nuclear Component Testing Discussion Group nuclear technology, SG1 leader UCLA DOE contact: Eckstrand, Steve, OFES #12;Nuclear Component Testing (NCT) aims to complement ITER mission and fill many DEMO R&D gaps · Mission of the Nuclear Component Testing

  3. 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.

    2009-11-30T23:59:59.000Z

    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.

  4. Development test report for the high pressure water jet system nozzles

    SciTech Connect (OSTI)

    Takasumi, D.S.

    1995-09-28T23:59:59.000Z

    The high pressure water jet nozzle tests were conducted to identify optimum water pressure, water flow rate, nozzle orifice size and fixture configuration needed to effectively decontaminate empty fuel storage canisters in KE-Basin. This report gives the tests results and recommendations from the these tests.

  5. 225-kW Dynamometer for Testing Small Wind Turbine Components (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2010-06-01T23:59:59.000Z

    This fact sheet describes the capabilities, operating envelope, loads and components of the 225-kW dynamometer at the NWTC.

  6. 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

    2014-05-01T23:59:59.000Z

    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.

  7. Feasibility of Using Measurements of Internal Components ofTankless Water Heaters for Field Monitoring of Energy and Water Use

    SciTech Connect (OSTI)

    Lutz, Jim; Biermayer, Peter

    2008-04-17T23:59:59.000Z

    The objective of this study was to determine if it was feasible to collect information regarding energy use and hot water delivery from tankless gas water heaters using the sensors and controls built into the water heaters. This could then be used to determine the water heater efficiency ? the ratio of energy out (hot water delivered) to energy in (energy in the gas) in actual residential installations. The goal was to be as unobtrusive as possible, and to avoid invalidating warranties or exposing researchers to liability issues. If feasible this approach would reduce the costs of instrumentation.This paper describes the limited field and laboratory investigations to determine if using the sensors and controls built into tankless water heaters is feasible for field monitoring.It was more complicated to use the existing gas flow, water and temperature sensors than was anticipated. To get the signals from the existing sensors and controls is difficult and may involve making changes that would invalidate manufacturer warrantees. The procedures and methods for using signals from the existing gas valves, water flow meters and temperature sensors will vary by model. To be able to monitor different models and brands would require detailed information about each model and brand.Based on these findings, we believe that for field monitoring projects it would be easier, quicker and safer to connect external meters to measure the same parameters rather than using the sensors and controls built into tankless water heaters.

  8. US Synthetic Corp (TRL 4 Component)- The Development of Open, Water Lubricated Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines

    Broader source: Energy.gov [DOE]

    US Synthetic Corp (TRL 4 Component) - The Development of Open, Water Lubricated Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines

  9. Concentrating Solar Power �¢���� Central Receiver Panel Component Fabrication and Testing FINAL REPORT

    SciTech Connect (OSTI)

    McDowell, Michael W [Pratt & Whitney Rocketdyne; Miner, Kris [Pratt & Whitney Rocketdyne

    2013-03-30T23:59:59.000Z

    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 test scale prototype receiver, off sun but at temperature, at a molten salt loop at ground level adjacent to the tower also had to be abandoned. Thus, no test facility existed for a molten salt receiver test. As a result, PWR completed the prototype receiver design and then fabricated key components for testing instead of fabricating the complete prototype receiver. A number of innovative design ideas have been developed. Key features of the receiver panel have been identified. This evaluation includes input from Solar 2, personal experience of people working on these programs and meetings with Sandia. Key components of the receiver design and key processes used to fabricate a receiver have been selected for further evaluation. The Test Plan, Concentrated Solar Power Receiver In Cooperation with the Department of Energy and Sandia National Laboratory was written to define the scope of the testing to be completed as well as to provide details related to the hardware, instrumentation, and data acquisition. The document contains a list of test objectives, a test matrix, and an associated test box showing the operating points to be tested. Test Objectives: 1. Demonstrate low-cost manufacturability 2. Demonstrate robustness of two different tube base materials 3. Collect temperature data during on sun operation 4. Demonstrate long term repeated daily operation of heat shields 5. Complete pinhole tube weld repairs 6. Anchor thermal models This report discusses the tests performed, the results, and implications for design improvements and LCOE reduction.

  10. Pilot scale test of a produced water-treatment system for initial removal of organic compounds

    SciTech Connect (OSTI)

    Sullivan, Enid J [Los Alamos National Laboratory; Kwon, Soondong [UT-AUSTIN; Katz, Lynn [UT-AUSTIN; Kinney, Kerry [UT-AUSTIN

    2008-01-01T23:59:59.000Z

    A pilot-scale test to remove polar and non-polar organics from produced water was performed at a disposal facility in Farmington NM. We used surfactant-modified zeolite (SMZ) adsorbent beds and a membrane bioreactor (MBR) in combination to reduce the organic carbon content of produced water prior to reverse osmosis (RO). Reduction of total influent organic carbon (TOC) to 5 mg/L or less is desirable for efficient RO system operation. Most water disposed at the facility is from coal-bed gas production, with oil production waters intermixed. Up to 20 gal/d of produced water was cycled through two SMZ adsorbent units to remove volatile organic compounds (BTEX, acetone) and semivolatile organic compounds (e.g., napthalene). Output water from the SMZ units was sent to the MBR for removal of the organic acid component of TOC. Removal of inorganic (Mn and Fe oxide) particulates by the SMZ system was observed. The SMZ columns removed up to 40% of the influent TOC (600 mg/L). BTEX concentrations were reduced from the initial input of 70 mg/L to 5 mg/L by the SMZ and to an average of 2 mg/L after the MBR. Removal rates of acetate (input 120-170 mg/L) and TOC (input up to 45 mg/L) were up to 100% and 92%, respectively. The water pH rose from 8.5 to 8.8 following organic acid removal in the MBR; this relatively high pH was likely responsible for observed scaling of the MBR internal membrane. Additional laboratory studies showed the scaling can be reduced by metered addition of acid to reduce the pH. Significantly, organic removal in the MBR was accomplished with a very low biomass concentration of 1 g/L throughout the field trial. An earlier engineering evaluation shows produced water treatment by the SMZ/MBR/RO system would cost from $0.13 to $0.20 per bbl at up to 40 gpm. Current estimated disposal costs for produced water are $1.75 to $4.91 per bbl when transportation costs are included, with even higher rates in some regions. Our results suggest that treatment by an SMZ/MBR/RO system may be a feasible alternative to current methods for produced water treatment and disposal.

  11. Moving Granular-Bed Filter Development Program, Option 1 - Component Test Facilities - Test Plan; topical report, September 8, 1995

    SciTech Connect (OSTI)

    NONE

    1997-12-31T23:59:59.000Z

    A test plan has been devised for Option 1 Contract period that focuses on the remaining SMGBF technical issues for the purpose of optimizing the SMGBF performance and generating key process performance data needed to promote the continued development of the technology. These technical issues have been identified and ranked in the Task 8, Technical Tradeoffs and Issues Report, submitted to DOE in May, 1994. Three activities are defined in this test plan to address the key issues identified: the first activity performs engineering modeling and design evaluation to Support the test activities; the second activity is directed toward SMGBF cold flow model testing; and the third activity is directed toward high- temperature, high-pressure (HTHP) SMGBF testing. All of the activities are directed toward Recycle SMGBF, although much of it also applies to Once-Through SMGBF.

  12. A Principal Components Analysis of Executive Processes: Exploring the Structure of Executive Functions using Neuropsychological Tests 

    E-Print Network [OSTI]

    Maner, Safir

    2011-11-23T23:59:59.000Z

    ”, “Dual-Tasking” and “Planning”) and their relationship to “Intelligence”. The separability of these executive functions was explored. Ten neuropsychological tests were administered to young and healthy participants (N =103). Correlations between tests...

  13. A Scaleless Snake: Tests of the Role of Reptilian Scales in Water Loss and Heat Transfer

    E-Print Network [OSTI]

    Bennett, Albert F.

    A Scaleless Snake: Tests of the Role of Reptilian Scales in Water Loss and Heat Transfer Reprinted: Tests of the Role of Reptilian Scales in Water Loss and Heat Transfer A unique specimen of gopher snake of pulmocutaneous water loss and heat transfer, no difference was observed between the scale- less animal

  14. A COMPARISON OF LABORATORY AND FIELD-TEST MEASUREMENTS OF HEAT PUMP WATER HEATERS

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    #12;A COMPARISON OF LABORATORY AND FIELD-TEST MEASUREMENTS OF HEAT PUMP WATER HEATERS William P a heat pump water heater (HPWH). After developing the HPWH, a field-test plan was implemented whereby 20 evaluate this effect. #12;INTRODUCTION Domestic water heaters account for approximately 2.5 EJ (2.4 x 1015

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

    SciTech Connect (OSTI)

    Wohlgemuth, J. H.; Kurtz, S.

    2011-02-01T23:59:59.000Z

    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.

  16. FOCUS: HARSH ENVIRONMENT MASS SPECTROMETRY Field Testing of Lake Water Chemistry with a

    E-Print Network [OSTI]

    Entekhabi, Dara

    FOCUS: HARSH ENVIRONMENT MASS SPECTROMETRY Field Testing of Lake Water Chemistry with a Portable waters. KOALA is a backpackable MS operated from above the water surface, in which samples are pumped for temperature control of a membrane inlet when steep thermal gradients are present in a water body, as well

  17. A reformulated, reconstituted water for testing the freshwater amphipod, Hyalella azteca

    SciTech Connect (OSTI)

    Smith, M.E.; Herrin, L.E.; Thoeny, W.T. [SBI Environmental, Cincinnati, OH (United States); Lazorchak, J.M. [Environmental Protection Agency, Cincinnati, OH (United States); Brewer-Swartz, S. [EMPE, Nashville, TN (United States)

    1997-06-01T23:59:59.000Z

    Toxicity testing with the freshwater amphipod, Hyalella azteca, has routinely been conducted using nonstandard waters. Four waters were tested for acceptability for aqueous reference toxicant testing with H. azteca. These included three formulated (standardized) waters: moderately hard reconstituted water (MHRW), reformulated moderately hard reconstituted water (RMHRW), and 25% dilute mineral water (DMW). The water used for comparison was a nonstandard, in-house culture water mixture of well water and dechlorinated tap water, diluted with Super-Q{reg_sign} deionized water to a hardness of 100 mg/L, as CaCO{sub 3} (LL/SQ). Control survival was less than the 90% minimum control survival criteria in all tests with MHRW. Two of five tests with DMW also failed to pass the minimum control survival criteria. All five tests with the RMHRW passed the control survival criteria. The mean 50% lethal concentration (LC50) for the tests in RMHRW was 320 mg/L KCl, with a coefficient of variation of 8.5%. Concurrent tests with the in-house water yielded control survival greater than 90% and a mean LC50 of 216 mg/L KCl with a coefficient of variation of 13.4%. Tests in an interlaboratory study yielded similar results. Whole-sediment toxicity tests conducted using RMHRW as the overlying water routinely exceed the 80% minimum survival criteria in the control and reference sediments. The failure of MHRW and DMW to produce acceptable results, as well as the inability of other laboratories to produce LL/SQ, makes RMHRW the best candidate for a standard water for H. azteca testing.

  18. Side-by-Side Testing of Water Heating Systems: Results from the 2009-2010 Evaluation

    Broader source: Energy.gov [DOE]

    The performance of seven differing types of residential water heating systems was compared in a side-by-side test configuration over a full year period. The Hot Water System Laboratory (HWS Lab) test facility at the Florida Solar Energy Center (FSEC) in Cocoa, FL was used for the tests.

  19. Implementation and Testing of Water Quality Lucy Cheng

    E-Print Network [OSTI]

    Fay, Noah

    Student Fellowship Program #12;1 BACKGROUND In Arizona, due the market development of realtime water quality sensors. These sensors are convenient in detecting aspects of the sensors in their implementations, have not been well studied. The water quality sensors

  20. Life extension of structural components via an improved nondestructive testing methodology

    E-Print Network [OSTI]

    Hohmann, Brian P. (Brian Patrick)

    2010-01-01T23:59:59.000Z

    An experimental study was performed to determine the flaw detection sensitivity of advanced nondestructive testing (NDT) techniques with respect to structural applications. The techniques analyzed exemplify the incorporation ...

  1. Mechanism of Irradiation Assisted Cracking of Core Components in Light Water Reactors

    SciTech Connect (OSTI)

    Gary S. Was; Michael Atzmon; Lumin Wang

    2003-04-28T23:59:59.000Z

    The overall goal of the project is to determine the mechanism of irradiation assisted stress corrosion cracking (IASCC). IASCC has been linked to hardening, microstructural and microchemical changes during irradiation. Unfortunately, all of these changes occur simultaneously and at similar rates during irradiation, making attribution of IASCC to any one of these features nearly impossible to determine. The strategy set forth in this project is to develop means to separate microstructural from microchemical changes to evaluate each separately for their effect on IASCC. In the first part, post irradiation annealing (PIA) treatments are used to anneal the irradiated microstructure, leaving only radiation induced segregation (RIS) for evaluation for its contribution to IASCC. The second part of the strategy is to use low temperature irradiation to produce a radiation damage dislocation loop microstructure without radiation induced segregation in order to evaluate the effect of the dislocation microstructure alone. A radiation annealing model was developed based on the elimination of dislocation loops by vacancy absorption. Results showed that there were indeed, time-temperature annealing combinations that leave the radiation induced segregation profile largely unaltered while the dislocation microstructure is significantly reduced. Proton irradiation of 304 stainless steel irradiated with 3.2 MeV protons to 1.0 or 2.5 dpa resulted in grain boundary depletion of chromium and enrichment of nickel and a radiation damaged microstructure. Post irradiation annealing at temperatures of 500 ? 600°C for times of up to 45 min. removed the dislocation microstructure to a greater degree with increasing temperatures, or times at temperature, while leaving the radiation induced segregation profile relatively unaltered. Constant extension rate tensile (CERT) experiments in 288°C water containing 2 ppm O2 and with a conductivity of 0.2 mS/cm and at a strain rate of 3 x 10-7 s-1 showed that the IASCC susceptibility, as measured by the crack length per unit strain, decreased with very short anneals and was almost completely removed by an anneal at 500°C for 45 min. This annealing treatment removed about 15% of the dislocation microstructure and the irradiation hardening, but did not affect the grain boundary chromium depletion or nickel segregation, nor did it affect the grain boundary content of other minor impurities. These results indicate that RIS is not the sole controlling feature of IASCC in irradiated stainless steels in normal water chemistry. The isolation of the irradiated microstructure was approached using low temperature irradiation or combinations of low and high temperature irradiations to achieve a stable, irradiated microstructure without RIS. Experiments were successful in achieving a high degree of irradiation hardening without any evidence of RIS of either major or minor elements. The low temperature irradiations to doses up to 0.3 dpa at T<75°C were also very successful in producing hardening to levels considerably above that for irradiations conducted under nominal conditions of 1 dpa at 360°C. However, the microstructure consisted of an extremely fine dispersion of defect clusters of sizes that are not resolvable by either transmission electron microscopy (TEM) or small angle x-ray scattering (SAXS). The microstructure was not stable at the 288°C IASCC test temperature and resulted in rapid reduction of hardening and presumably, annealing of the defect clusters at this temperature as well. Nevertheless, the annealing studies showed that treatments that resulted in significant decreases in the hardening produced small changes in the dislocation microstructure that were confined to the elimination of the finest of loops (~1 nm). These results substantiate the importance of the very fine defect microstructure in the IASCC process. The results of this program provide the first definitive evidence that RIS is not the sole controlling factor in the irradiation assisted stress corrosion cracking of austenitic stain

  2. Annotated bibliography of the Northwest Territories action on water component of the Arctic environmental strategy

    SciTech Connect (OSTI)

    Goodwin, R.

    1998-01-01T23:59:59.000Z

    Water-related research conducted under the 1991--97 Arctic Environmental Strategy resulted in the production of 215 publications listed in this bibliography. The main section sorts citations by author and then by title. All citations are annotated and are keyed to the database of the Arctic Science and Technology Information System (ASTIS). The bibliography has three indexes that refer back to the main section: Subject, geographic area, and title. Topics covered include Northwest Territories hydrology, environmental fate of contaminants, water quality, snow, the water cycle, modelling, and limnology.

  3. NREL's e-Ca Test: A Scalable, High-Sensitivity Water Permeation Measurement Methodology (Poster)

    SciTech Connect (OSTI)

    Dameron, A.; Kempe, M.; Reese, M.

    2014-02-01T23:59:59.000Z

    A test method is described that uses the resistivity of a Calcium film to detect very small amounts of water permeating through a barrier material.

  4. Field testing of component-level model-based fault detection methods for mixing boxes and VAV fan systems

    SciTech Connect (OSTI)

    Xu, Peng; Haves, Philip

    2002-05-16T23:59:59.000Z

    An automated fault detection and diagnosis tool for HVAC systems is being developed, based on an integrated, life-cycle, approach to commissioning and performance monitoring. The tool uses component-level HVAC equipment models implemented in the SPARK equation-based simulation environment. The models are configured using design information and component manufacturers' data and then fine-tuned to match the actual performance of the equipment by using data measured during functional tests of the sort using in commissioning. This paper presents the results of field tests of mixing box and VAV fan system models in an experimental facility and a commercial office building. The models were found to be capable of representing the performance of correctly operating mixing box and VAV fan systems and detecting several types of incorrect operation.

  5. Estimation of land surface water and energy balance flux components and closure relation using conditional sampling

    E-Print Network [OSTI]

    Farhadi, Leila

    2012-01-01T23:59:59.000Z

    Models of terrestrial water and energy balance include numerical treatment of heat and moisture diffusion in the soil-vegetation-atmosphere continuum. These two diffusion and exchange processes are linked only at a few ...

  6. Liquid-Water Uptake and Removal in PEM Fuel-Cell Components

    SciTech Connect (OSTI)

    Das, Prodip K.; Gunterman, Haluna P.; Kwong, Anthony; Weber, Adam Z.

    2011-09-23T23:59:59.000Z

    Management of liquid water is critical for optimal fuel-cell operation, especially at low temperatures. It is therefore important to understand the wetting properties and water holdup of the various fuel-cell layers. While the gas-diffusion layer is relatively hydrophobic and exhibits a strong intermediate wettability, the catalyst layer is predominantly hydrophilic. In addition, the water content of the ionomer in the catalyst layer is lower than that of the bulk membrane, and is affected by platinum surfaces. Liquid-water removal occurs through droplets on the surface of the gas-diffusion layer. In order to predict droplet instability and detachment, a force balance is used. While the pressure or drag force on the droplet can be derived, the adhesion or surface-tension force requires measurement using a sliding-angle approach. It is shown that droplets produced by forcing water through the gas-diffusion layer rather than placing them on top of it show much stronger adhesion forces owing to the contact to the subsurface water.

  7. Determination of Water Saturation in Relatively Dry Porous Media Using Gas-phase Tracer Tests

    SciTech Connect (OSTI)

    Oostrom, Martinus; Tartakovsky, Guzel D.; Wietsma, Thomas W.; Truex, Michael J.; Dane, Jacob H.

    2011-04-15T23:59:59.000Z

    Soil desiccation (drying), involving water evaporation induced by dry air injection and extraction, is a potentially robust remediation process to slow migration of inorganic or radionuclide contaminants through the vadose zone. The application of gas-phase partitioning tracer tests has been proposed as a means to estimate initial water volumes and to monitor the progress of the desiccation process at pilot-test and field sites. In this paper, tracer tests have been conducted in porous medium columns with various water saturations using sulfur hexafluoride as the conservative tracer and tricholorofluoromethane and difluoromethane as the water-partitioning tracers. For porous media with minimal silt and/or organic matter fractions, tracer tests provided reasonable saturation estimates for saturations close to zero. However, for sediments with significant silt and/or organic matter fractions, tracer tests only provided satisfactory results when the water saturation was at least 0.1 - 0.2. For dryer conditions, the apparent tracer retardation increases due to air – soil sorption, which is not included in traditional retardation coefficients derived from advection-dispersion equations accounting only for air – water partitioning and water – soil sorption. Based on these results, gas-phase partitioning tracer tests may be used to determine initial water volumes in sediments, provided the initial water saturations are sufficiently large. However, tracer tests are not suitable for quantifying moisture content in desiccated sediments.

  8. 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.

    2008-05-05T23:59:59.000Z

    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.

  9. Water Loss Test Results for the West Main Pipeline United Irrigation District of Hidalgo County

    E-Print Network [OSTI]

    Leigh, E.; Fipps, G.

    TR-322 2008 Water Loss Test Results for the West Main Pipeline United Irrigation District of Hidalgo County Eric Leigh Texas AgriLife Extension Associate, Biological and Agricultural Engineering, College... Station Guy Fipps Texas AgriLife Extension Professor and Extension Agricultural Engineer, Biological and Agricultural Engineering, College Station March 20, 2007 Water Loss Test Results for the West Main Pipeline United Irrigation...

  10. DESIGN AND DEVELOPMENT TESTING OF AN IMPROVED (1 HIGH-EFFICIENCY WATER HEATER

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    #12;DESIGN AND DEVELOPMENT TESTING OF AN IMPROVED (1 HIGH-EFFICIENCY WATER HEATER (2} (3) (21 icense in and to any copyright covering the drticle. This paper describes a high-efficiency water heater which uses a design approach quite different from the conventional center-flue water heater. While high

  11. Acoustic Emission and Guided Ultrasonic Waves for Detection and Continuous Monitoring of Cracks in Light Water Reactor Components

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Coble, Jamie B.; Ramuhalli, Pradeep; Watson, Bruce E.; Cumblidge, Stephen E.; Doctor, Steven R.; Bond, Leonard J.

    2012-06-28T23:59:59.000Z

    Acoustic emission (AE) and guided ultrasonic waves (GUW) are considered for continuous monitoring and detection of cracks in Light Water Reactor (LWR) components. In this effort, both techniques are applied to the detection and monitoring of fatigue crack growth in a full scale pipe component. AE results indicated crack initiation and rapid growth in the pipe, and significant GUW responses were observed in response to the growth of the fatigue crack. After initiation, the crack growth was detectable with AE for approximately 20,000 cycles. Signals associated with initiation and rapid growth where distinguished based on total rate of activity and differences observed in the centroid frequency of hits. An intermediate stage between initiation and rapid growth was associated with significant energy emissions, though few hits. GUW exhibit a nearly monotonic trend with crack length with an exception of measurements obtained at 41 mm and 46 mm.

  12. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.1.1 Error-Detecting Command Format

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.1.1 Error-Detecting Command Format. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.1.1 Error

  13. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5a Code in PROM

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5a Code in PROM Date: February 13 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement-0045 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  14. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.2 Capability to Upload Data

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.2 Capability to Upload Data Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.2 Capability to Upload

  15. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5c Code in PROM

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5c Code in PROM Date: February 13 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement-0047 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  16. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.4.2 HST Memory Monitor Commanding

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.4.2 HST Memory Monitor Commanding. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.4.2 HST Memory

  17. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.4.1 HST Memory Monitors in Housekeeping

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.4.1 HST Memory Monitors. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.4.1 HST Memory

  18. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5c Code in PROM

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5c Code in PROM Date: February 13 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.09 Component Test Results Requirement-0015 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  19. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.2.1 Process Memory Download Commands

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.2.1 Process Memory Download Commands. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.2.1 Process Memory

  20. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.2b Command to Disable/Enable Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.2b Command to Disable. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.2b Command

  1. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.2 Echoes for Command Opcode and Parameters

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.2 Echoes for Command Opcode. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.2 Echoes

  2. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.2.1 Process Memory Download Commands

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.2.1 Process Memory Download Commands. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.2.1 Process Memory

  3. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.3.1 CRC Background Checking on Memory Regions

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.3.1 CRC Background Checking on Memory. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.3.1 CRC

  4. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.1 Process Memory Copy Commands

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.1 Process Memory Copy Commands Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.1 Process Memory

  5. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.4 Command to Disable/Enable CRC Checking on Upload

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.4 Command to Disable/Enable CRC. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5

  6. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.1Housekeeping Response Within One Second

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.1Housekeeping Response Within One. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5

  7. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5a Performs Requisite Initializations

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5a Performs Requisite. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5a Performs

  8. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.2 Capability to Upload Data

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.2 Capability to Upload Data Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.1.2 Capability to Upload

  9. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.4.1 HST Memory Monitors in Housekeeping

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.4.1 HST Memory Monitors. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.4.1 HST Memory

  10. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.1.1 Error-Detecting Command Format

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.1.1 Error-Detecting Command Format. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.1.1 Error

  11. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.3 Capability to Log Diagnostics

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.3 Capability to Log Diagnostics. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.2.3 Capability

  12. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.2a Command to Disable/Enable Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.2a Command to Disable. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.2a Command

  13. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5d Code in PROM

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5d Code in PROM Date: February 13 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.09 Component Test Results Requirement-0016 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  14. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5d Code in PROM

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5d Code in PROM Date: February 13 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement-0048 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  15. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5b Code in PROM

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.5b Code in PROM Date: February 13 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement-0046 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  16. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.1 Process Memory Copy Commands

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.1 Process Memory Copy Commands Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.1 Process Memory

  17. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.4.2 HST Memory Monitor Commanding

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.4.2 HST Memory Monitor Commanding. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.4.2 HST Memory

  18. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.2 Distinguish between Power-Up and Watchdog Resets

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.2 Distinguish between Power. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5

  19. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.1 Housekeeping Response Within One Second

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.1 Housekeeping Response Within One. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5

  20. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.4 Command to Disable/Enable CRC Checking on Upload

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.5.1.4 Command to Disable/Enable CRC. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5

  1. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.3.1 CRC Background Checking on Memory Regions

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.3.1 CRC Background Checking on Memory. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.5.3.1 CRC

  2. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.4 Memory Initialization on Power-Up Only

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.4 Memory Initialization on Power. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.4 Memory

  3. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.2b Command to Disable/Enable Watchdog

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.2b Command to Disable. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.2b Command

  4. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.5a HST Error Format

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.5a HST Error Format Date: February for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement-03-0054 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW

  5. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5b Code in PROM

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.5b Code in PROM Date: February 13 for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.09 Component Test Results Requirement-0014 February 13, 2001 Center for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1

  6. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.2 Distinguish Between Power-up and Watchdog Resets

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.2 Distinguish Between Power. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 for Astrophysics & Space Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5

  7. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.3 Capability to Log Diagnostics

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.3 Capability to Log Diagnostics. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.2.3 Capability

  8. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.4 Memory Initialization on Power-Up Only

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.4 Memory Initialization on Power. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.4 Memory

  9. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.2 Echoes for Command Opcode and Parameters

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.2 Echoes for Command Opcode. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 & Space Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.2 Echoes

  10. 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

    2011-02-01T23:59:59.000Z

    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.

  11. Water Power Calculator Temperature and Analog Input/Output Module Ambient Temperature Testing

    SciTech Connect (OSTI)

    Mark D. McKay

    2011-02-01T23:59:59.000Z

    Water Power Calculator Temperature and Analog input/output Module Ambient Temperature Testing A series of three ambient temperature tests were conducted for the Water Power Calculator development using the INL Calibration Laboratory’s Tenney Environmental Chamber. The ambient temperature test results demonstrate that the Moore Industries Temperature Input Modules, Analog Input Module and Analog Output Module, ambient temperature response meet or exceed the manufactures specifications

  12. Disaggregating Hot Water Use and Predicting Hot Water Waste in Five Test Homes

    SciTech Connect (OSTI)

    Henderson, H.; Wade, J.

    2014-04-01T23:59:59.000Z

    While it is important to make the equipment (or 'plant') in a residential hot water system more efficient, the hot water distribution system also affects overall system performance and energy use. Energy wasted in heating water that is not used is estimated to be on the order of 10 to 30 percent of total domestic hot water (DHW) energy use. This field monitoring project installed temperature sensors on the distribution piping (on trunks and near fixtures) and programmed a data logger to collect data at 5 second intervals whenever there was a hot water draw. This data was used to assign hot water draws to specific end uses in the home as well as to determine the portion of each hot water that was deemed useful (i.e., above a temperature threshold at the fixture). Five houses near Syracuse NY were monitored. Overall, the procedures to assign water draws to each end use were able to successfully assign about 50% of the water draws, but these assigned draws accounted for about 95% of the total hot water use in each home. The amount of hot water deemed as useful ranged from low of 75% at one house to a high of 91% in another. At three of the houses, new water heaters and distribution improvements were implemented during the monitoring period and the impact of these improvements on hot water use and delivery efficiency were evaluated.

  13. Cesium reservoir and interconnective components. Final test report: TFE Verification Program

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    The program objective is to demonstrate the technology readiness of a TFE (thermionic fuel element) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW range. A thermionic converter must be supplied with cesium vapor for two reasons. Cesium atoms adsorbed on the surface of the emitter cause a reduction of the emitter work function to permit high current densities without excessive heating of the emitter. The second purpose of the cesium vapor is to provide space-charge neutralization in the emitter-collector gap so that the high current densities may flow across the gap unattenuated. The function of the cesium reservoir is to provide a source of cesium atoms, and to provide a reserve in the event that cesium is lost from the plasma by any mechanism. This can be done with a liquid cesium metal reservoir in which case it is heated to the desired temperature with auxiliary heaters. In a TFE, however, it is desirable to have the reservoir passively heated by the nuclear fuel. In this case, the reservoir must operate at a temperature intermediate between the emitter and the collector, ruling out the use of liquid reservoirs. Integral reservoirs contained within the TFE will produce cesium vapor pressures in the desired range at typical electrode temperatures. The reservoir material that appears to be the best able to meet requirements is graphite. Cesium intercalates easily into graphite, and the cesium pressure is insensitive to loading for a given intercalation stage. The goals of the cesium reservoir test program were to verify the performance of Cs-graphite reservoirs in the temperature-pressure range of interest to TFE operation, and to test the operation of these reservoirs after exposure to a fast neutron fluence corresponding to seven year mission lifetime. In addition, other materials were evaluated for possible use in the integral reservoir.

  14. A NORMETEX MODEL 15 M3/HR WATER VAPOR PUMPING TEST

    SciTech Connect (OSTI)

    Klein, J.; Fowley, M.; Steeper, T.

    2010-12-20T23:59:59.000Z

    Tests were performed using a Model 15 m{sup 3}/hr Normetex vacuum pump to determine if pump performance degraded after pumping a humid gas stream. An air feed stream containing 30% water vapor was introduced into the pump for 365 hours with the outlet pressure of the pump near the condensation conditions of the water. Performance of the pump was tested before and after the water vapor pumping test and indicated no loss in performance of the pump. The pump also appeared to tolerate small amounts of condensed water of short duration without increased noise, vibration, or other adverse indications. The Normetex pump was backed by a dual-head diaphragm pump which was affected by the condensation of water and produced some drift in operating conditions during the test.

  15. Results and phenomena observed from the DF-4 BWR (boiling water reactor) control blade-channel box test

    SciTech Connect (OSTI)

    Gauntt, R.O.; Gasser, R.D.; Fryer, C.P.; Walker, J.V.

    1988-01-01T23:59:59.000Z

    The DF-4 in-pile fuel damage experiment, one of a series of tests performed as part of the USNRC's internationally sponsored severe fuel damage (SFD) program, and carried out at Sandia National Laboratories, addressed the behavior of boiling water reactor (BWR) fuel canisters and control blades in the high temperature environment of an unrecovered loss of coolant accident. The DF-4 test is described in some detail herein and results from the experiment are presented. Significant results from prior experiments in the series are also summarized. Important findings from the DF-4 test include the low temperature melting of the stainless steel control blade caused by reaction with the B/sub 4/C, and the subsequent low temperature attack of the Zr-4 channel box by the relocating molten blade components. This early melt and relocation phenomena could significantly influence the progression of meltdown in BWRs and should be considered in SFD accident analyses. 14 refs., 9 figs.

  16. Water Clarity Simulant for K East Basin Filtration Testing

    SciTech Connect (OSTI)

    Schmidt, Andrew J.

    2006-01-20T23:59:59.000Z

    This document provides a simulant formulation intended to mimic the behavior of the suspended solids in the K East (KE) Basin fuel storage pool. The simulant will be used to evaluate alternative filtration apparatus to improve Basin water clarity and to possibly replace the existing sandfilter. The simulant was formulated based on the simulant objectives, the key identified parameters important to filtration, the composition and character of the KE Basin suspended sludge particles, and consideration of properties of surrogate materials.

  17. Insights for aging management of light water reactor components: Metal containments. Volume 5

    SciTech Connect (OSTI)

    Shah, V.N.; Sinha, U.P. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Smith, S.K. [Ogden Environmental and Energy Services, Southfield, MI (United States)

    1994-03-01T23:59:59.000Z

    This report evaluates the available technical information and field experience related to management of aging damage to light water reactor metal containments. A generic aging management approach is suggested for the effective and comprehensive aging management of metal containments to ensure their safe operation. The major concern is corrosion of the embedded portion of the containment vessel and detection of this damage. The electromagnetic acoustic transducer and half-cell potential measurement are potential techniques to detect corrosion damage in the embedded portion of the containment vessel. Other corrosion-related concerns include inspection of corrosion damage on the inaccessible side of BWR Mark I and Mark II containment vessels and corrosion of the BWR Mark I torus and emergency core cooling system piping that penetrates the torus, and transgranular stress corrosion cracking of the penetration bellows. Fatigue-related concerns include reduction in the fatigue life (a) of a vessel caused by roughness of the corroded vessel surface and (b) of bellows because of any physical damage. Maintenance of surface coatings and sealant at the metal-concrete interface is the best protection against corrosion of the vessel.

  18. Water quality monitoring at the Hoe Creek test site: review and preliminary conclusions

    SciTech Connect (OSTI)

    Wang, F.T.

    1983-01-01T23:59:59.000Z

    Post-burn monitoring of the ground water near to the Hoe creek underground coal gasification site showed that a broad range of gasification products had been introduced into the water system. Although many of these contaminants were eventually absorbed by the surrounding coal, some chemicals continued to appear in the water in concentrations higher than pre-test levels for several years after gasification. Possible mechanisms by which the contaminants entered the ground water include: (1) leakage of pyrolysis products; (2) post-burn leaching of coal ash and overburden rubble by returning ground water; and (3) dissolution of minerals outside the cavity by the CO/SUB/2 generated during gasification.

  19. 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

    2007-06-30T23:59:59.000Z

    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-flow operation to natural circulation. Low-flow coolant events are the most difficult to design for because they involve the most complex thermal-hydraulic behavior induced by the dominance of thermal-buoyancy forces acting on the coolants. Such behavior can cause multiple-component flow interaction phenomena, which are not adequately understood or appreciated by reactor designers as to their impact on reactor performance and safety. Since the early 1990s, when DOE canceled the U.S. Liquid Metal Fast Breeder Reactor (LMFBR) program, little has been done experimentally to further understand the importance of the complex thermal-buoyancy phenomena and their impact on reactor design or to improve the ability of three-dimensional (3-D) transient computational fluid dynamics (CFD) and structures codes to model the phenomena. An improved experimental data base and the associated improved validated codes would provide needed design tools to the reactor community. The improved codes would also facilitate scale-up from small-scale testing to prototype size and would facilitate comparing performance of one reactor/component design with another. The codes would also have relevance to the design and safety of water-cooled reactors. To accomplish the preceding, it is proposed to establish a national GNEP-LMR research and development center at Argonne having as its foundation state-of-art science-based infrastructure consisting of: (a) thermal-hydraulic experimental capabilities for conducting both water and sodium testing of individual reactor components and complete reactor in-vessel models and (b) a computational modeling development and validation capability that is strongly interfaced with the experimental facilities. The proposed center would greatly advance capabilities for reactor development by establishing the validity of high-fidelity (i.e., close to first principles) models and tools. Such tools could be used directly for reactor design or for qualifying/tuning of lower-fidelity models, which now require costly experimental qualification for each different type of design

  20. 2014-02-21 Issuance: Test Procedure for Commercial Water Heating Equipment; Request for Information

    Broader source: Energy.gov [DOE]

    This document is a pre-publication Federal Register request for information regarding test procedures for commercial water heating equipment, as issued by the Deputy Assistant Secretary for Energy Efficiency (February 21, 2014).

  1. Water Research 38 (2004) 33313339 Testing a surface tension-based model to predict the salting

    E-Print Network [OSTI]

    Herbert, Bruce

    Water Research 38 (2004) 3331­3339 Testing a surface tension-based model to predict the salting out associated with transferring solutes from water to a salt solution to the difference in surface tensions likely reflects the inability of the simple surface tension model to account for all interactions among

  2. Private Water Well Testing in Areas Impacted by Marcellus Shale Gas Drilling

    E-Print Network [OSTI]

    Manning, Sturt

    Private Water Well Testing in Areas Impacted by Marcellus Shale Gas Drilling (Updated November 15th in the absence of shale-gas drilling, well owners are strongly encouraged to evaluate their water on a regular review of shale gas drilling in New York State, as well as the most comprehensive collection of data

  3. Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing,

    E-Print Network [OSTI]

    Optimization J. Vernon Cole and Ashok Gidwani CFDRC Prepared for: DOE Hydrogen Fuel Cell Kickoff MeetingWater Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing, and Design fuel cell design and operation; Demonstrate improvements in water management resulting in improved

  4. Acceptance test report for high pressure water jet system feed pump

    SciTech Connect (OSTI)

    Crystal, J.B.

    1996-03-12T23:59:59.000Z

    This document summarizes results of WHC-SD-SNF-ATP-016, Rev. 0 ``Acceptance Test Procedure High Pressure Water Jet System``, conducted on December 20, 1995 and December 22, 1995. This jet supplies water at 15,000 psi @ 15 gpm to nozzles to clean surfaces of empty fuel storage canisters.

  5. Fluence Thresholds for Laser-Induced Damage of Optical Components in the Injector Laser of the SSRL Gun Test Facility

    SciTech Connect (OSTI)

    Boton, P

    2005-01-31T23:59:59.000Z

    Damage threshold fluences for several optical components were measured at three wavelengths using the injector laser at SSRL's Gun Test Facility. Measurements were conducted using the fundamental ir wavelength at 1053 nanometers and harmonics at 526 nm and 263 nm with 3.4ps pulses (1/e{sup 2} full width intensity); ir measurements were also conducted with 850 ps pulses. Practical surfaces relevant to the laser system performance are emphasized. Damage onset was evidenced by an alteration of the specular reflection of a cw probe laser (650 nm) from the irradiated region of the target surface. For the case of stretched ir pulses, damage to a Nd:glass rod was observed to begin at a site within the bulk material and to progress back toward the incident surface.

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

    SciTech Connect (OSTI)

    Molvik, A W; Simonen, T C

    2009-07-17T23:59:59.000Z

    This report summarizes discussions and conclusions of the workshop to 'Assess The Mission and Technology of a Gas Dynamic Trap Neutron Source for Fusion Material and Component Testing and Qualification'. The workshop was held at LBNL, Berkeley, CA on March 12, 2009. Most workshop attendees have worked on magnetic mirror systems, several have worked on similar neutron source designs, and others are knowledgeable of materials, fusion component, and neutral beams The workshop focused on the gas dynamic trap DT Neutron Source (DTNS) concept being developed at the Budker Institute of Nuclear Physics (BINP) in Novosibirsk, Russia. The DTNS may be described as a line source of neutrons, in contrast to a spallation or a D-Lithium source with neutrons beaming from a point, or a tokamak volume source. The DTNS is a neutral beam driven linear plasma system with magnetic mirrors to confine the energetic deuterium and tritium beam injected ions, which produce the 14 MeV neutrons. The hot ions are imbedded in warm-background plasma, which traps the neutral atoms and provides both MHD and micro stability to the plasma. The 14 MeV neutron flux ranges typically at the level of 1 to 4 MW/m2.

  7. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.2.1a Command Rate: One Per Second

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.2.1a Command Rate: One Per Second. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.2.1a Command Rate

  8. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1c Initialize to Boot State After Reset

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1c Initialize to Boot State After. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1c Initialize to Boot State After Reset Size Code Indent No

  9. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1a Initialize to Boot State After Reset

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1a Initialize to Boot State After. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1a Initialize to Boot State After Reset Size Code Indent No

  10. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.4.1 Command to Jump Anywhere in Code

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.4.1 Command to Jump Anywhere in Code. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.4.1 Command to Jump

  11. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.4.1 Command to Jump Anywhere in Code

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.4.1 Command to Jump Anywhere in Code. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.4.1 Command to Jump

  12. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1d Initialize to Boot State After Reset

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1d Initialize to Boot State After. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1d Initialize to Boot State After Reset Size Code Indent No

  13. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.2.1a Command Rate: One Per Second

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.2.1a Command Rate: One Per Second. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Astronomy Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.2.1a Command Rate

  14. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.3a Counters for All Commands

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.3a Counters for All Commands Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.2.3.3a Counters for All

  15. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1b Initialize to Boot State After Reset

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1b Initialize to Boot State After. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.1b Initialize to Boot State After Reset Size Code Indent No

  16. COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.3 Commands to Reboot DCE FSW

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.3 Commands to Reboot DCE FSW Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.13 Component Test Results Requirement 5.1.1.3 Commands to Reboot DCE

  17. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.3 Commands to Re-boot DCE FSW

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.3 Commands to Re-boot DCE FSW Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.1.1.3 Commands to Re-boot DCE FSW Size Code Indent No. Document No. Rev

  18. COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.3a Counter for All Commands

    E-Print Network [OSTI]

    Colorado at Boulder, University of

    COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.3a Counter for All Commands Date. Brownsberger 2-13-01 The Center for Astrophysics and Space Astronomy Reviewed: Approved: COS DCE BOOT FSW v1 Initial Release COS DCE BOOT FSW v1.09 Component Test Results Requirement 5.2.3.3a Counter for All

  19. Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-6 test data report : thermal hydraulic results, Rev. 0.

    SciTech Connect (OSTI)

    Lomperski, S.; Farmer, M. T.; Kilsdonk, D.; Aeschlimann, B. (Nuclear Engineering Division)

    2011-06-28T23:59:59.000Z

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure? (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx} {phi} 30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength is being addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus measures the fracture strength of the crust while it is either at room temperature or above, the latter state being achieved with a heating element placed below the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the sixth water ingression test, designated SSWICS-6. This test investigated the quenching behavior of a fully oxidized PWR corium melt containing 15 wt% siliceous concrete at a system pressure of 1 bar absolute. The report includes a description of the test apparatus, the instrumentation used, plots of the recorded data, and some rudimentary data reduction to obtain an estimate of the heat flux from the corium to the overlying water pool.

  20. Results of scoping tests in corium-water thermal interactions in ex-vessel geometry

    SciTech Connect (OSTI)

    Spencer, B.W.; McUmber, L.; Sehgal, B.R.; Sienicki, J.J.; Squarer, D.

    1983-01-01T23:59:59.000Z

    Results of scoping tests are reported which were performed in the ANL/EPRI Corium Ex-vessel interactions (COREXIT) Facility located at ANL. These tests are examining issues related to containment loading (i.e., steam generation, H/sub 2/ production, and debris dispersal) for hypothetical LWR accidents that are postulated to progress to the point of molten corium breaching the vessel bottom head and entering the reactor cavity. The geometry selected for these tests is a 1 : 30 linear scale of the Zion PWR containment design in which the cavity is connected to the containment volume by an open tunnel through which pass the in-core detector guide tubes. The effects of the corium-water mixing modes were investigated in the first two tests in the series. In test CWTI-1 the molten corium was ejected into water which filled the cavity mockup volume to one-half the passageway height. In CWTI-2, the molten corium was dropped atop the refractory base in the cavity mockup without the presence of water, and water was injected atop the corium melt immediately afterward as per accumulator discharge. These tests have shown significant differences in fuel fragmentation, steam generation rate, hydrogen production, and fuel dispersal. Particularly noteworthy was the significant amount of dispersal of both water and corium debris from the cavity mockup due to the initially rapid steam generation rate in CWTI-1.

  1. Test plan for reactions between spent fuel and J-13 well water under unsaturated conditions

    SciTech Connect (OSTI)

    Finn, P.A.; Wronkiewicz, D.J.; Hoh, J.C.; Emery, J.W.; Hafenrichter, L.D.; Bates, J.K.

    1993-01-01T23:59:59.000Z

    The Yucca Mountain Site Characterization Project is evaluating the long-term performance of a high-level nuclear waste form, spent fuel from commercial reactors. Permanent disposal of the spent fuel is possible in a potential repository to be located in the volcanic tuff beds near Yucca Mountain, Nevada. During the post-containment period the spent fuel could be exposed to water condensation since of the cladding is assumed to fail during this time. Spent fuel leach (SFL) tests are designed to simulate and monitor the release of radionuclides from the spent fuel under this condition. This Test Plan addresses the anticipated conditions whereby spent fuel is contacted by small amounts of water that trickle through the spent fuel container. Two complentary test plans are presented, one to examine the reaction of spent fuel and J-13 well water under unsaturated conditions and the second to examine the reaction of unirradiated UO{sub 2} pellets and J-13 well water under unsaturated conditions. The former test plan examines the importance of the water content, the oxygen content as affected by radiolysis, the fuel burnup, fuel surface area, and temperature. The latter test plant examines the effect of the non-presence of Teflon in the test vessel.

  2. Test Report for Low Water Consumption Stainless Steel Water Closet Toilets

    E-Print Network [OSTI]

    Claridge, D. E.; Boecker, C. L.

    1994-01-01T23:59:59.000Z

    requirements as specified in the ASME Standard and is intended for use in new prison facilities. This toilet passed all performance criteria stated in the ASME Standard when operating with the 1.6 gallon flush valve at a static water pressure of 35 psi. However...

  3. Evaluating the Effects of Underground Nuclear Testing Below the Water Table on Groundwater and Radionuclide Migration in the

    E-Print Network [OSTI]

    Evaluating the Effects of Underground Nuclear Testing Below the Water Table on Groundwater, using FEHM, evaluate perturbed groundwater behavior associated with underground nuclear tests to an instantaneous pressurization event caused by a nuclear test when different permeability and porosity

  4. 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.

    2012-10-01T23:59:59.000Z

    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 ?m to 0.50 ?m 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 cell pieces was observed that was not seen on BZO/glass, and a CdS/CIGS sample displayed a small darkening and then flaking feature. Additionally, standard AlNi grid contact was less stable than thin Ni grid contact at T/RH ? 70/70. The edge sealant and moisture-blocking films were effective to block moisture ingress, as evidenced by the good stability of most CIGS solar cells and device components at T/RH = 85/70 for 704 h, and by preservation of the initial blue color on the RH indicator strips. The SSADT experiment is ongoing to be completed at T/RH = 85/85.

  5. Field Test Design Simulations of Pore-Water Extraction for the SX Tank Farm

    SciTech Connect (OSTI)

    Truex, Michael J.; Oostrom, Martinus

    2013-09-01T23:59:59.000Z

    A proof of principle test of pore water extraction is being performed by Washington River Protection Solutions for the U.S. Department of Energy, Office of River Protection. This test is being conducted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (HFFACO) (Ecology et al. 1989) Milestone M 045-20, and is described in RPP-PLAN-53808, 200 West Area Tank Farms Interim Measures Investigation Work Plan. To support design of this test, numerical simulations were conducted to help define equipment and operational parameters. The modeling effort builds from information collected in laboratory studies and from field characterization information collected at the test site near the Hanford Site 241-SX Tank Farm. Numerical simulations were used to evaluate pore-water extraction performance as a function of the test site properties and for the type of extraction well configuration that can be constructed using the direct-push installation technique. Output of simulations included rates of water and soil-gas production as a function of operational conditions for use in supporting field equipment design. The simulations also investigated the impact of subsurface heterogeneities in sediment properties and moisture distribution on pore-water extraction performance. Phenomena near the extraction well were also investigated because of their importance for pore-water extraction performance.

  6. Water Loss Test Results: West Main Canal United Irrigation District of Hidalgo County

    E-Print Network [OSTI]

    Leigh, E.; Fipps, G.

    IRRIGATION TECHNOLOGY CENTER Texas Cooperative Extension ? Texas Agricultural Experiment Station Texas A&M University System 1 Extension Associate, and Professor and Extension Agricultural Engineer... Table 3. Data for Test UN1: West Main District: United Irrigation District of Hidalgo County Test ID: UN1 Canal: West Main Lining Type: Lined Starting Water Span Widths: SG1: 11.21 ft, SG3: 11.24 ft, SG5: 11.26 ft Date...

  7. Pore Water Extraction Test Near 241-SX Tank Farm at the Hanford Site, Washington, USA

    SciTech Connect (OSTI)

    Eberlein, Susan J. [Washington River Protection Systems, Richland, WA (United States); Parker, Danny L. [Washington River Protection Systems, Richland, WA (United States); Tabor, Cynthia L. [Washington River Protection Systems, Richland, WA (United States); Holm, Melissa J. [Washington River Protection Systems, Richland, WA (United States)

    2013-11-11T23:59:59.000Z

    A proof-of-principle test is underway near the Hanford Site 241-SX Tank Farm. The test will evaluate a potential remediation technology that will use tank farm-deployable equipment to remove contaminated pore water from vadose zone soils. The test system was designed and built to address the constraints of working within a tank farm. Due to radioactive soil contamination and limitations in drilling near tanks, small-diameter direct push drilling techniques applicable to tank farms are being utilized for well placement. To address space and weight limitations in working around tanks and obstacles within tank farms, the above ground portions of the test system have been constructed to allow deployment flexibility. The test system utilizes low vacuum over a sealed well screen to establish flow into an extraction well. Extracted pore water is collected in a well sump,and then pumped to the surface using a small-diameter bladder pump.If pore water extraction using this system can be successfully demonstrated, it may be possible to target local contamination in the vadose zone around underground storage tanks. It is anticipated that the results of this proof-of-principle test will support future decision making regarding interim and final actions for soil contamination within the tank farms.

  8. An easily installable groundwater lysimeter to determine water balance components and hydraulic properties of peat soils Hydrology and Earth System Sciences, 7(1), 2332 (2003) EGU

    E-Print Network [OSTI]

    Boyer, Edmond

    2003-01-01T23:59:59.000Z

    properties of peat soils 23 Hydrology and Earth System Sciences, 7(1), 23­32 (2003) © EGU An easily installable groundwater lysimeter to determine water balance components and hydraulic properties of peat soils.Schwaerzel@TU-Berlin.de Abstract A simple method for the installation of groundwater lysimeters in peat soils was developed which

  9. Preliminary Modeling, Testing and Analysis of a Gas Tankless Water Heater

    SciTech Connect (OSTI)

    Burch, J.; Thornton, J.; Hoeschele, M.; Springer, D.; Rudd, A.

    2008-01-01T23:59:59.000Z

    Tankless water heaters offer significant energy savings over conventional storage-tank water heaters, because thermal losses to the environment are much less. Although standard test results are available to compare tankless heaters with storage tank heaters, actual savings depend on the draw details because energy to heat up the internal mass depends on the time since the last draw. To allow accurate efficiency estimates under any assumed draw pattern, a one-node model with heat exchanger mass is posed here. Key model parameters were determined from test data. Burner efficiency showed inconsistency between the two data sets analyzed. Model calculations show that efficiency with a realistic draw pattern is {approx}8% lower than that resulting from using only large {approx}40 liter draws, as specified in standard water-heater tests. The model is also used to indicate that adding a small tank controlled by the tankless heater ameliorates unacceptable oscillations that tankless with feedback control can experience with pre-heated water too hot for the minimum burner setting. The added tank also eliminates problematic low-flow cut-out and hot-water-delay, but it will slightly decrease efficiency. Future work includes model refinements and developing optimal protocols for parameter extraction.

  10. Department of Mechanical Engineering Spring 2012 Space Vehicle Water Drop Test and Vehicle Design

    E-Print Network [OSTI]

    Demirel, Melik C.

    PENNSTATE Department of Mechanical Engineering Spring 2012 Space Vehicle Water Drop Test and Vehicle Design Overview The team was tasked with modelling the accelerations and pressures of an impact of the scaled landing vehicle to reduce the accelerations and pressures of the vehicle. Objectives Provide

  11. NREL Tests Integrated Heat Pump Water Heater Performance in Different Climates (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-01-01T23:59:59.000Z

    This technical highlight describes NREL tests to capture information about heat pump performance across a wide range of ambient conditions for five heat pump water heaters (HPWH). These water heaters have the potential to significantly reduce water heater energy use relative to traditional electric resistance water heaters. These tests have provided detailed performance data for these appliances, which have been used to evaluate the cost of saved energy as a function of climate. The performance of HPWHs is dependent on ambient air temperature and humidity and the logic controlling the heat pump and the backup resistance heaters. The laboratory tests were designed to measure each unit's performance across a range of air conditions and determine the specific logic controlling the two heat sources, which has a large effect on the comfort of the users and the energy efficiency of the system. Unlike other types of water heaters, HPWHs are both influenced by and have an effect on their surroundings. Since these effects are complex and different for virtually every house and climate region, creating an accurate HPWH model from the data gathered during the laboratory tests was a main goal of the project. Using the results from NREL's laboratory tests, such as the Coefficient of Performance (COP) curves for different air conditions as shown in Figure 1, an existing HPWH model is being modified to produce more accurate whole-house simulations. This will allow the interactions between the HPWH and the home's heating and cooling system to be evaluated in detail, for any climate region. Once these modeling capabilities are in place, a realistic cost-benefit analysis can be performed for a HPWH installation anywhere in the country. An accurate HPWH model will help to quantify the savings associated with installing a HPWH in the place of a standard electric water heater. In most locations, HPWHs are not yet a cost-effective alternative to natural gas water heaters. The detailed system performance maps that were developed by this testing program will be used to: (1) Target regions of the country that would benefit most from this technology; (2) Identify improvements in current systems to maximize homeowner cost savings; and (3) Explore opportunities for development of advanced hot water heating systems.

  12. Review of International Methods of Test to Rate the Efficiency of Water Heaters

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    water heaters, heat-pump water heaters, and instantaneous (Wasted water Solar Heat pump water heater Australia/New

  13. Preoperational test report, cross-site transfer water flush system (POTP-001)

    SciTech Connect (OSTI)

    Parsons, G.L.

    1998-02-20T23:59:59.000Z

    This report documents the results of the testing performed per POTP-001, for the Cross-Site Transfer Water Flush System. (HNF-1552, Rev. 0) The Flush System consists of a 47,000 gallon tank (302C), a 20 hp pump, two 498kW heaters, a caustic addition pump, various valves, instruments, and piping. The purpose of this system is to provide flush water at 140 F, 140gpm, and pH 11-12 for the Cross-Site Transfer System operation.

  14. LWRS Fuels Pathway: Engineering Design and Fuels Pathway Initial Testing of the Hot Water Corrosion System

    SciTech Connect (OSTI)

    Dr. John Garnier; Dr. Kevin McHugh

    2012-09-01T23:59:59.000Z

    The Advanced LWR Nuclear Fuel Development R&D pathway performs strategic research focused on cladding designs leading to improved reactor core economics and safety margins. The research performed is to demonstrate the nuclear fuel technology advancements while satisfying safety and regulatory limits. These goals are met through rigorous testing and analysis. The nuclear fuel technology developed will assist in moving existing nuclear fuel technology to an improved level that would not be practical by industry acting independently. Strategic mission goals are to improve the scientific knowledge basis for understanding and predicting fundamental nuclear fuel and cladding performance in nuclear power plants, and to apply this information in the development of high-performance, high burn-up fuels. These will result in improved safety, cladding, integrity, and nuclear fuel cycle economics. To achieve these goals various methods for non-irradiated characterization testing of advanced cladding systems are needed. One such new test system is the Hot Water Corrosion System (HWCS) designed to develop new data for cladding performance assessment and material behavior under simulated off-normal reactor conditions. The HWCS is capable of exposing prototype rodlets to heated, high velocity water at elevated pressure for long periods of time (days, weeks, months). Water chemistry (dissolved oxygen, conductivity and pH) is continuously monitored. In addition, internal rodlet heaters inserted into cladding tubes are used to evaluate repeated thermal stressing and heat transfer characteristics of the prototype rodlets. In summary, the HWCS provides rapid ex-reactor evaluation of cladding designs in normal (flowing hot water) and off-normal (induced cladding stress), enabling engineering and manufacturing improvements to cladding designs before initiation of the more expensive and time consuming in-reactor irradiation testing.

  15. Performance of Charcoal Cookstoves for Haiti Part 1: Results from the Water Boiling Test

    SciTech Connect (OSTI)

    Booker, Kayje; Han, Tae Won; Granderson, Jessica; Jones, Jennifer; Lsk, Kathleen; Yang, Nina; Gadgil, Ashok

    2011-06-01T23:59:59.000Z

    In April 2010, a team of scientists and engineers from Lawrence Berkeley National Lab (LBNL) and UC Berkeley, with support from the Darfur Stoves Project (DSP), undertook a fact-finding mission to Haiti in order to assess needs and opportunities for cookstove intervention. Based on data collected from informal interviews with Haitians and NGOs, the team, Scott Sadlon, Robert Cheng, and Kayje Booker, identified and recommended stove testing and comparison as a high priority need that could be filled by LBNL. In response to that recommendation, five charcoal stoves were tested at the LBNL stove testing facility using a modified form of version 3 of the Shell Foundation Household Energy Project Water Boiling Test (WBT). The original protocol is available online. Stoves were tested for time to boil, thermal efficiency, specific fuel consumption, and emissions of CO, CO{sub 2}, and the ratio of CO/CO{sub 2}. In addition, Haitian user feedback and field observations over a subset of the stoves were combined with the experiences of the laboratory testing technicians to evaluate the usability of the stoves and their appropriateness for Haitian cooking. The laboratory results from emissions and efficiency testing and conclusions regarding usability of the stoves are presented in this report.

  16. Prediction of heat transfer for a supercritical water test with a four pin fuel bundle

    SciTech Connect (OSTI)

    Behnke, L. [RWE Power AG, Essen (Germany); Himmel, S.; Waata, C.; Schulenberg, T. [Forschungszentrum Karlsruhe GmbH, Institute for Nuclear and Energy Technologies, PO Box 3640, D-76021 Karlsruhe (Germany); Laurien, E. [University of Stuttgart (Germany)

    2006-07-01T23:59:59.000Z

    As a next step to validate prediction methods for core design of a Supercritical Water Cooled Reactor, a small, electrically heated fuel bundle with 4 pins is planned to be tested. This paper summarizes first heat transfer predictions for such a test, which were performed based on supercritical and subcritical sub-channel analyses. For heat transfer under supercritical pressure conditions, the sub-channel code STAFAS has been applied, which had been tested successfully already for a supercritical water reactor design. Design studies with different assembly box sizes at a given pin diameter and pitch have been performed to optimize the coolant temperature distribution. With a fuel pin outer diameter of 10 mm and a pitch to diameter ratio of 1.15, an optimum inner width of the assembly box was determined to be 24 mm. Coolant and cladding surface temperatures to be expected at subcritical pressure conditions have been predicted with the sub-channel code MATRA. As, different from typical PWR or BWR conditions, a dryout has been foreseen for the tests, this code had to be extended to include suitable dryout criteria as well as post dryout heat transfer correlations at higher enthalpies and pressures. Different from PWR or BWR design, the cladding surface temperature of fuel pins in supercritical water reactors can vary significantly around the circumference of each pin, causing bending towards its hotter side which, in turn, can cause additional sub-channel heat-up and thus additional thermal bending of the pin. To avoid a thermal instability by this effect, a sensitivity study with respect to thermal bending of fuel pins has been performed, which determines the minimum number of grid spacers needed for this test. (authors)

  17. Abstract--Commercial-off-the-shelf (COTS) components were tested over the Martian temperature range for their use in a

    E-Print Network [OSTI]

    Kuhn, William B.

    supplies and multi meter using IEEE GPIB- 488 standard for data acquisition. Measurements were then taken TESTING Cryogenic cooling is a process of bringing down the temperature of the DUT (Device under Test to vapor state and thus the idea behind cryogenic cooling is to make a liquid vaporize and thus cool

  18. Design and testing of a deep sea formation water and temeperature sampling probe for the Ocean Drilling Program

    E-Print Network [OSTI]

    Fisseler, Patrick James

    2012-06-07T23:59:59.000Z

    . Components were then fabricated by a local machine shop. All components under went quality inspection and were then assembled. Full scale testing at the Ocean Drilling Programs Annex is the next step. If successful, the probe is to undergo sea trials...

  19. Developing an Instrumentation Package for in-Water Testing of Marine Hydrokinetic Energy Devices: Preprint

    SciTech Connect (OSTI)

    Nelson, E.

    2010-08-01T23:59:59.000Z

    The ocean-energy industry is still in its infancy and device developers have provided their own equipment and procedures for testing. Currently, no testing standards exist for ocean energy devices in the United States. Furthermore, as prototype devices move from the test tank to in-water testing, the logistical challenges and costs grow exponentially. Development of a common instrumentation package that can be moved from device to device is one means of reducing testing costs and providing normalized data to the industry as a whole. As a first step, the U.S. National Renewable Energy Laboratory (NREL) has initiated an effort to develop an instrumentation package to provide a tool to allow common measurements across various ocean energy devices. The effort is summarized in this paper. First, we present the current status of ocean energy devices. We then review the experiences of the wind industry in its development of the instrumentation package and discuss how they can be applied in the ocean environment. Next, the challenges that will be addressed in the development of the ocean instrumentation package are discussed. For example, the instrument package must be highly adaptable to fit a large array of devices but still conduct common measurements. Finally, some possible system configurations are outlined followed by input from the industry regarding its measurement needs, lessons learned from prior testing, and other ideas.

  20. 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

    2008-02-25T23:59:59.000Z

    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.

  1. A Test Facility for the International Linear Collider at SLAC End Station A, for Prototypes of Beam Delivery and IR Components

    SciTech Connect (OSTI)

    Woods, M.; Erickson, R.; Frisch, J.; Hast, C.; Jobe, R.K.; Keller, L.; Markiewicz, T.; Maruyama, T.; McCormick, D.; Nelson, J.; Nelson, T.; Phinney, N.; Raubenheimer, T.; Ross, M.; Seryi, A.; Smith, S.; Szalata, Z.; Tenenbaum, P.; Woodley, M.; /SLAC; Angal-Kalinin, D.; Beard, C.; /Daresbury /CERN /DESY /KEK, Tsukuba /LLNL, Livermore /Lancaster U.

    2005-05-23T23:59:59.000Z

    The SLAC Linac can deliver damped bunches with ILC parameters for bunch charge and bunch length to End Station A. A 10Hz beam at 28.5 GeV energy can be delivered there, parasitic with PEP-II operation. We plan to use this facility to test prototype components of the Beam Delivery System and Interaction Region. We discuss our plans for this ILC Test Facility and preparations for carrying out experiments related to collimator wakefields and energy spectrometers. We also plan an interaction region mockup to investigate effects from backgrounds and beam-induced electromagnetic interference.

  2. Testing the Adequacy of Simple Water Models at the Opposite Ends of the Phase Diagram

    SciTech Connect (OSTI)

    Baranayai, A. [Eotvos University, Budapest, Hungary; Bartok, A. [Eotvos University, Budapest, Hungary; Chialvo, Ariel A [ORNL

    2007-01-01T23:59:59.000Z

    The transferability of a few simple rigid non-polarizable water models were tested by Gibbs Ensemble Monte Carlo simulations to predict their vapor-liquid phase equilibria, and by isothermal-isobaric (Parrinello-Rahman) Monte Carlo simulations of the 13 known crystalline phases of ice. The temperature dependence of the corresponding second virial coefficients was also determined and then used to test the internal consistency of the simulated vapor-phase densities. The model predictions appear satisfactory for liquid water for ambient conditions, but they fail to mimic accurately the properties of the ice polymorphs and the orthobaric vapor phase. The major shortcomings of the models were in the overestimation by a factor of two ({approx}4-6 kJ/mol) of the internal energy difference between the high-pressure ice phases and the hexagonal phase. This unacceptable discrepancy is caused by the parameterization to reproduce the density of liquid water at ambient conditions, that accounts for the significant polarization effects in the condensed phases in terms of augmented dipole moments, with the consequent detrimental effect on the estimations of the vapor-phase properties.

  3. Review of International Methods of Test to Rate the Efficiency of Water Heaters

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    energy multiplier Distribution losses Smart controls Wasted water Solar Heat pump water heater Australia/

  4. SUPERCRITICAL WATER PARTIAL OXIDATION PHASE I - PILOT-SCALE TESTING / FEASIBILITY STUDIES FINAL REPORT

    SciTech Connect (OSTI)

    SPRITZER,M; HONG,G

    2005-01-01T23:59:59.000Z

    Under Cooperative Agreement No. DE-FC36-00GO10529 for the Department of Energy, General Atomics (GA) is developing Supercritical Water Partial Oxidation (SWPO) as a means of producing hydrogen from low-grade biomass and other waste feeds. The Phase I Pilot-scale Testing/Feasibility Studies have been successfully completed and the results of that effort are described in this report. The Key potential advantages of the SWPO process is the use of partial oxidation in-situ to rapidly heat the gasification medium, resulting in less char formation and improved hydrogen yield. Another major advantage is that the high-pressure, high-density aqueous environment is ideal for reaching and gasifying organics of all types. The high water content of the medium encourages formation of hydrogen and hydrogen-rich products and is especially compatible with high water content feeds such as biomass materials. The high water content of the medium is also effective for gasification of hydrogen-poor materials such as coal. A versatile pilot plant for exploring gasification in supercritical water has been established at GA's facilities in San Diego. The Phase I testing of the SWPO process with wood and ethanol mixtures demonstrated gasification efficiencies of about 90%, comparable to those found in prior laboratory-scale SCW gasification work carreid out at the University of Hawaii at Manoa (UHM) as well as other biomass gasification experience with conventional gasifiers. As in the prior work at UHM, a significant amount of the hydrogen found in the gas phase products is derived from the water/steam matrix. The studies at UHM utilized an indirectly heated gasifier with an acitvated carbon catalyst. In contrast, the GA studies utilized a directly heated gasifier without catalyst, plus a surrogate waste fuel. Attainment of comparable gasification efficiencies without catalysis is an important advancement for the GA process, and opens the way for efficient hydrogen production from low-value, dirty feed materials. The Phase I results indicate that a practical means to overcome limitations on biomass slurry feed concentration and preheat temperatuare is to coprocess an auxiliary high heating value material. SWPO coprocessing of tow hgih-water content wastes, partially dewatered sewage sludge and trap grease, yields a scenario for the production of hydrogen at highly competitive prices. It is estimated that there are hundreds if not thousands of potential sites for this technology across the US and worldwide.

  5. Baseline risk assessment of the perched water system at the INEL test reactor area

    SciTech Connect (OSTI)

    Gordon, J.W.; Sinton, P.O. (Dames Moore, Denver, CO (United States)); Jensen, N. (DOE, Idaho Falls, ID (United States)); McCormick, S. (Idaho National Engineering Lab., Idaho Falls, ID (United States))

    1993-01-01T23:59:59.000Z

    A baseline health risk assessment (HRA) was prepared to evaluate potential risks to human health and the environment posed by the Perched Water System (PWS) at the Test Reactor Area (TRA). The PWS has been designated Operable Unit 2-12, one of the 13 operable units identified at TRA. During the period from 1962 to 1990, a total of 6770 million gal of water were discharged from the TRA to unlined surface ponds. Wastewater discharged to the surface ponds at TRA percolates downward through the surficial alluvium and the underlying basalt bedrock. A resulting shallow perched water zone has formed at the interface between the surficial sediments and the underlying basalt. Further downward movement of groundwater is again impeded by a low-permeability layer of silt, clay, and sand encountered at a depth of [approximately]150 ft. The deep perched water zone occurs on top of this low-permeability interbed. An evaluation was made as to whether potential risks for the PWS could justify implementing a remedial action. The risk evaluation consisted of two parts, the human health evaluation and the ecological evaluation.

  6. SUPERCRITICAL WATER PARTIAL OXIDATION PHASE I - PILOT-SCALE TESTING/FEASIBILTY SUDIES FINAL REPORT

    SciTech Connect (OSTI)

    SPRITZER.M; HONG,G

    2005-01-01T23:59:59.000Z

    General Atomics (GA) is developing Supercritical Water Partial Oxidation (SWPO) as a means of producing hydrogen from low-grade biomass and other waste feeds. The Phase I Pilot-scale Testing/Feasibility Studies have been successfully completed and the results of that effort are described in this report. The key potential advantage of the SWPO process is the use of partial oxidation in-situ to rapidly heat the gasification medium, resulting in less char formation and improved hydrogen yield. Another major advantage is that the high-pressure, high-density aqueous environment is ideal for reacting and gasifying organics of all types. The high water content of the medium encourages formation of hydrogen and hydrogen-rich products and is especially compatible with high water content feeds such as biomass materials. The high water content of the medium is also effective for gasification of hydrogen-poor materials such as coal. A versatile pilot plant for exploring gasification in supercritical water has been established at GA's facilities in San Diego. The Phase I testing of the SWPO process with wood and ethanol mixtures demonstrated gasification efficiencies of about 90%, comparable to those found in prior laboratory-scale SCW gasification work carried out at the University of Hawaii at Manoa (UHM), as well as other biomass gasification experience with conventional gasifiers. As in the prior work at UHM, a significant amount of the hydrogen found in the gas phase products is derived from the water/steam matrix. The studies at UHM utilized an indirectly heated gasifier with an activated carbon catalyst. In contrast, the GA studies utilized a directly heated gasifier without catalyst, plus a surrogate waste fuel. Attainment of comparable gasification efficiencies without catalysis is an important advancement for the GA process, and opens the way for efficient hydrogen production from low-value, dirty feed materials. The Phase I results indicate that a practical means to overcome limitations on biomass slurry feed concentration and preheat temperature is to coprocess an auxiliary high heating value material. SWPO coprocessing of two high-water content wastes, partially dewatered sewage sludge and trap grease, yields a scenario for the production of hydrogen at highly competitive prices. It is estimated that there are hundreds if not thousands of potential sites for this technology across the US and worldwide. The economics for plants processing 40 tpd sewage sludge solids augmented with grease trap waste are favorable over a significant range of cost parameters such as sludge disposal credit and capital financing. Hydrogen production costs for SWPO plants of this size are projected to be about $3/GJ or less. Economics may be further improved by future developments such as pumping of higher solids content sludges and improved gasifier nozzle designs to reduce char and improve hydrogen yields. The easiest market entry for SWPO is expected to be direct sales to municipal wastewater treatment plants for use with sewage sludge in conjunction with trap grease, as both of these wastes are ubiquitous and have reasonably well-defined negative value (i.e., the process can take credit for reduction of well-defined disposal costs for these streams). Additionally, waste grease is frequently recovered at municipal wastewater treatment plants where it is already contaminated with sewage. SWPO should also be favorable to other market applications in which low or negative value, high water content biomass is available in conjunction with a low or negative value fuel material. For biomass slurries primary candidates are sewage sludge, manure sludge, and shredded and/or composted organic municipal solid waste (MSW) slurries. For the high heating value stream primary candidates are trap grease, waste plastic or rubber slurries, and coal or coke slurries. Phase II of the SWPO program will be focused on verifying process improvements identified during Phase I, and then performing extended duration testing with the GA pilot plant. Tests of at least 1

  7. 2014-06-27 Issuance: Test Procedures for Residential and Commercial Water Heaters; Final Rule

    Broader source: Energy.gov [DOE]

    This document is a pre-publication Federal Register final rule regarding test procedures for residential and commercial water heaters, as issued by the Deputy Assistant Secretary for Energy Efficiency on June 27, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  8. Complete characterization of the water dimer vibrational ground state and testing the VRT(ASP-W)III,

    E-Print Network [OSTI]

    Cohen, Ronald C.

    Complete characterization of the water dimer vibrational ground state and testing the VRT(ASP-W)III, SAPT-5st, and VRT(MCY-5f) surfaces FRANK N. KEUTSCH1 , NIR GOLDMAN2 , HEATHER A. HARKER3 , CLAUDE of the water dimer very well. The VRT(MCY-5f) and especially the VRT(ASP-W)III potentials show larger

  9. Poster: Building a test-bed for wireless sensor networking for under-water oil and gas installations

    E-Print Network [OSTI]

    Zhou, Shengli

    . Initially we are building a laboratory in a large water tank. Later we will cooperate with an oil and gasPoster: Building a test-bed for wireless sensor networking for under-water oil and gas@ifi.uio.no 1 Introduction and background When the oil and gas industry moves its production facilities

  10. Treatability test of a stacked-tray air stripper for VOC in water

    SciTech Connect (OSTI)

    Pico, T., LLNL

    1998-04-01T23:59:59.000Z

    A common strategy for hydraulic containment and mass removal at VOC contaminated sites is `pump and treat (P&T)`. In P&T operations, contaminated ground water is pumped from wells, treated above ground, and discharged. Many P&T remediation systems at VOC sites rely on air stripping technology because VOCs are easily transferred to the vapor phase. In stacked-tray air strippers, contaminated water is aerated while it flows down through a series of trays. System operations at LLNL are strictly regulated by the California and federal Environmental Protection Agencies (Cal/EPA and EPA), the Bay Area Air Quality Management District (BAAQMD), the California Regional Water Quality Control Board (RWQCB) and the Department of Toxic Substances Control (DTSC). These agencies set discharge limits, require performance monitoring, and assess penalties for non-compliance. National laboratories are also subject to scrutiny by the public and other government agencies. This extensive oversight makes it necessary to accurately predict field treatment performance at new extraction locations to ensure compliance with all requirements prior to facility activation. This paper presents treatability test results for a stacked- tray air stripper conducted at LLNL and compares them to the vendor`s modeling software results.

  11. How to Make Appliance Standards Work: Improving Energy and Water Efficiency Test Procedures

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    efficiency of commercial water heaters and hot water supplyheat pump water heaters). http://edocket.access.gpo.gov/2004/CSA 4.3- 2004 Gas Water Heaters - Volume III, Storage

  12. Barrier erosion control test plan: Gravel mulch, vegetation, and soil water interactions

    SciTech Connect (OSTI)

    Waugh, W.J.; Link, S.O. (Pacific Northwest Lab., Richland, WA (USA))

    1988-07-01T23:59:59.000Z

    Soil erosion could reduce the water storage capacity of barriers that have been proposed for the disposal of near-surface waste at the US Department of Energy's Hanford Site. Gravel mixed into the top soil surface may create a self-healing veneer that greatly retards soil loss. However, gravel admixtures may also enhance infiltration of rainwater, suppress plant growth and water extraction, and lead to the leaching of underlying waste. This report describes plans for two experiments that were designed to test hypotheses concerning the interactive effects of surface gravel admixtures, revegetation, and enhanced precipitation on soil water balance and plant abundance. The first experiment is a factorial field plot set up on the site selected as a soil borrow area for the eventual construction of barriers. The treatments, arranged in a a split-split-plot design structure, include two densities of gravel admix, a mixture of native and introduced grasses, and irrigation to simulate a wetter climate. Changes in soil water storage and plant cover are monitored with neutron moisture probes and point intercept sampling, respectively. The second experiment consists of an array of 80 lysimeters containing several different barrier prototypes. Surface treatments are similar to the field-plot experiment. Drainage is collected from a valve at the base of each lysimeter tube, and evapotranspiration is estimated by subtraction. The lysimeters are also designed to be coupled to a whole-plant gas exchange system that will be used to conduct controlled experiments on evapotranspiration for modeling purposes. 56 refs., 6 figs., 8 tabs.

  13. Development of a vortex combustor (VC) for space/water heating applications (combustion tests). Final report

    SciTech Connect (OSTI)

    Fu, T.T. [Naval Civil Engineering Lab., Port Hueneme, CA (United States); Nieh, S. [Catholic Univ. of America, Washington, DC (United States). Combustion and Multiphase Flows Lab.

    1990-11-01T23:59:59.000Z

    This is the final report for Interagency Agreement DE-AI22-87PC79660 on ``Combustion Test`` for vortex combustor (VC) development for commercial applications. The work culminated in the successful demonstration of a 2 MB/H proof-of-concept (POC) model firing coal-water fuel (CWF). This development is concerned with a new concept in combustion, and was a general lack of relevant information. The work therefore began (in addition to the companion cold flow modeling study) with the design and test of two subscale models (0.15 and 0.3 MB/H) and one full scale model (3 MB/H) to obtain the needed information. With the experience gained, the 2 MB/H POC model was then designed and demonstrated. Although, these models were designed somewhat differently from one another, they all performed well and demonstrated the superiority of the concept. In summary, test results have shown that VC can be fired on several coal fuels (CWF, dry ultrafine coal, utility grind pulverized coal) at high combustion efficiency (>99%), high firing intensity (up to 0.44 MB/H-ft{sup 3}), and at temperatures sufficiently low or dry ash removal. The combustion process is completed totally inside the combustor. Conventional combustion enhancement techniques such as: preheating (air and/or fuel), pre-combustion, and post combustion are not needed.

  14. Development of a vortex combustor (VC) for space/water heating applications (combustion tests)

    SciTech Connect (OSTI)

    Fu, T.T. (Naval Civil Engineering Lab., Port Hueneme, CA (United States)); Nieh, S. (Catholic Univ. of America, Washington, DC (United States). Combustion and Multiphase Flows Lab.)

    1990-11-01T23:59:59.000Z

    This is the final report for Interagency Agreement DE-AI22-87PC79660 on Combustion Test'' for vortex combustor (VC) development for commercial applications. The work culminated in the successful demonstration of a 2 MB/H proof-of-concept (POC) model firing coal-water fuel (CWF). This development is concerned with a new concept in combustion, and was a general lack of relevant information. The work therefore began (in addition to the companion cold flow modeling study) with the design and test of two subscale models (0.15 and 0.3 MB/H) and one full scale model (3 MB/H) to obtain the needed information. With the experience gained, the 2 MB/H POC model was then designed and demonstrated. Although, these models were designed somewhat differently from one another, they all performed well and demonstrated the superiority of the concept. In summary, test results have shown that VC can be fired on several coal fuels (CWF, dry ultrafine coal, utility grind pulverized coal) at high combustion efficiency (>99%), high firing intensity (up to 0.44 MB/H-ft[sup 3]), and at temperatures sufficiently low or dry ash removal. The combustion process is completed totally inside the combustor. Conventional combustion enhancement techniques such as: preheating (air and/or fuel), pre-combustion, and post combustion are not needed.

  15. Superclean coal-water slurry combustion testing in an oil-fired boiler

    SciTech Connect (OSTI)

    Miller, B.G.; Pisupati, S.V.; Poe, R.L.; Morrison, J.L.; Xie, J.; Walsh, P.M.; Wincek, R.T.; Clark, D.A.; Scaroni, A.W.

    1993-04-21T23:59:59.000Z

    The Pennsylvania State University is conducting a superclean coal-water slurry (SCCWS) program for the United States Department of Energy (DOE) and the Commonwealth of Pennsylvania with the objective of determining the capability of effectively firing SCCWS in an industrial boiler designed for heavy fuel oil. Penn State has entered into a cooperative agreement with DOE to determine if SCCWS (a fuel containing coal with 3.0 wt.% ash and 0.9 wt.% sulfur) can effectively be burned in a heavy fuel oil-designed industrial boiler without adverse impact on boiler rating, maintainability, reliability, and availability. The project will provide information on the design of new systems specifically configured to fire these clean coal-based fuels. The project consists of four phases: (1) design, permitting, and test planning, (2) construction and start up, (3) demonstration and evaluation (1,000-hour demonstration), and (4) program expansion (additional 1,000 hours of testing). The boiler testing wig determine if the SCCWS combustion characteristics, heat release rate, fouling and slagging behavior, corrosion and erosion limits, and fuel transport, storage, and handling characteristics can be accommodated in an oil-designed boiler system. In addition, the proof-of-concept demonstration will generate data to determine how the properties of SCCWS and its parent coal affect boiler performance. Economic factors associated with retrofitting boilers will be identified

  16. 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

    2009-11-23T23:59:59.000Z

    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.

  17. Investigation of CTBT OSI Radionuclide Techniques at the DILUTED WATERS Nuclear Test Site

    SciTech Connect (OSTI)

    Baciak, James E.; Milbrath, Brian D.; Detwiler, Rebecca S.; Kirkham, Randy R.; Keillor, Martin E.; Lepel, Elwood A.; Seifert, Allen; Emer, Dudley; Floyd, Michael

    2012-11-01T23:59:59.000Z

    Under the Comprehensive Nuclear-Test-Ban Treaty (CTBT), a verification regime that includes the ability to conduct an On-Site Inspection (OSI) will be established. The Treaty allows for an OSI to include many techniques, including the radionuclide techniques of gamma radiation surveying and spectrometry and environmental sampling and analysis. Such radioactivity detection techniques can provide the “smoking gun” evidence that a nuclear test has occurred through the detection and quantification of indicative recent fission products. An OSI faces restrictions in time and manpower, as dictated by the Treaty; not to mention possible logistics difficulties due to the location and climate of the suspected explosion site. It is thus necessary to have a good understanding of the possible source term an OSI will encounter and the proper techniques that will be necessary for an effective OSI regime. One of the challenges during an OSI is to locate radioactive debris that has escaped an underground nuclear explosion (UNE) and settled on the surface near and downwind of ground zero. To support the understanding and selection of sampling and survey techniques for use in an OSI, we are currently designing an experiment, the Particulate Release Experiment (PRex), to simulate a small-scale vent from an underground nuclear explosion. PRex will occur at the Nevada National Security Site (NNSS). The project is conducted under the National Center for Nuclear Security (NCNS) funded by the National Nuclear Security Agency (NNSA). Prior to the release experiment, scheduled for Spring of 2013, the project scheduled a number of activities at the NNSS to prepare for the release experiment as well as to utilize the nuclear testing past of the NNSS for the development of OSI techniques for CTBT. One such activity—the focus of this report—was a survey and sampling campaign at the site of an old UNE that vented: DILUTED WATERS. Activities at DILUTED WATERS included vehicle-based survey, in situ measurements with high-purity germanium (HPGe) and hand-held LaBr3 systems, soil sampling with a variety of tools, and laboratory gamma spectrometric analysis of those samples. A further benefit of the measurement campaign was to gain familiarity with the many logistical aspects of performing radiological field work at NNSS ahead of the PRex. Many practical lessons concerning the proper methodologies and logistics of using the surveying and sampling equipment were noted. These Lessons Learned are compiled together in Appendix A. The vehicle-based survey was successful in that it found a previously unknown hotspot (determined to be 232Th) while it demonstrated that a better method for keeping a serpentine track without staking was needed. Some of the soil sampling equipment was found to be impractical for the application, though core sampling would not be the correct way to take soil samples for a fresh vent deposit (as opposed to an old site like DILUTED WATERS). Due to the site’s age, 137Cs was the only fission radioisotope identified, though others were searched for. While not enough samples were taken and analyzed to definitively link the 137Cs to DILUTED WATERS as opposed to other NNSS activities, results were consistent with the historical DILUTED WATERS plume. MDAs were compared for soil sampling and in situ measurements.

  18. D.C. Water Resources Research Institute Annual Technical Report

    E-Print Network [OSTI]

    projects that address the three components of integrated urban water system: storm water runoff and sewer developing and maintaining new environmental quality testing and modeling tools to advance water researchD.C. Water Resources Research Institute Annual Technical Report FY 2013 D.C. Water Resources

  19. How to Make Appliance Standards Work: Improving Energy and Water Efficiency Test Procedures

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    Volume III, Storage Water Heaters With Input Ratings AboveVolume III, Storage Water Heaters With Input Ratings AboveVolume III, Storage Water Heaters With Input Ratings Above

  20. Review of International Methods of Test to Rate the Efficiency of Water Heaters

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    gas and electric storage water heaters, heat-pump watersmall gas-fired storage water heaters with a large burner.such as electric storage water heaters, the comparison of

  1. Superclean coal-water slurry combustion testing in an oil-fired boiler

    SciTech Connect (OSTI)

    Miller, B.G.; Schobert, H.H.

    1990-09-28T23:59:59.000Z

    The Pennsylvania State University is conducting a superclean coal-water slurry (SCCWS) program with the objective of demonstrating the capability of effectively firing SCCWS in industrial boilers designed for oil. Penn State has entered into a cooperative agreement with DOE to determine if SCCWS (a fuel containing coal with less than 3.0% ash and 0.9% sulfur) can effectively be burned in oil-designed industrial boilers without adverse impact on boiler rating, maintainability, reliability and availability. The project will provide information on the design of new systems specifically configured to fire these clean coal-based fuels. The project consists of three phases: (1) design, permitting, and test planning, (2) construction and start up, and (3) demonstration and evaluation. The boiler testing will determine if the SCCWS combustion characteristics, heat release rate, fouling and slagging behavior, corrosion and erosion limits, and fuel transport, storage, and handling characteristics can be accommodated in an oil-designed boiler system. In addition, the proof-of-concept demonstration will generate data to determine how the properties of SCCWS and its parent coal affect boiler performance. Economic factors associated with retrofitting and operating boilers will be identified to assess the viability of future oil-to-coal retrofits. Progress is reported. 7 refs., 7 figs., 1 tab.

  2. Proposed and existing passive and inherent safety-related structures, systems, and components (building blocks) for advanced light-water reactors

    SciTech Connect (OSTI)

    Forsberg, C.W.; Moses, D.L.; Lewis, E.B.; Gibson, R.; Pearson, R.; Reich, W.J.; Murphy, G.A.; Staunton, R.H.; Kohn, W.E.

    1989-10-01T23:59:59.000Z

    A nuclear power plant is composed of many structures, systems, and components (SSCs). Examples include emergency core cooling systems, feedwater systems, and electrical systems. The design of a reactor consists of combining various SSCs (building blocks) into an integrated plant design. A new reactor design is the result of combining old SSCs in new ways or use of new SSCs. This report identifies, describes, and characterizes SSCs with passive and inherent features that can be used to assure safety in light-water reactors. Existing, proposed, and speculative technologies are described. The following approaches were used to identify the technologies: world technical literature searches, world patent searches, and discussions with universities, national laboratories and industrial vendors. 214 refs., 105 figs., 26 tabs.

  3. OECD MCCI Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-3 test data report : thermal Hydraulic results, Rev. 0 February 19, 2003.

    SciTech Connect (OSTI)

    Lomperski, S.; Farmer, M. T.; Kilsdonk, D.; Aeschlimann, B. (Nuclear Engineering Division)

    2011-05-23T23:59:59.000Z

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx}{phi}30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the third water ingression test, designated SSWICS-3. This test investigated the quenching behavior of a fully oxidized PWR corium melt containing 8 wt% limestone/common sand concrete at a system pressure of 4 bar absolute. The report includes a description of the test apparatus, the instrumentation used, plots of the recorded data, and some rudimentary data reduction to obtain an estimate of the heat flux from the corium to the overlying water pool.

  4. Transparency of 0.2% GdCl3 Doped Water in a Stainless Steel Test Environment

    E-Print Network [OSTI]

    W. Coleman; A. Bernstein; S. Dazeley; R. Svoboda

    2008-06-11T23:59:59.000Z

    The possibility of neutron and neutrino detection using water Cerenkov detectors doped with gadolinium holds the promise of constructing very large high-efficiency detectors with wide-ranging application in basic science and national security. This study addressed a major concern regarding the feasibility of such detectors: the transparency of the doped water to the ultraviolet Cerenkov light. We report on experiments conducted using a 19-meter water transparency measuring instrument and associated materials test tank. Sensitive measurements of the transparency of water doped with 0.2% GdCl3 at 337nm, 400nm and 420nm were made using this instrument. These measurements indicate that GdCl3 is not an appropriate dopant in stainless steel constructed water Cerenkov detectors.

  5. OECD MCCI project Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-1 test data report : thermal hydraulic results. Rev. 0 September 20, 2002.

    SciTech Connect (OSTI)

    Lomperski, S.; Farmer, M. T.; Kilsdonk, D. J.; Aeschlimann, R. W.; Basu, S. (Nuclear Engineering Division); (NRC)

    2011-05-23T23:59:59.000Z

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx}{phi}30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the first water ingression test, designated SSWICS-1. The report includes a description of the test apparatus, the instrumentation used, plots of the recorded data, and some rudimentary data reduction to obtain an estimate of the heat flux from the corium to the overlying water pool.

  6. OECD MMCI Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-2 test data report : thermal hydraulic results, Rev. 0 September 20, 2002.

    SciTech Connect (OSTI)

    Lomperski, S.; Farmer, M. T.; Kilsdonk, D. J.; Aeschlimann, R. W.; Basu, S. (Nuclear Engineering Division); (NRC)

    2011-05-23T23:59:59.000Z

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx}{phi}30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the second water ingression test, designated SSWICS-2. The report includes a description of the test apparatus, the instrumentation used, plots of the recorded data, and some rudimentary data reduction to obtain an estimate of the heat flux from the corium to the overlying water pool.

  7. A focused liquid jet formed by a water hammer in a test tube

    E-Print Network [OSTI]

    Kiyama, Akihito; Ando, Keita; Kameda, Masaharu

    2015-01-01T23:59:59.000Z

    We investigate motion of a gas-liquid interface in a test tube induced by a large acceleration via impulsive force. We conduct simple experiments in which the tube partially filled with a liquid falls under gravity and impacts a rigid floor. A curved gas-liquid interface inside the tube reverses and eventually forms an elongated jet (i.e. the so-called a focused jet). In our experiments, there arises either vibration of the interface or increment in the velocity of a liquid jet accompanied by the onset of cavitation in the liquid column. These phenomena cannot be explained by considering pressure impulse in a classical potential flow analysis, which does not account for finite speeds of sound as well as phase change. Here we model such water-hammer events as a result of one-dimensional pressure wave propagation and its interaction with boundaries through acoustic impedance mismatching. The method of characteristics is applied to describe pressure wave interactions and the subsequent cavitation. The proposed m...

  8. VARIATIONS IN RADON-222 IN SOIL AND GROUND WATER AT THE NEVADA TEST SITE

    E-Print Network [OSTI]

    Wollenberg, H.

    2010-01-01T23:59:59.000Z

    water 222Rn by gamma-ray spectrometry. There was no clearlyradioelement content by gamma-ray spectrometry. Results are

  9. Review of International Methods of Test to Rate the Efficiency of Water Heaters

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    air source to be added Discharge Includes: Source energy multiplier Distribution losses Smart controls Wasted water Solar Heat pump

  10. Development and Field Testing of a Hybrid Water Heating and Dehumidification Appliance

    E-Print Network [OSTI]

    Aaron K. Ball; Chip Ferguson; William Mcdaniel

    standard system is replaced by a Heat Pump Water Heater (HPWH), the performance can be increased by 140

  11. Piping flow erosion in water retaining structures: inferring erosion rates from hole erosion tests and quantifying the failure time

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Piping flow erosion in water retaining structures: inferring erosion rates from hole erosion tests-en-Provence Cedex 5, France E-mail: stephane.bonelli@cemagref.fr Abstract The piping flow erosion process, involving structures. Such a pipe can be imputed to roots or burrows. The coefficient of erosion must be known in order

  12. Review of International Methods of Test to Rate the Efficiency of Water Heaters

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    Water Heaters Jim Lutz, Lawrence Berkeley National Laboratory January 25, 2011 The American Society of Heating, Refrigerating, and Air-conditioning Engineers (ASHRAE) Standards

  13. Ground-water data for the Nevada Test Site 1992, and for selected other areas in South-Central Nevada, 1952--1992

    SciTech Connect (OSTI)

    NONE

    1992-12-31T23:59:59.000Z

    Ground-water data collected from wells and test holes at and in the vicinity of the Nevada Test Site have been compiled in a recently released report. These data were collected by the US Geological Survey, Department of the Interior, in support of the US Department of Energy, Environmental Restoration and Hydrologic Resources Management Programs. Depth-to-water measurements were made at 53 sites at the Nevada Test Site from October 1, 1991, to September 30, 1992, and at 60 sites in the vicinity of the Nevada Test Site from 1952 to September 30, 1992. For water year 1992, depth to water ranged from 288 to 2,213 feet below land surface at the Nevada Test Site and from 22 to 1,460 feet below land surface at sites in the vicinity of the Nevada Test Site. Total ground-water withdrawal data compiled for 12 wells at the Nevada Test Site during calendar year 1992 was more than 400 million gallons. Tritium concentrations in water samples collected from five test holes at the Nevada Test Site in water year 1992 did not exceed the US Environmental Protection Agency drinking, water limit.

  14. 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

    2014-10-01T23:59:59.000Z

    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.

  15. Experimental investigation of a flow monitoring instrument in an upper plenum of an air-water reflood test facility. [PWR

    SciTech Connect (OSTI)

    Combs, S.K.; Hardy, J.E.

    1980-01-01T23:59:59.000Z

    Instrumentation was developed for measuring fluid phenomena in the upper plenum of pressurized water reactor reflood facilities. In particular, the instrumentation measured two-phase flow velocity and void fraction. The principle of operation of the instrumentation scheme was based on the measurement of electrical impedance. The technique of analysis of random signals from two spatially separated impedance sensors was employed to measure two-phase flow velocity. A relative admittance technique was used to determine void fraction. The performance of the instrumentaton was studied in an air-water test facility.

  16. 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.

    2007-12-31T23:59:59.000Z

    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 temperature increase inside the device due the internal heat that is generated due to conduction and switching losses. Capacitors and high current switches that are reliable and meet performance specifications over an increased temperature range are necessary to realize electronics needed for hybrid-electric vehicles (HEVs), fuel cell (FC) and plug-in HEVs (PHEVs). In addition to individual component level testing, it is necessary to evaluate and perform long term module level testing to ascertain the effects of high temperature operation on power electronics.

  17. How to Make Appliance Standards Work: Improving Energy and Water Efficiency Test Procedures

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    Water Heaters With Input Ratings Above 75,000 Btu per Hour, Circulating and Instantaneous” [ANSI Z21.10.3a] American National StandardsWater Heaters With Input Ratings Above 75,000 Btu Per Hour, Circulating and Instantaneous” [ANSI Z21.10.3a] American National Standards

  18. Testing of Alternative Abrasives for Water-Jet Cutting at C Tank Farm

    SciTech Connect (OSTI)

    Krogstad, Eirik J.

    2013-08-01T23:59:59.000Z

    Legacy waste from defense-related activities at the Hanford Site has predominantly been stored in underground tanks, some of which have leaked; others may be at risk to do so. The U.S. Department of Energy’s goal is to empty the tanks and transform their contents into more stable waste forms. To do so requires breaking up, and creating a slurry from, solid wastes in the bottoms of the tanks. A technology developed for this purpose is the Mobile Arm Retrieval System. This system is being used at some of the older single shell tanks at C tank farm. As originally planned, access ports for the Mobile Arm Retrieval System were to be cut using a high- pressure water-jet cutter. However, water alone was found to be insufficient to allow effective cutting of the steel-reinforced tank lids, especially when cutting the steel reinforcing bar (“rebar”). The abrasive added in cutting the hole in Tank C-107 was garnet, a complex natural aluminosilicate. The hardness of garnet (Mohs hardness ranging from H 6.5 to 7.5) exceeds that of solids currently in the tanks, and was regarded to be a threat to Hanford Waste Treatment and Immobilization Plant systems. Olivine, an iron-magnesium silicate that is nearly as hard as garnet (H 6.5 to 7), has been proposed as an alternative to garnet. Pacific Northwest National Laboratory proposed to test pyrite (FeS2), whose hardness is slightly less (H 6 to 6.5) for 1) cutting effectiveness, and 2) propensity to dissolve (or disintegrate by chemical reaction) in chemical conditions similar to those of tank waste solutions. Cutting experiments were conducted using an air abrader system and a National Institute of Standards and Technology Standard Reference Material (SRM 1767 Low Alloy Steel), which was used as a surrogate for rebar. The cutting efficacy of pyrite was compared with that of garnet and olivine in identical size fractions. Garnet was found to be most effective in removing steel from the target; olivine and pyrite were less effective, but about equal to each other. The reactivity of pyrite, compared to olivine and garnet, was studied in high-pH, simulated tank waste solutions in a series of bench-top experiments. Variations in temperature, degree of agitation, grain size, exposure to air, and presence of nitrate and nitrite were also studied. Olivine and garnet showed no sign of dissolution or other reaction. Pyrite was shown to react with the fluids in even its coarsest variation (150?1000 ?m). Projected times to total dissolution for most experiments range from months to ca. 12 years, and the strongest control on reaction rate is the grain size.

  19. Construction and early test results of waste transport in piping systems served by ULF water closets

    E-Print Network [OSTI]

    Carrier, Jonathan Gerald

    2003-01-01T23:59:59.000Z

    The intent of this study was to determine if there is a correlation between discharge curves and venting on waste transport. Test stands were built to facilitate discharge curve and waste transport testing at the ESL Laboratory of Texas A&M. Tests...

  20. WaterTransport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing and Design Optimization

    SciTech Connect (OSTI)

    J. Vernon Cole; Abhra Roy; Ashok Damle; Hari Dahr; Sanjiv Kumar; Kunal Jain; Ned Djilai

    2012-10-02T23:59:59.000Z

    Water management in Proton Exchange Membrane, PEM, Fuel Cells is challenging because of the inherent conflicts between the requirements for efficient low and high power operation. Particularly at low powers, adequate water must be supplied to sufficiently humidify the membrane or protons will not move through it adequately and resistance losses will decrease the cell efficiency. At high power density operation, more water is produced at the cathode than is necessary for membrane hydration. This excess water must be removed effectively or it will accumulate in the Gas Diffusion Layers, GDLs, between the gas channels and catalysts, blocking diffusion paths for reactants to reach the catalysts and potentially flooding the electrode. As power density of the cells is increased, the challenges arising from water management are expected to become more difficult to overcome simply due to the increased rate of liquid water generation relative to fuel cell volume. Thus, effectively addressing water management based issues is a key challenge in successful application of PEMFC systems. In this project, CFDRC and our partners used a combination of experimental characterization, controlled experimental studies of important processes governing how water moves through the fuel cell materials, and detailed models and simulations to improve understanding of water management in operating hydrogen PEM fuel cells. The characterization studies provided key data that is used as inputs to all state-of-the-art models for commercially important GDL materials. Experimental studies and microscopic scale models of how water moves through the GDLs showed that the water follows preferential paths, not branching like a river, as it moves toward the surface of the material. Experimental studies and detailed models of water and airflow in fuel cells channels demonstrated that such models can be used as an effective design tool to reduce operating pressure drop in the channels and the associated costs and weight of blowers and pumps to force air and hydrogen gas through the fuel cell. Promising improvements to materials structure and surface treatments that can potentially aid in managing the distribution and removal of liquid water were developed; and improved steady-state and freeze-thaw performance was demonstrated for a fuel cell stack under the self-humidified operating conditions that are promising for stationary power generation with reduced operating costs.

  1. Puget Sound Tidal Energy In-Water Testing and Development Project Final Technical Report

    SciTech Connect (OSTI)

    Craig W. Collar

    2012-11-16T23:59:59.000Z

    Tidal energy represents potential for the generation of renewable, emission free, environmentally benign, and cost effective energy from tidal flows. A successful tidal energy demonstration project in Puget Sound, Washington may enable significant commercial development resulting in important benefits for the northwest region and the nation. This project promoted the United States Department of Energy�s Wind and Hydropower Technologies Program�s goals of advancing the commercial viability, cost-competitiveness, and market acceptance of marine hydrokinetic systems. The objective of the Puget Sound Tidal Energy Demonstration Project is to conduct in-water testing and evaluation of tidal energy technology as a first step toward potential construction of a commercial-scale tidal energy power plant. The specific goal of the project phase covered by this award was to conduct all activities necessary to complete engineering design and obtain construction approvals for a pilot demonstration plant in the Admiralty Inlet region of the Puget Sound. Public Utility District No. 1 of Snohomish County (The District) accomplished the objectives of this award through four tasks: Detailed Admiralty Inlet Site Studies, Plant Design and Construction Planning, Environmental and Regulatory Activities, and Management and Reporting. Pre-Installation studies completed under this award provided invaluable data used for site selection, environmental evaluation and permitting, plant design, and construction planning. However, these data gathering efforts are not only important to the Admiralty Inlet pilot project. Lessons learned, in particular environmental data gathering methods, can be applied to future tidal energy projects in the United States and other parts of the world. The District collaborated extensively with project stakeholders to complete the tasks for this award. This included Federal, State, and local government agencies, tribal governments, environmental groups, and others. All required permit and license applications were completed and submitted under this award, including a Final License Application for a pilot hydrokinetic license from the Federal Energy Regulatory Commission. The tasks described above have brought the project through all necessary requirements to construct a tidal pilot project in Admiralty Inlet with the exception of final permit and license approvals, and the selection of a general contractor to perform project construction.

  2. Ponding Test Results Seepage Losses Laterals 8E and 2A-C, Maverick County Water Control and Improvement District No. 1

    E-Print Network [OSTI]

    Leigh, Eric; Fipps, Guy

    TR-336 2008 Ponding Test Results Seepage Losses Laterals 8E and 2A-C Maverick County Water Control and Improvement District No. 1 By: Eric Leigh, Extension Associate, Biological and Agricultural... Engineering Guy Fipps, Professor and Extension Agricultural Engineer, Biological and Agricultural Engineering Texas Water Resources Institute Technical Report November 2008 PONDING TEST RESULTS SEEPAGE LOSSES LATERALS 8E AND 2A...

  3. Role of metal components in Pd?Cu bimetallic catalysts supported on CeO2 for the oxygen-enhanced water gas shift

    SciTech Connect (OSTI)

    Kugai, J.; Miller, J. T.; Guo, N.; Song, C. (Chemical Sciences and Engineering Division); ( PSC-USR); (Penn State Univ.)

    2011-06-01T23:59:59.000Z

    Catalytic hydrogen production and CO removal in a post-reforming process are critical for low-temperature fuel cell applications. The present study aims at clarifying the role of metal components in bimetallic catalysts for oxygen-enhanced water gas shift (OWGS), wherein a small amount of O{sub 2} is added to H{sub 2}-rich reformate gas to enhance CO shift. Among CeO{sub 2}-supported bimetallic catalysts, Pd-Cu and Pt-Cu combinations were found to show strong synergetic promoting effect in OWGS, which leads to much higher CO conversion and higher H{sub 2} yield than WGS at low temperature around 250 C. Temperature programmed reduction (TPR) showed strong interaction between Pd and Cu in Pd-Cu/CeO{sub 2} by a single reduction peak in contrast to multiple peaks on monometallic Cu/CeO{sub 2}. Extended X-ray absorption fine structure (EXAFS) analysis revealed that such bimetallic Pd-Cu and Pt-Cu form alloy nanoparticles, where noble metal is mainly surrounded by Cu atoms. Oxygen storage capacity (OSC) measurements point to higher resistance of Pd-Cu to oxidation indicating that Pd keeps Cu in reduced state in air pulse condition. From kinetic study, Pd in Pd-Cu was found to promote CO shift, rather than CO oxidation by increasing the number of active sites and by suppressing H{sub 2} activation (that is inherent to monometallic Pd), which minimizes both the inhibition effect of H{sub 2} and the loss of H{sub 2} by oxidation in OWGS. Transient response technique revealed that Cu in Pd-Cu enhances desorption of strongly chemisorbed CO{sub 2} on catalyst surface in contrast to very slow CO{sub 2} desorption from surface of monometallic Pd. Thus, the excellent OWGS activity of Pd-Cu catalyst has been attributed to the complementary roles of the two metals for enhancing CO shift, which is realized by its alloy structure and the accompanying strong interaction between metal components.

  4. Compost Analysis Samples provided by the Soil, Water and Forage Testing Laboratory at Texas A&M, 2003

    E-Print Network [OSTI]

    Mukhtar, Saqib

    Compost Analysis Samples provided by the Soil, Water and Forage Testing Laboratory at Texas A ppm ppm % % dS/m Dairy Manure Compost 0.6171 .2680 1.4345 3.5041 .2737 .4371 319.7 249.1 33.53 173.1 30.0 16.02 9.3 1.280 Dairy Manure Compost 1.0704 .3866 2.4949 6.7455 .5472 .7320 155.6 381.5 47

  5. OECD MCCI Small-Scale Water Ingression and Crust Strength tests (SSWICS) design report, Rev. 2 October 31, 2002.

    SciTech Connect (OSTI)

    Farmer, M.; Lomperski, S.; Kilsdonk, D.; Aeschlimann, B.; Pfeiffer, P. (Nuclear Engineering Division); (NRC)

    2011-05-23T23:59:59.000Z

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are planned to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx}{phi}30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. A description of the test apparatus, instrumentation, data reduction, and test matrix are the subject of the first portion of this report. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The introduction of a thermal gradient across the crust is thought to be important for these tests because of uncertainty in the magnitude of the thermal stresses and thus their relative importance in the crust fracture mechanism at plant scale. The second half of this report describes the apparatus for measuring crust strength. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength).

  6. Dielectric-breakdown tests of water at 6 MV W. A. Stygar,1

    E-Print Network [OSTI]

    . R. Woodworth1 1 Sandia National Laboratories, Albuquerque, New Mexico 87185, USA 2 Ktech Corporation, Albuquerque, New Mexico 87123, USA 3 EG&G, Albuquerque, New Mexico 87107, USA (Received 6 May 2008; published-insulated electrical components are often incorporated in the designs of multiterawatt pulsed- power accelerators

  7. Chlorine-36 in Water, Snow, and Mid-Latitude Glacial Ice of North America: Meteoric and Weapons-Tests Production in the Vicinity of the Idaho National Engineering and Environmental Laboratory, Idaho

    SciTech Connect (OSTI)

    L. DeWayne; J. R. Green (USGS); S. Vogt, P. Sharma (Purdue University); S. K. Frape (University of Waterloo); S. N. Davis (University of Arizona); G. L. Cottrell (USGS)

    1999-01-01T23:59:59.000Z

    Measurements of chlorine-36 (36Cl) were made for 64 water, snow, and glacial-ice and -runoff samples to determine the meteoric and weapons-tests-produced concentrations and fluxes of this radionuclide at mid-latitudes in North America. The results will facilitate the use of 36Cl as a hydrogeologic tracer at the Idaho National Engineering and Environmental Laboratory (INEEL). This information was used to estimate meteoric and weapons-tests contributions of this nuclide to environmental inventories at and near the INEEL. The data presented in this report suggest a meteoric source 36Cl for environmental samples collected in southeastern Idaho and western Wyoming if the concentration is less than 1 x 10 7 atoms/L. Additionally, concentrations in water, snow, or glacial ice between 1 x 10 7 and 1 x 10 8 atoms/L may be indicative of a weapons-tests component from peak 36Cl production in the late 1950s. Chlorine-36 concentrations between 1 x 10 8 and 1 x 10 9 atoms/L may be representative of re-suspension of weapons-tests fallout airborne disposal of 36Cl from the INTEC, or evapotranspiration. It was concluded from the water, snow, and glacial data presented here that concentrations of 36Cl measured in environmental samples at the INEEL larger than 1 x 10 9 atoms/L can be attributed to waste-disposal practices.

  8. Preliminary Modeling, Testing, and Analysis of a Gas Tankless Water Heater: Preprint

    SciTech Connect (OSTI)

    Burch, J.; Hoeschele, M.; Springer, D.; Rudd, A.

    2008-05-01T23:59:59.000Z

    Today's gas tankless water heaters offer significant energy savings over conventional gas storage tank water heaters, but savings depends on the draw pattern. A one-node model incorporating heat exchanger mass is used to address this and other issues. Key model parameters are determined from least-squares regression on short-term data, including burner efficiency, thermal capacitance, and thermal loss coefficient. The calibrated model agrees with data to ~5% on Qgas, with temperature RMS deviation of ~4..deg..C. Efficiency with a standard realistic draw is 71%, compared to 81% predicted from standard energy-factors. Adding a small tank controlled by the tankless heater solves issues of oscillations with solar pre-heat, low-flow and hot-water-delay issues. Future work includes model refinements and developing optimal data protocols for model parameter extraction.

  9. Field test of hydrophobic soil clod mulch for soil water conservation in a semiarid area

    E-Print Network [OSTI]

    Horton, Robert

    1977-01-01T23:59:59.000Z

    for mulched and unmulched profiles? 0. 0 m ? 2. 25 m, over the dry period, February 28 - April 4, 1977 . 7' TABLF Page 14. Yieasured vs. calculated weekly water balances for profiles of 0. 15 m ? 2. 25 m, for mulched and unmulched pro files dur Ing... the wet period, October 4? November 1, 1976 . 73 15. M asured vs. calculated weekly water balances ;-or profiles of 0. 15 m ? 2. 25 m, for mulched ano unmulched profiles during the dry period, February 28? April 4, 1977 75 16. Simulated i. emperature...

  10. SSSSaaaammmmpppplllliiiinnnngggg ffffoooorrrr BBBBaaaacccctttteeeerrrriiiiaaaa iiiinnnn WWWWeeeellllllllssss Water samples for bacteria tests must always be col-

    E-Print Network [OSTI]

    the inside surface of the faucet by flam- ing with a propane torch (a disposable butane lighter is fine the bottle immediately after collecting water sample. Refrigerate the sample and transport it to the laborato, disability, religion, age or national origin. Issued in furtherance of Cooperative Extension Work

  11. Testing Thermo-acoustic Sound Generation in Water with Proton and Laser Beams

    E-Print Network [OSTI]

    K. Graf; G. Anton; J. Hoessl; A. Kappes; T. Karg; U. Katz; R. Lahmann; C. Naumann; K. Salomon; C. Stegmann

    2005-09-15T23:59:59.000Z

    Experiments were performed at a proton accelerator and an infrared laser acility to investigate the sound generation caused by the energy deposition of pulsed particle and laser beams in water. The beams with an energy range of 1 PeV to 400 PeV per proton beam spill and up to 10 EeV for the laser pulse were dumped into a water volume and the resulting acoustic signals were recorded with pressure sensitive sensors. Measurements were performed at varying pulse energies, sensor positions, beam diameters and temperatures. The data is well described by simulations based on the thermo-acoustic model. This implies that the primary mechanism for sound generation by the energy deposition of particles propagating in water is the local heating of the media giving rise to an expansion or contraction of the medium resulting in a pressure pulse with bipolar shape. A possible application of this effect would be the acoustical detection of neutrinos with energies greater than 1 EeV.

  12. Water-quality monitoring at the Hoe Creek test site: review and preliminary conclusions

    SciTech Connect (OSTI)

    Wang, F T; Mead, S W; Stuermer, D H

    1982-05-20T23:59:59.000Z

    It has been shown that underground coal gasification (UCG) may introduce a broad range of residual gasification products into the groundwater of a coal aquifer. Sorption of many contaminants by the coal itself is an important factor in restricting the migration of these contaminants in the ground water. However, field studies, conducted at Lawrence Livermore National Laboratory's Hoe Creek site, have shown that sorption of organic compounds by coal is not as effective as expected, perhaps because the coal surface area is limited. Furthermore, if severe roof collapse has taken place during gasification, non-coal aquifers located above the gasified coal seam may be interconnected with the coal aquifer, and contaminants may enter these non-coal aquifers, in which sorption is even less effective. The Hoe Creek II and III experiments have provided opportunities to study the contamination of a sand aquifer located above a gasified coal seam in a hydrological recharge area. Preliminary results indicate that the water in the overlying sand aquifer is much less contaminated with organic compounds than the water in the gasified coal aquifer. In conducting these field investigations, valuable lessons ere learned concerning groundwater monitoring. A suggested monitoring strategy is discussed.

  13. 2 IEEE TRANSACTIONS ON COMPONENTS, PACKAGING, AND MANUFACTURING TECHNOLOGY--PART B, VOL. 20, NO. 1, FEBRUARY 1997 A Novel Test Technique for MCM Substrates

    E-Print Network [OSTI]

    Swaminathan, Madhavan

    , FEBRUARY 1997 A Novel Test Technique for MCM Substrates Bruce Kim, Member, IEEE, Madhavan Swaminathan-- This paper describes a novel and low-cost test technique that is capable of detecting process related defects such as opens and shorts in multichip module (MCM) substrates. This method is an alternative to existing test

  14. Water Loss Test Results Main 'J' Canal Delta Lake Irrigation District

    E-Print Network [OSTI]

    Leigh, E.; Fipps, G.

    Program and Discussion Table 2. Additional Test Result Information for the Main ?J? Canal Figure 3. Photo showing the GPS survey and a staff gage Figure 4. Small earthen dam upstream of the lateral head-gate Appendix Detailed Test Results... (Figure 1), the concrete lined section of the main supply canal that feeds the City of Raymondville, flows west to east in the northeastern sector of the district (see figure 2); located approximately four miles west of US Hwy 77 and a mile north of FM...

  15. Hanford Waste Vitrification Plant full-scale feed preparation testing with water and process simulant slurries

    SciTech Connect (OSTI)

    Gaskill, J.R.; Larson, D.E.; Abrigo, G.P. [and others] [and others

    1996-03-01T23:59:59.000Z

    The Hanford Waste Vitrification Plant was intended to convert selected, pretreated defense high-level waste and transuranic waste from the Hanford Site into a borosilicate glass. A full-scale testing program was conducted with nonradioactive waste simulants to develop information for process and equipment design of the feed-preparation system. The equipment systems tested included the Slurry Receipt and Adjustment Tank, Slurry Mix Evaporator, and Melter-Feed Tank. The areas of data generation included heat transfer (boiling, heating, and cooling), slurry mixing, slurry pumping and transport, slurry sampling, and process chemistry. 13 refs., 129 figs., 68 tabs.

  16. 2014-10-14 Issuance: Test Procedures and Energy Conservation Standards for Residential Solar Water Heaters; Request for Information

    Broader source: Energy.gov [DOE]

    This document is a pre-publication Federal Register request for information regarding test procedures and energy conservation standards for residential solar water heaters, as issued by the Deputy Assistant Secretary for Energy Efficiency on October 14, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  17. Analysis of Ground-Water Levels and Associated Trends in Yucca Flat, Nevada Test Site, Nye County, Nevada, 1951-2003

    SciTech Connect (OSTI)

    J.M. Fenelon

    2005-10-05T23:59:59.000Z

    Almost 4,000 water-level measurements in 216 wells in the Yucca Flat area from 1951 to 2003 were quality assured and analyzed. An interpretative database was developed that describes water-level conditions for each water level measured in Yucca Flat. Multiple attributes were assigned to each water-level measurement in the database to describe the hydrologic conditions at the time of measurement. General quality, temporal variability, regional significance, and hydrologic conditions are attributed for each water-level measurement. The database also includes narratives that discuss the water-level history of each well. Water levels in 34 wells were analyzed for variability and for statistically significant trends. An attempt was made to identify the cause of many of the water-level fluctuations or trends. Potential causes include equilibration following well construction or development, pumping in the monitoring well, withdrawals from a nearby supply well, recharge from precipitation, earthquakes, underground nuclear tests, land subsidence, barometric pressure, and Earth tides. Some of the naturally occurring fluctuations in water levels may result from variations in recharge. The magnitude of the overall water-level change for these fluctuations generally is less than 2 feet. Long-term steady-state hydrographs for most of the wells open to carbonate rock have a very similar pattern. Carbonate-rock wells without the characteristic pattern are directly west of the Yucca and Topgallant faults in the southwestern part of Yucca Flat. Long-term steady-state hydrographs from wells open to volcanic tuffs or the Eleana confining unit have a distinctly different pattern from the general water-level pattern of the carbonate-rock aquifers. Anthropogenic water-level fluctuations were caused primarily by water withdrawals and nuclear testing. Nuclear tests affected water levels in many wells. Trends in these wells are attributed to test-cavity infilling or the effects of depressurization following nuclear testing. The magnitude of the overall water-level change for wells with anthropogenic trends can be large, ranging from several feet to hundreds of feet. Vertical water-level differences at 27 sites in Yucca Flat with multiple open intervals were compared. Large vertical differences were noted in volcanic rocks and in boreholes where water levels were affected by nuclear tests. Small vertical differences were noted within the carbonate-rock and valley-fill aquifers. Vertical hydraulic gradients generally are downward in volcanic rocks and from pre-Tertiary clastic rocks toward volcanic- or carbonate-rock units.

  18. Comparison of Test Procedures and Energy Efficiency Criteria in Selected International Standards and Labeling Programs for Clothes Washers, Water Dispensers, Vending Machines and CFLs

    E-Print Network [OSTI]

    Fridley, David

    2010-01-01T23:59:59.000Z

    Appliance Manufacturers (AHAM), and Japan’s own JIS C 9606The U.S. test procedure (AHAM HWL-1) does not include a washAppliance Manufacturers (AHAM) HWL-1 Cold Water: 60 ± 5?F (

  19. Slow Strain Rate Testing of Alloy 22 in Simulated Concentrated Ground Waters

    SciTech Connect (OSTI)

    King, K J; Wong, L L; Estill, J C; Rebak, R B

    2003-10-29T23:59:59.000Z

    The proposed engineering barriers for the high-level nuclear waste repository in Yucca Mountain include a double walled container and a detached drip shield. The candidate material for the external wall of the container is Alloy 22 (N06022). One of the anticipated degradation modes for the containers could be environmentally assisted cracking (EAC). The objective of the current research was to characterize the effect of applied potential and temperature on the susceptibility of Alloy 22 to EAC in simulated concentrated water (SCW) and other environments using the slow strain rate technique (SSRT). Results show that the temperature and applied potential have a strong influence on the susceptibility of Alloy 22 to suffer EAC in SCW solution. Limited results show that sodium fluoride solution is more detrimental than sodium chloride solution.

  20. Cyclone reburn using coal-water fuel: Pilot-scale development and testing. Final report

    SciTech Connect (OSTI)

    Eckhart, C.F.; DeVault, R.F.

    1991-10-01T23:59:59.000Z

    There is an ongoing effort to develop retrofit technologies capable of converting oil- and/or gas-fired boilers to coal combustion. The objective of this project is to demonstrate the technical feasibility of an improved portion of a previously developed retrofit system designed for the purpose of converting oil/gas boilers. This improvement would almost entirely eliminate the use of premium fuels, thereby significantly increasing the economical attractiveness of the system. Specifically, the goals in this program were to replace natural gas as a reburning fuel with coal-water fuel (CWF). The advantages of such a system include: (1) increased return on investment (ROI) for conversions; (2) nearly complete elimination of premium oil or gas fuel; (3) a more integrated approach to the conversion of oil- or gas-designed boilers to CWF.

  1. Cyclone reburn using coal-water fuel: Pilot-scale development and testing

    SciTech Connect (OSTI)

    Eckhart, C.F.; DeVault, R.F.

    1991-10-01T23:59:59.000Z

    There is an ongoing effort to develop retrofit technologies capable of converting oil- and/or gas-fired boilers to coal combustion. The objective of this project is to demonstrate the technical feasibility of an improved portion of a previously developed retrofit system designed for the purpose of converting oil/gas boilers. This improvement would almost entirely eliminate the use of premium fuels, thereby significantly increasing the economical attractiveness of the system. Specifically, the goals in this program were to replace natural gas as a reburning fuel with coal-water fuel (CWF). The advantages of such a system include: (1) increased return on investment (ROI) for conversions; (2) nearly complete elimination of premium oil or gas fuel; (3) a more integrated approach to the conversion of oil- or gas-designed boilers to CWF.

  2. Water-quality monitoring at the Hoe Creek test site: review and preliminary conclusions

    SciTech Connect (OSTI)

    Wang, F.T.; Mead, S.W.; Stuermer, D.H.

    1983-04-16T23:59:59.000Z

    It has been shown that underground coal gasification (UCG) may introduce a broad range of residual gasification products into the groundwater of a coal aquifer. Sorption of many contaminants by the coal itself is an important factor in restricting the migration of these contaminants in the groundwater. However, our field studies at the Lawrence Livermore National Laboratory (LLNL) Hoe Creek site in northeastern Wyoming have shown that sorption of organic compounds by coal is not as effective as expected, perhaps because the coal surface area is limited. Furthermore, if severe roof collapse has taken place during gasification, non-coal aquifers located above the gasified coal seam may be interconnected with the coal aquifer. Contaminants may enter these non-coal aquifers, in which sorption is even less effective. The Hoe Creek II and III experiments have enabled us to study the contamination of a sand aquifer located above a gasified coal seam in a hydrological recharge area. Our preliminary results indicate that the water in the overlying sand aquifer is much less contaminated with organic compounds than that in the gasified coal aquifer. In conducting these field investigations, we have also learned valuable lessons concerning a strategy for groundwater monitoring. 21 figures.

  3. Water quality monitoring at the Hoe Creek test site: review and preliminary conclusions

    SciTech Connect (OSTI)

    Wang, F.T.; Mead, S.W.; Sturmer, D.H.

    1983-01-01T23:59:59.000Z

    It has been shown that underground coal gasification (UCG) may introduce a broad range of residual products into the groundwater of a coal aquifer. Sorption of many contaminants by the coal itself is an important factor in restricting the migration of these contaminants in the groundwater. However, our field studies at the Lawrence Livermore National Laboratory (LLNL) Hoe Creek site in northeastern Wyoming have shown that sorption of organic compounds by coal is not as effective as expected, perhaps because the coal surface area is limited. Furthermore, if severe roof collapse has taken place during gasification, non-coal aquifers located above the gasified coal seam may become interconnected with the cavity. Contaminants may enter these non-coal aquifers, in which sorption is even less effective. The Hoe Creek II and III experiments have enabled us to study the contamination of a sand aquifer located above a gasified coal seam in a hydrological recharge area. The preliminary results indicate that the water in the overlying sand aquifer is much less contaminated with organic compounds than that in the gasified

  4. Pressure Build-Up During the Fire Test in Type B(U) Packages Containing Water - 13280

    SciTech Connect (OSTI)

    Feldkamp, Martin; Nehrig, Marko; Bletzer, Claus; Wille, Frank [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44, 12205 Berlin (Germany)] [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44, 12205 Berlin (Germany)

    2013-07-01T23:59:59.000Z

    The safety assessment of packages for the transport of radioactive materials with content containing liquids requires special consideration. The main focus is on water as supplementary liquid content in Type B(U) packages. A typical content of a Type B(U) package is ion exchange resin, waste of a nuclear power plant, which is not dried, normally only drained. Besides the saturated ion exchange resin, a small amount of free water can be included in these contents. Compared to the safety assessment of packages with dry content, attention must be paid to some more specific issues. An overview of these issues is provided. The physical and chemical compatibility of the content itself and the content compatibility with the packages materials must be demonstrated for the assessment. Regarding the mechanical resistance the package has to withstand the forces resulting from the freezing liquid. The most interesting point, however, is the pressure build-up inside the package due to vaporization. This could for example be caused by radiolysis of the liquid and must be taken into account for the storage period. If the package is stressed by the total inner pressure, this pressure leads to mechanical loads to the package body, the lid and the lid bolts. Thus, the pressure is the driving force on the gasket system regarding the activity release and a possible loss of tightness. The total pressure in any calculation is the sum of partial pressures of different gases which can be caused by different effects. The pressure build-up inside the package caused by the regulatory thermal test (30 min at 800 deg. C), as part of the cumulative test scenario under accident conditions of transport is discussed primarily. To determine the pressure, the temperature distribution in the content must be calculated for the whole period from beginning of the thermal test until cooling-down. In this case, while calculating the temperature distribution, conduction and radiation as well as evaporation and condensation during the associated process of transport have to be considered. This paper discusses limiting amounts of water inside the cask which could lead to unacceptable pressure and takes into account saturated steam as well as overheated steam. However, the difficulties of assessing casks containing wet content will be discussed. From the authority assessment point of view, drying of the content could be an effective way to avoid the above described pressure build-up and the associated difficulties for the safety assessment. (authors)

  5. Status of the Norwegian thorium light water reactor (LWR) fuel development and irradiation test program

    SciTech Connect (OSTI)

    Drera, S.S.; Bjork, K.I.; Kelly, J.F.; Asphjell, O. [Thor Energy AS: Sommerrogaten 13-15, Oslo, NO255 (Norway)

    2013-07-01T23:59:59.000Z

    Thorium based fuels offer several benefits compared to uranium based fuels and should thus be an attractive alternative to conventional fuel types. In order for thorium based fuel to be licensed for use in current LWRs, material properties must be well known for fresh as well as irradiated fuel, and accurate prediction of fuel behavior must be possible to make for both normal operation and transient scenarios. Important parameters are known for fresh material but the behaviour of the fuel under irradiation is unknown particularly for low Th content. The irradiation campaign aims to widen the experience base to irradiated (Th,Pu)O{sub 2} fuel and (Th,U)O{sub 2} with low Th content and to confirm existing data for fresh fuel. The assumptions with respect to improved in-core fuel performance are confirmed by our preliminary irradiation test results, and our fuel manufacture trials so far indicate that both (Th,U)O{sub 2} and (Th,Pu)O{sub 2} fuels can be fabricated with existing technologies, which are possible to upscale to commercial volumes.

  6. Cold vacuum drying proof of performance (first article testing) test results

    SciTech Connect (OSTI)

    MCCRACKEN, K.J.

    1999-06-23T23:59:59.000Z

    This report presents and details the test results of the first of a kind process referred to as Cold Vacuum Drying (CVD). The test results are compiled from several months of testing of the first process equipment skid and ancillary components to de-water and dry Multi-Canister Overpacks (MCO) filled with Spent Nuclear Fuel (SNF). The tests results provide design verifications, equipment validations, model validation data, and establish process parameters.

  7. Development and testing of a photometric method to identify non-operating solar hot water systems in field settings.

    SciTech Connect (OSTI)

    He, Hongbo (University of New Mexico, Albuquerque, NM); Vorobieff, Peter V. (University of New Mexico, Albuquerque, NM); Menicucci, David (University of New Mexico, Albuquerque, NM); Mammoli, Andrea A. (University of New Mexico, Albuquerque, NM); Carlson, Jeffrey J.

    2012-06-01T23:59:59.000Z

    This report presents the results of experimental tests of a concept for using infrared (IR) photos to identify non-operational systems based on their glazing temperatures; operating systems have lower glazing temperatures than those in stagnation. In recent years thousands of new solar hot water (SHW) systems have been installed in some utility districts. As these numbers increase, concern is growing about the systems dependability because installation rebates are often based on the assumption that all of the SHW systems will perform flawlessly for a 20-year period. If SHW systems routinely fail prematurely, then the utilities will have overpaid for grid-energy reduction performance that is unrealized. Moreover, utilities are responsible for replacing energy for loads that failed SHW system were supplying. Thus, utilities are seeking data to quantify the reliability of SHW systems. The work described herein is intended to help meet this need. The details of the experiment are presented, including a description of the SHW collectors that were examined, the testbed that was used to control the system and record data, the IR camera that was employed, and the conditions in which testing was completed. The details of the associated analysis are presented, including direct examination of the video records of operational and stagnant collectors, as well as the development of a model to predict glazing temperatures and an analysis of temporal intermittency of the images, both of which are critical to properly adjusting the IR camera for optimal performance. Many IR images and a video are presented to show the contrast between operating and stagnant collectors. The major conclusion is that the technique has potential to be applied by using an aircraft fitted with an IR camera that can fly over an area with installed SHW systems, thus recording the images. Subsequent analysis of the images can determine the operational condition of the fielded collectors. Specific recommendations are presented relative to the application of the technique, including ways to mitigate and manage potential sources of error.

  8. A field-based study of alternative microbial indicator tests for drinking water quality in Northern Ghana

    E-Print Network [OSTI]

    O'Keefe, Samantha F

    2012-01-01T23:59:59.000Z

    Safe drinking water is essential for human survival, yet it is unavailable to over 1 billion of the world's people living in poverty (World Bank, 2009). The current methods used to identify drinking water sources are ...

  9. Sampling and analytical testing of groundwater and surface water at the Colorado School of Mines Research Institute (CSMRI) has been conducted on a quarterly basis since early

    E-Print Network [OSTI]

    is being consumed, changing the water chemistry, and leading to lower uranium concentrations with flow, Th-230, Th-232, and uranium), and metals (arsenic, barium calcium, cadmium, chromium, lead, manganese and analytical testing for radium, calcium, magnesium, potassium, sodium, uranium, and zinc will continue

  10. OECD MMCI Small-Scale Water Ingression and Crust Strength tests (SSWICS) SSWICS-1 final data report, Rev. 1 February 10, 2003.; Report, Rev. 1

    SciTech Connect (OSTI)

    Lomperski, S.; Farmer, M. T.; Kilsdonk, D.; Aeschlimann, B. (Nuclear Engineering Division)

    2011-05-23T23:59:59.000Z

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure; and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx}{phi}30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the first water ingression test, designated SSWICS-1. The test investigated the quench behavior of a 15 cm deep, fully oxidized PWR corium melt containing 8 wt% limestone/common sand concrete decomposition products. The melt was quenched at nominally atmospheric pressure. The report includes a description of the test apparatus, the instrumentation used, plots of the recorded data, and data reduction to obtain an estimate of the corrected heat flux from the corium to the overlying water pool. A section of the report is devoted to calculations of the conduction-limited heat flux that accounts for heat losses to the crucible holding the corium. The remainder of the report describes post test examinations of the crust, which includes permeability and mechanical strength measurements, and chemical analysis.

  11. OECM MCCI Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-2 final data report, Rev. 0 February 12, 2003.

    SciTech Connect (OSTI)

    Lomperski, S.; Farmer, M. T.; Kilsdonk, D.; Aeschlimann, B. (Nuclear Engineering Division)

    2011-05-23T23:59:59.000Z

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx}{phi}30 cm; up to 20 cm deep). The main parameter to be varied in these quench tests is the melt composition since it is thought to have a critical influence on the crust cracking behavior which, in turn, alters quench rate. The issue of crust strength will be addressed with a second apparatus designed to mechanically load the crust produced by the quench tests. This apparatus will measure the fracture strength of the crust while under a thermal load created by a heating element beneath the crust. The two apparatuses used to measure the melt quench rate and crust strength are jointly referred to as SSWICS (Small-Scale Water Ingression and Crust Strength). This report describes results of the second water ingression test, designated SSWICS-2. The test investigated the quench behavior of a 15 cm deep, fully oxidized PWR corium melt containing 8 wt% siliceous concrete decomposition products. The melt was quenched at nominally atmospheric pressure. The report includes a description of the test apparatus, the instrumentation used, plots of the recorded data, and data reduction to obtain an estimate of the corrected heat flux from the corium to the overlying water pool. A section of the report is devoted to calculations of the conduction-limited heat flux that accounts for heat losses to the crucible holding the corium. The remainder of the report describes post test examinations of the crust, which includes permeability and mechanical strength measurements, and chemical analysis.

  12. A system to test the effects of materials on the electron drift lifetime in liquid argon and observations on the effect of water

    SciTech Connect (OSTI)

    Andrews, R.; Jaskierny, W.; Jostlein, H.; Kendziora, C.; Pordes, S.; Tope, T.; /Fermilab; ,

    2009-07-01T23:59:59.000Z

    A materials test system (MTS) has been developed at FNAL to assess the suitability of materials for use in a large liquid argon time projection chamber. During development of the MTS, it was noted that controlling the cryostat pressure with a 'raining' condenser reduced the electron drift lifetime in the liquid argon. The effect of condensing has been investigated using a series of passive materials to filter the condensate. We report the results of these studies and of tests on different candidate materials for detector construction. The inferred reduction of electron drift lifetime by water concentrations in the parts per trillion is of particular interest.

  13. Materials and Components Technology Division research summary, 1992

    SciTech Connect (OSTI)

    Not Available

    1992-11-01T23:59:59.000Z

    The Materials and Components Technology Division (MCT) provides a research and development capability for the design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs related to nuclear energy support the development of the Integral Fast Reactor (IFR): life extension and accident analyses for light water reactors (LWRs); fuels development for research and test reactors; fusion reactor first-wall and blanket technology; and safe shipment of hazardous materials. MCT Conservation and Renewables programs include major efforts in high-temperature superconductivity, tribology, nondestructive evaluation (NDE), and thermal sciences. Fossil Energy Programs in MCT include materials development, NDE technology, and Instrumentation design. The division also has a complementary instrumentation effort in support of Arms Control Technology. Individual abstracts have been prepared for the database.

  14. Drinking Water Problems: Lead

    E-Print Network [OSTI]

    Dozier, Monty; McFarland, Mark L.

    2004-02-20T23:59:59.000Z

    Lead in drinking water can damage the brain, kidneys, nervous system and red blood cells. This publication explains how lead can enter drinking water, how to have your water tested, and how to eliminate lead from drinking water....

  15. Testing with JUnit Testing with JUnit

    E-Print Network [OSTI]

    Peters, Dennis

    Testing with JUnit Testing with JUnit Running a test case: 1 Get the component to a known state (set up). 2 Cause some event (the test case). 3 Check the behaviour. · Record pass/fail · Track statistics · Typically we want to do a lot of test cases so it makes sense to automate. · Test cases

  16. Water Heaters and Hot Water Distribution Systems

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    heat loss testing; part load performance curves for instantaneous gas water heaters; and pressure loss calculationsheat loss testing; part load performance curves for instantaneous gas water heaters; and pressure loss calculations

  17. Well Owner's Guide To Water Supply

    E-Print Network [OSTI]

    Fay, Noah

    's groundwater and guidelines, including national drinking water standards, to test well water to insure safe drinking water in private wells. National drinking water standards and common methods of home water .....................22 Contaminants in Water........................................23 Drinking Water Guidelines

  18. A Study of the Economic Impact of Water Impoundment Through Validity Testing of a Comparitive-Projection Model

    E-Print Network [OSTI]

    Pearson, J. E.; Heideman, K. E.

    An established economic simulation model for reservoir development was applied to ten reservoir projects throughout Texas. The model as a predictor of economic impact was given a difficult test because of the diversity of geographic, economic...

  19. Initial field testing definition of subsurface sealing and backfilling tests in unsaturated tuff; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Fernandez, J.A. [Sandia National Labs., Albuquerque, NM (United States); Case, J.B.; Tyburski, J.R. [I. T. Corp., Albuquerque, NM (United States)

    1993-05-01T23:59:59.000Z

    This report contains an initial definition of the field tests proposed for the Yucca Mountain Project repository sealing program. The tests are intended to resolve various performance and emplacement concerns. Examples of concerns to be addressed include achieving selected hydrologic and structural requirements for seals, removing portions of the shaft liner, excavating keyways, emplacing cementitious and earthen seals, reducing the impact of fines on the hydraulic conductivity of fractures, efficient grouting of fracture zones, sealing of exploratory boreholes, and controlling the flow of water by using engineered designs. Ten discrete tests are proposed to address these and other concerns. These tests are divided into two groups: Seal component tests and performance confirmation tests. The seal component tests are thorough small-scale in situ tests, the intermediate-scale borehole seal tests, the fracture grouting tests, the surface backfill tests, and the grouted rock mass tests. The seal system tests are the seepage control tests, the backfill tests, the bulkhead test in the Calico Hills unit, the large-scale shaft seal and shaft fill tests, and the remote borehole sealing tests. The tests are proposed to be performed in six discrete areas, including welded and non-welded environments, primarily located outside the potential repository area. The final selection of sealing tests will depend on the nature of the geologic and hydrologic conditions encountered during the development of the Exploratory Studies Facility and detailed numerical analyses. Tests are likely to be performed both before and after License Application.

  20. Advanced BWR core component designs and the implications for SFD analysis

    SciTech Connect (OSTI)

    Ott, L.J.

    1997-02-01T23:59:59.000Z

    Prior to the DF-4 boiling water reactor (BWR) severe fuel damage (SFD) experiment conducted at the Sandia National Laboratories in 1986, no experimental data base existed for guidance in modeling core component behavior under postulated severe accident conditions in commercial BWRs. This paper will present the lessons learned from the DF-4 experiment (and subsequent German CORA BWR SFD tests) and the impact on core models in the current generation of SFD codes. The DF-4 and CORA BWR test assemblies were modeled on the core component designs circa 1985; that is, the 8 x 8 fuel assembly with two water rods and a cruciform control blade constructed of B{sub 4}C-filled tubelets. Within the past ten years, the state-of-the-art with respect to BWR core component development has out-distanced the current SFD experimental data base and SFD code capabilities. For example, modern BWR control blade design includes hafnium at the tips and top of each control blade wing for longer blade operating lifetimes; also water rods have been replaced by larger water channels for better neutronics economy; and fuel assemblies now contain partial-length fuel rods, again for better neutronics economy. This paper will also discuss the implications of these advanced fuel assembly and core component designs on severe accident progression and on the current SFD code capabilities.

  1. Comparative laboratory selection and field testing of polymers for selective control of water production in gas wells

    SciTech Connect (OSTI)

    Ranjbar, M. [Technical Univ., Clausthal (Germany); Czolbe, P. [DBI-GUT, Freiberg (Germany); Kohler, N. [IFP, Rueil-Malmaison (France)

    1995-11-01T23:59:59.000Z

    Intensive comparative feasibility studies were performed in different laboratories in order to select the most promising polymer based technology for water control in gas production and storage wells exhibiting low matrix permeability, high temperature and high produced brine salinity. Core flow experiments performed under reservoir conditions with different commercially available chemical systems have pointed to the superiority of two relatively low-molecular-weight vinyl sulfonated/vinyl amide/acrylamide terpolymers over other polymers to decrease selectively and effectively the water permeability without affecting the gas flow. These polymers have excellent compatibility with all types of reservoir brines and good thermal stability up to 150 C. Furthermore, because of their high shear resistance, and excellent injectability even in low permeability cores, solutions of these polymers can be pumped at high injection rates with a moderate wellhead pressure.

  2. Revisions to the SRCC Rating Process for Solar Water Heaters: Preprint

    SciTech Connect (OSTI)

    Burch, J.; Huggins, J.; Long, S.; Thornton, J.

    2012-06-01T23:59:59.000Z

    In the United States, annual performance ratings for solar water heaters are computed with component-based simulation models driven by typical meteorological year weather and specified water draw. Changes in the process are being implemented to enhance credibility through increased transparency and accuracy. Changes to the process include using a graphical rather than text-based model-building tool, performing analytical tests on all components and systems, checking energy balances on every component, loop, and system at every time step, comparing the results to detect outliers and potential errors, and documenting the modeling process in detail. Examples of changes in ratings are shown, along with analytical and comparative testing results.

  3. Colorado State University program for developing, testing, evaluating and optimizing solar heating and cooling systems

    SciTech Connect (OSTI)

    Not Available

    1992-03-23T23:59:59.000Z

    The objective is to develop and test various integrated solar heating, cooling and domestic hot water systems, and to evaluate their performance. Systems composed of new, as well as previously tested, components are carefully integrated so that effects of new components on system performance can be clearly delineated. The SEAL-DOE program includes six tasks which have received funding for the 1991--92 fifteen-month period. These include: (1) a project employing isothermal operation of air and liquid solar space heating systems, (2) a project to build and test several generic solar water heaters, (3) a project that will evaluate advanced solar domestic hot water components and concepts and integrate them into solar domestic hot water systems, (4) a liquid desiccant cooling system development project, (5) a project that will perform system modeling and analysis work on solid desiccant cooling systems research, and (6) a management task. The objectives and progress in each task are described in this report.

  4. Colorado State University program for developing, testing, evaluating and optimizing solar heating and cooling systems

    SciTech Connect (OSTI)

    Not Available

    1990-11-01T23:59:59.000Z

    The objective is to develop and test various integrated solar heating, cooling and domestic hot water systems, and to evaluate their performance. Systems composed of new, as well as previously tested, components are carefully integrated so that effects of new components on system performance can be clearly delineated. The eight-month program for 1990 is separated into seven tasks. There are tasks for each of the three solar houses, a project to build and test several generic solar water heaters, a project that will evaluate advanced solar domestic hot water components and concepts and integrate them into solar domestic hot water systems, a management task, and a task funding travel to attend the Field Monitoring for a Purpose'' workshop which was held April 2--5, 1990, in Gothenburg, Sweden. The objectives and progress in each task are described in this report. 7 figs., 4 tabs.

  5. Free-piston Stirling engine diaphragm-coupled Heat-Actuated Heat Pump component technology program: Volume 2, Phase 2A and 2B final report: Lennox test program

    SciTech Connect (OSTI)

    Ackermann, R.A.

    1988-01-25T23:59:59.000Z

    This volume addresses the testing of the Mark I heat pump module conducted by Lennox Industries. The following information is contained herein: Lennox Test Plan; Lennox Test Data Spread Sheet; Lennox Parametric Test Data Plots; and Lennox Parametric Test Data Sheets.

  6. US Synthetic Corp (TRL 4 Component) - The Development of Open...

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

    Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines US Synthetic Corp (TRL 4 Component) - The Development of Open, Water Lubricated...

  7. Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

    SciTech Connect (OSTI)

    Curtis Smith; David Schwieder; Cherie Phelan; Anh Bui; Paul Bayless

    2012-08-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

  8. Critical pulse power components

    SciTech Connect (OSTI)

    Sarjeant, W.J.; Rohwein, G.J.

    1981-01-01T23:59:59.000Z

    Critical components for pulsed power conditioning systems will be reviewed. Particular emphasis will be placed on those components requiring significant development efforts. Capacitors, for example, are one of the weakest elements in high-power pulsed systems, especially when operation at high-repetition frequencies for extended periods of time are necessary. Switches are by far the weakest active components of pulse power systems. In particular, opening switches are essentially nonexistent for most applications. Insulaton in all systems and components requires development and improvement. Efforts under way in technology base development of pulse power components will be discussed.

  9. Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

    SciTech Connect (OSTI)

    Ware, A.G.; Morton, D.K.; Nitzel, M.E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-03-01T23:59:59.000Z

    Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants.

  10. Design and Development of a Test Facility to Study Two-Phase Steam/Water Flow in Porous Media

    SciTech Connect (OSTI)

    Verma, Ashok K.; Pruess, Karsten; Bodvarsson, G.S.; Tsang, C.F.; Witherspoon, Paul A.

    1983-12-15T23:59:59.000Z

    The concept of relative permeability is the key concept in extending Darcy's law for single phase flow through porous media to the two-phase flow regime. Relative permeability functions are needed for simulation studies of two-phase geothermal reservoirs. These are poorly known inspite of considerable theoretical and experimental investigations during the last decade. Since no conclusive results exist, many investigators use ad hoc parametrization, or adopt results obtined from flow of oil and gas (Corey, 1954). It has been shown by Reda and Eaton (1980) that this can lead to serious deficiencies. Sensitivity of the relative permeability curves for prediction of mass flow rate and flowing enthalpy into geothermal wells has been studied by many investigators (e.g. Eaton and Reda (1980), Bodvarsson et al (1980), Sun and Ershagi (1979) etc.). It can be concluded from these studies that the beehavior of a two-phase steam/water reservoir depends greatly on the relative permeability curves used. Hence, there exists a need for obtaining reliable relative permeability functions.

  11. Superclean coal-water slurry combustion testing in an oil-fired boiler. Semiannual technical progress report, August 15, 1992--February 15, 1993

    SciTech Connect (OSTI)

    Miller, B.G.; Pisupati, S.V.; Poe, R.L.; Morrison, J.L.; Xie, J.; Walsh, P.M.; Wincek, R.T.; Clark, D.A.; Scaroni, A.W.

    1993-04-21T23:59:59.000Z

    The Pennsylvania State University is conducting a superclean coal-water slurry (SCCWS) program for the United States Department of Energy (DOE) and the Commonwealth of Pennsylvania with the objective of determining the capability of effectively firing SCCWS in an industrial boiler designed for heavy fuel oil. Penn State has entered into a cooperative agreement with DOE to determine if SCCWS (a fuel containing coal with 3.0 wt.% ash and 0.9 wt.% sulfur) can effectively be burned in a heavy fuel oil-designed industrial boiler without adverse impact on boiler rating, maintainability, reliability, and availability. The project will provide information on the design of new systems specifically configured to fire these clean coal-based fuels. The project consists of four phases: (1) design, permitting, and test planning, (2) construction and start up, (3) demonstration and evaluation (1,000-hour demonstration), and (4) program expansion (additional 1,000 hours of testing). The boiler testing wig determine if the SCCWS combustion characteristics, heat release rate, fouling and slagging behavior, corrosion and erosion limits, and fuel transport, storage, and handling characteristics can be accommodated in an oil-designed boiler system. In addition, the proof-of-concept demonstration will generate data to determine how the properties of SCCWS and its parent coal affect boiler performance. Economic factors associated with retrofitting boilers will be identified

  12. Existing and Past Methods of Test and Rating Standards Related to Integrated Heat Pump Technologies

    SciTech Connect (OSTI)

    Reedy, Wayne R. [Sentech, Inc.

    2010-07-01T23:59:59.000Z

    This report evaluates existing and past US methods of test and rating standards related to electrically operated air, water, and ground source air conditioners and heat pumps, 65,000 Btu/hr and under in capacity, that potentiality incorporate a potable water heating function. Two AHRI (formerly ARI) standards and three DOE waivers were identified as directly related. Six other AHRI standards related to the test and rating of base units were identified as of interest, as they would form the basis of any new comprehensive test procedure. Numerous other AHRI and ASHRAE component test standards were also identified as perhaps being of help in developing a comprehensive test procedure.

  13. Insulating and sheathing materials of electric and optical cables - Common test methods - Part 5-1: Methods specific to filling compounds - Drop-point - Separation of oil - Lower temperature brittleness - Total acid number - Absence of corrosive components - Permittivity at 23 °C - DC resistivity at 23 °C and 100 °C

    E-Print Network [OSTI]

    International Electrotechnical Commission. Geneva

    2004-01-01T23:59:59.000Z

    Specifies the test methods for filling compounds of electric cables used with telecommunication equipment. Gives the methods for drop-point, separation of oil, lower temperature brittleness, total acid number, absence of corrosive components, permittivity at 23 °C, d.c. resistivity at 23°C and 100°C.

  14. Processing of Activated Core Components

    SciTech Connect (OSTI)

    Friske, A.; Gestermann, G.; Finkbeiner, R.

    2003-02-26T23:59:59.000Z

    Used activated components from the core of a NPP like control elements, water channels from a BWR, and others like in-core measurement devices need to be processed into waste forms suitable for interim storage, and for the final waste repository. Processing of the activated materials can be undertaken by underwater cutting and packaging or by cutting and high-pressure compaction in a hot cell. A hot cell is available in Germany as a joint investment between GNS and the Karlsruhe Research Center at the latter's site. Special transport equipment is available to transport the components ''as-is'' to the hot cell. Newly designed underwater processing equipment has been designed, constructed, and operated for the special application of NPP decommissioning. This equipment integrates an underwater cutting device with an 80 ton force underwater in-drum compactor.

  15. Community Environmental Monitoring Program (CEMP) Data related to Air, Soil, and Water Monitoring around the Nevada Test Site

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

    The Community Environmental Monitoring Program (CEMP) is a network of 29 monitoring stations located in communities surrounding and downwind of the Nevada Test Site (NTS) that monitor the airborne environment for manmade radioactivity that could result from NTS activities. The network stations, located in Nevada, Utah, and California are comprised of instruments that collect a variety of environmental radiological and meteorological data. The emphasis of the CEMP is to monitor airborne radioactivity and weather conditions, and make the results available to the public. Instrumentation that records these data is connected to a datalogger, and real-time radiation levels or weather conditions can immediately and easily be seen on a display at each station. These data are transmitted via direct or wireless internet connection, landline or cellular phone, or satellite transmission to DRI's Western Regional Climate Center in Reno, Nevada, and are updated as frequently as every 10 minutes on the World Wide Web at http://www.cemp.dri.edu. DOE and DRI also publish the results of the monitoring program and distribute these reports throughout the network community. The reports provide summaries of average values for each station and the entire network, and show deviations from the expected range values. [Copied from the CEMP website (Introduction) at http://www.cemp.dri.edu/cemp/moreinfo.html

  16. Measured Performance and Analysis of Ground Source Heat Pumps for Space Conditioning and for Water Heating in a Low-Energy Test House Operated under Simulated Occupancy Conditions

    SciTech Connect (OSTI)

    Ally, Moonis Raza [ORNL] [ORNL; Munk, Jeffrey D [ORNL] [ORNL; Baxter, Van D [ORNL] [ORNL; Gehl, Anthony C [ORNL] [ORNL

    2012-01-01T23:59:59.000Z

    In this paper we present measured performance and efficiency metrics of Ground Source Heat Pumps (GSHPs) for space conditioning and for water heating connected to a horizontal ground heat exchanger (GHX) loop. The units were installed in a 345m2 (3700ft2) high-efficiency test house built with structural insulated panels (SIPs), operated under simulated occupancy conditions, and located in Oak Ridge, Tennessee (USA) in US Climate Zone 4 . The paper describes distinctive features of the building envelope, ground loop, and equipment, and provides detailed monthly performance of the GSHP system. Space conditioning needs of the house were completely satisfied by a nominal 2-ton (7.0 kW) water-to-air GSHP (WA-GSHP) unit with almost no auxiliary heat usage. Recommendations for further improvement through engineering design changes are identified. The comprehensive set of data and analyses demonstrate the feasibility and practicality of GSHPs in residential applications and their potential to help achieve source energy and greenhouse gas emission reduction targets set under the IECC 2012 Standard.

  17. Superclean coal-water slurry combustion testing in an oil-fired boiler. Quarterly technical progress report, November 15, 1989--February 15, 1990

    SciTech Connect (OSTI)

    Miller, B.G.; Walsh, P.M.; Elston, J.T.; Scaroni, A.W.

    1990-04-06T23:59:59.000Z

    The Pennsylvania State University is conducting a superclean coal-water slurry (SCCWS) program for the US Department of Energy (DOE) and the Commonwealth of Pennsylvania with the objective of demonstrating the capability of effectively firing SCCWS in industrial boilers designed for oil. Penn State has entered into a cooperative agreement with DOE to determine if SCCWS (a fuel containing coal with less than 3% ash and 0.9% sulfur) can effectively be burned in oil-designed industrial boilers without adverse impact on boiler rating, maintainability, reliability, and availability. The project will provide information on the design of new systems specifically configured to fire these clean coal-based fuels. The project consists of three phases: (1) design, permitting, and test planning, (2) construction and start up, and (3) operations and disposition. The boiler testing will determine if the SCCWS combustion characteristics, heat release rate, slagging and fouling factors, erosion and corrosion limits, and fuel transport, storage, and handling can be accommodated in an oil-designed boiler. In addition, the proof-of-concept demonstration will generate data to determine how the properties of SCCWS and its parent coal affect boiler performance. Economic factors associated with retrofitting and operating boilers will be identified to assess the viability of future oil-to-coal retrofits. Progress for this quarter is summarized.

  18. Test Automation Test Automation

    E-Print Network [OSTI]

    Mousavi, Mohammad

    Test Automation Test Automation Mohammad Mousavi Eindhoven University of Technology, The Netherlands Software Testing 2013 Mousavi: Test Automation #12;Test Automation Outline Test Automation Mousavi: Test Automation #12;Test Automation Why? Challenges of Manual Testing Test-case design: Choosing inputs

  19. 100-kW class applied-field MPD thruster component wear

    SciTech Connect (OSTI)

    Mantenieks, M.A.; Myers, R.M.

    1993-01-01T23:59:59.000Z

    Component erosion and material deposition sites were identified and analyzed during tests of various configurations of 100 kW class, applied-field, water-cooled magnetoplasmadynamic (MPD) thrusters. Severe erosion of the cathode and the boron nitride insulator was observed for the first series of tests, which was significantly decreased by reducing the levels of propellant contamination. Severe erosion of the copper anode resulting from sputtering by the propellant was also observed. This is the first observation of this phenomenon in MPD thrusters. The anode erosion indicates that development of long life MPD thrusters requires the use of light gas propellants such as hydrogen, deuterium, or lithium.

  20. 100-kW class applied-field thruster component wear

    SciTech Connect (OSTI)

    Mantenieks, M.A. (M.S. SPTD-1, NASA Lewis Research Center, Cleveland, Ohio 44135 (United States)); Myers, R.M. (M.S. SPTD-1, Sverdrup Technology Inc., NASA Lewis Research Center, Cleveland, Ohio 44135 (United States))

    1993-01-20T23:59:59.000Z

    Component erosion and material deposition sites were identified and analyzed during tests of various configurations of 100 kW class, applied-field, water-cooled magnetoplasmadynamic (MPD) thrusters. Severe erosion of the cathode and the boron nitride insulator was observed for the first series of tests, which was significantly decreased by reducing the levels of propellant contamination. Severe erosion of the copper anode resulting from sputtering by the propellant was also observed. This is the first observation of this phenomenon in MPD thrusters. The anode erosion indicates that development of long life MPD thrusters requires the use of light gas propellants such as hydrogen, deuterium, or lithium.

  1. Transverse Component Acknowledgements

    E-Print Network [OSTI]

    , 232-237. Raw Data Radial Component Analysis of Treasure Island earthquake data using seismic by Treasure Island Geotechnical Array near San Francisco, California on 06/26/94. It was a magnitude 4

  2. LMFBR fuel component costs

    SciTech Connect (OSTI)

    Epperson, E.M.; Borisch, R.R.; Rice, L.H.

    1981-10-29T23:59:59.000Z

    A significant portion of the cost of fabricating LMFBR fuels is in the non-fuel components such as fuel pin cladding, fuel assembly ducts and end fittings. The contribution of these to fuel fabrication costs, based on FFTF experience and extrapolated to large LMFBR fuel loadings, is discussed. The extrapolation considers the expected effects of LMFBR development programs in progress on non-fuel component costs.

  3. Watts nickel and rinse water recovery via an advanced reverse osmosis system

    SciTech Connect (OSTI)

    Schmidt, C.; White, I.E.; Ludwig, R.

    1993-08-01T23:59:59.000Z

    The report summarizes the results of an eight month test program conducted at the Hewlett Packard Printed Circuit Board Production Plant, Sunnyvale, CA (H.P.) to assess the effectiveness of an advanced reverse osmosis system (AROS). The AROS unit, manufactured by Water Technologies, Inc. (WTI) of Minneapolis, MN, incorporates membrane materials and system components designed to treat metal plating rinse water and produce two product streams; (1) a concentrated metal solution suitable for the plating bath, and (2) rinse water suitable for reuse as final rinse. Waste water discharge can be virtually eliminated and significant reductions realized in the need for new plating bath solution and rinse water.

  4. A User’s Guide to the Comprehensive Water Quality Database for Groundwater in the Vicinity of the Nevada Test Site, Rev. No.: 1

    SciTech Connect (OSTI)

    Farnham, Irene

    2006-09-01T23:59:59.000Z

    This water quality database (viz.GeochemXX.mdb) has been developed as part of the Underground Test Area (UGTA) Program with the cooperation of several agencies actively participating in ongoing evaluation and characterization activities under contract to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). The database has been constructed to provide up-to-date, comprehensive, and quality controlled data in a uniform format for the support of current and future projects. This database provides a valuable tool for geochemical and hydrogeologic evaluations of the Nevada Test Site (NTS) and surrounding region. Chemistry data have been compiled for groundwater within the NTS and the surrounding region. These data include major ions, organic compounds, trace elements, radionuclides, various field parameters, and environmental isotopes. Colloid data are also included in the database. The GeochemXX.mdb database is distributed on an annual basis. The extension ''XX'' within the database title is replaced by the last two digits of the release year (e.g., Geochem06 for the version released during the 2006 fiscal year). The database is distributed via compact disc (CD) and is also uploaded to the Common Data Repository (CDR) in order to make it available to all agencies with DOE intranet access. This report provides an explanation of the database configuration and summarizes the general content and utility of the individual data tables. In addition to describing the data, subsequent sections of this report provide the data user with an explanation of the quality assurance/quality control (QA/QC) protocols for this database.

  5. ANAEROBIC BIOLOGICAL TREATMENT OF PRODUCED WATER

    SciTech Connect (OSTI)

    John R. Gallagher

    2001-07-31T23:59:59.000Z

    During the production of oil and gas, large amounts of water are brought to the surface and must be disposed of in an environmentally sensitive manner. This is an especially difficult problem in offshore production facilities where space is a major constraint. The chief regulatory criterion for produced water is oil and grease. Most facilities have little trouble meeting this criterion using conventional oil-water separation technologies. However, some operations have significant amounts of naphthenic acids in the water that behave as oil and grease but are not well removed by conventional technologies. Aerobic biological treatment of naphthenic acids in simulated-produced water has been demonstrated by others; however, the system was easily overloaded by the large amounts of low-molecular-weight organic acids often found in produced waters. The objective of this research was to determine the ability of an anaerobic biological system to treat these organic acids in a simulated produced water and to examine the potential for biodegradation of the naphthenic acids in the anaerobic environment. A small fixed-film anaerobic biological reactor was constructed and adapted to treat a simulated produced water. The bioreactor was tubular, with a low-density porous glass packing material. The inocula to the reactor was sediment from a produced-water holding pond from a municipal anaerobic digester and two salt-loving methanogenic bacteria. During start-up, the feed to the reactor contained glucose as well as typical produced-water components. When glucose was used, rapid gas production was observed. However, when glucose was eliminated and the major organic component was acetate, little gas was generated. Methane production from acetate may have been inhibited by the high salt concentrations, by sulfide, or because of the lack, despite seeding, of microbes capable of converting acetate to methane. Toluene, a minor component of the produced water (0.1 g/L) was removed in the reactor. Batch tests were conducted to examine naphthenic acid biodegradability under several conditions. The conditions used were seed from the anaerobic reactor, wetland sediments under aerobic and anaerobic conditions, and a sterile control. The naphthenic acid was from a commercial source isolated from Gulf Coast petroleum as was dosed at 2 mg/mL. The incubations were for 30 days at 30 C. The results showed that the naphthenic acids were not biodegraded under anaerobic conditions, but were degraded under aerobic conditions. Despite poor performance of the anaerobic reactor, it remains likely that anaerobic treatment of acetate, toluene, and, potentially, other produced-water components is feasible.

  6. Colorado State University program for developing, testing, evaluating and optimizing solar heating and cooling systems. Project status report, January--February 1992

    SciTech Connect (OSTI)

    Not Available

    1992-03-23T23:59:59.000Z

    The objective is to develop and test various integrated solar heating, cooling and domestic hot water systems, and to evaluate their performance. Systems composed of new, as well as previously tested, components are carefully integrated so that effects of new components on system performance can be clearly delineated. The SEAL-DOE program includes six tasks which have received funding for the 1991--92 fifteen-month period. These include: (1) a project employing isothermal operation of air and liquid solar space heating systems, (2) a project to build and test several generic solar water heaters, (3) a project that will evaluate advanced solar domestic hot water components and concepts and integrate them into solar domestic hot water systems, (4) a liquid desiccant cooling system development project, (5) a project that will perform system modeling and analysis work on solid desiccant cooling systems research, and (6) a management task. The objectives and progress in each task are described in this report.

  7. Integrity of neutron-absorbing components of LWR fuel systems

    SciTech Connect (OSTI)

    Bailey, W.J.; Berting, F.M.

    1991-03-01T23:59:59.000Z

    A study of the integrity and behavior of neutron-absorbing components of light-water (LWR) fuel systems was performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE). The components studies include control blades (cruciforms) for boiling-water reactors (BWRs) and rod cluster control assemblies for pressurized-water reactors (PWRs). The results of this study can be useful for understanding the degradation of neutron-absorbing components and for waste management planning and repository design. The report includes examples of the types of degradation, damage, or failures that have been encountered. Conclusions and recommendations are listed. 84 refs.

  8. Cygnus Water Switch Jitter

    SciTech Connect (OSTI)

    Charles V. Mitton, George D. Corrow, Mark D. Hansen, David J. Henderson, et al.

    2008-03-01T23:59:59.000Z

    The Cygnus Dual Beam Radiographic Facility consists of two identical radiographic sources - Cygnus 1 and Cygnus 2. Each source has the following x-ray output: 1-mm diameter spot size, 4 rad at 1 m, 50-ns Full Width Half Max. The diode pulse has the following electrical specifications: 2.25 MV, 60 kA, 60 ns. This Radiographic Facility is located in an underground tunnel test area at the Nevada Test Site (NTS). The sources were developed to produce high-resolution images on subcritical tests which are performed at NTS. Subcritical tests are single-shot, high-value events. For this application, it is desirable to maintain a high level of reproducibility in source output. The major components of the Cygnus machines are: Marx generator, water-filled pulse–forming line (PFL), water-filled coaxial transmission line, three-cell inductive voltage adder, and rod-pinch diode. A primary source of fluctuation in Cygnus shot-to-shot performance is jitter in breakdown of the main PFL switch, which is a “self-break” switch. The PFL switch breakdown time determines the peak PFL charging voltage, which ultimately affects the diode pulse. Therefore, PFL switch jitter contributes to shot-to-shot variation in source endpoint energy and dose. In this paper we will present PFL switch jitter analysis for both Cygnus machines and give the correlation with diode performance. For this analysis the PFL switch on each machine was maintained at a single gap setting which has been used for the majority of shots at NTS. In addition to this analysis, PFL switch performance for different switch gap settings taken recently will be examined. Lastly, implications of source jitter for radiographic diagnosis of subcritical shots will be discussed.

  9. Investigation of the condition of spent-fuel pool components

    SciTech Connect (OSTI)

    Kustas, F.M.; Bates, S.O.; Opitz, B.E.; Johnson, A.B. Jr.; Perez, J.M. Jr.; Farnsworth, R.K.

    1981-09-01T23:59:59.000Z

    It is currently projected that spent nuclear fuel, which is discharged from the reactor and then stored in water pools, may remain in those pools for several decades. Other studies have addressed the expected integrity of the spent fuel during extended water storage; this study assesses the integrity of metallic spent fuel pool components. Results from metallurgical examinations of specimens taken from stainless steel and aluminum components exposed in spent fuel pools are presented. Licensee Event Reports (LERs) relating to problems with spent fuel components were assessed and are summarized to define the types of operational problems that have occurred. The major conclusions of this study are: aluminum and stainless steel spent fuel pool components have a good history of performance in both deionized and borated water pools. Although some operational problems involving pool components have occurred, these problems have had minimal impacts.

  10. Degradation mechanisms and accelerated testing in PEM fuel cells

    SciTech Connect (OSTI)

    Borup, Rodney L [Los Alamos National Laboratory; Mukundan, Rangachary [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    The durability of PEM fuel cells is a major barrier to the commercialization of these systems for stationary and transportation power applications. Although there has been recent progress in improving durability, further improvements are needed to meet the commercialization targets. Past improvements have largely been made possible because of the fundamental understanding of the underlying degradation mechanisms. By investigating component and cell degradation modes; defining the fundamental degradation mechanisms of components and component interactions new materials can be designed to improve durability. Various factors have been shown to affect the useful life of PEM fuel cells. Other issues arise from component optimization. Operational conditions (such as impurities in either the fuel and oxidant stream), cell environment, temperature (including subfreezing exposure), pressure, current, voltage, etc.; or transient versus continuous operation, including start-up and shutdown procedures, represent other factors that can affect cell performance and durability. The need for Accelerated Stress Tests (ASTs) can be quickly understood given the target lives for fuel cell systems: 5000 hours ({approx} 7 months) for automotive, and 40,000 hrs ({approx} 4.6 years) for stationary systems. Thus testing methods that enable more rapid screening of individual components to determine their durability characteristics, such as off-line environmental testing, are needed for evaluating new component durability in a reasonable turn-around time. This allows proposed improvements in a component to be evaluated rapidly and independently, subsequently allowing rapid advancement in PEM fuel cell durability. These tests are also crucial to developers in order to make sure that they do not sacrifice durability while making improvements in costs (e.g. lower platinum group metal [PGM] loading) and performance (e.g. thinner membrane or a GDL with better water management properties). To achieve a deeper understanding and improve PEM fuel cell durability LANL is conducting research to better define fuel cell component degradation mechanisms and correlate AST measurements to component in 'real-world' situations.

  11. Solid state lighting component

    DOE Patents [OSTI]

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

    2010-10-26T23:59:59.000Z

    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.

  12. Solid state lighting component

    DOE Patents [OSTI]

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

    2012-07-10T23:59:59.000Z

    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.

  13. Injection molded component

    DOE Patents [OSTI]

    James, Allister W; Arrell, Douglas J

    2014-09-30T23:59:59.000Z

    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.

  14. Water Resources Water Quality and Water Treatment

    E-Print Network [OSTI]

    Sohoni, Milind

    Water Resources TD 603 Lecture 1: Water Quality and Water Treatment CTARA Indian Institute of Technology, Bombay 2nd November, 2011 #12;OVERVIEW Water Quality WATER TREATMENT PLANTS WATER TREATMENT PLANTS WATER TREATMENT PLANTS WATER TRE OVERVIEW OF THE LECTURE 1. Water Distribution Schemes Hand Pump

  15. Design of thermal control systems for testing of electronics

    E-Print Network [OSTI]

    Sweetland, Matthew, 1970-

    2001-01-01T23:59:59.000Z

    In the electronic component manufacturing industry, most components are subjected to a full functional test before they are sold. Depending on the type of components, these functional tests may be performed at room ...

  16. In-reactor oxidation of zircaloy-4 under low water vapor pressures

    SciTech Connect (OSTI)

    Walter G. Luscher; David J. Senor; Keven K. Clayton; Glen R. Longhurst

    2015-01-01T23:59:59.000Z

    Complementary in- and ex-reactor oxidation tests have been performed to evaluate the oxidation and hydrogen absorption performance of Zircaloy-4 (Zr-4) under relatively low partial pressures (300 and 1000 Pa) of water vapor at specified test temperatures (330 and 370 C). Data from these tests will be used to support the fabrication of components intended for isotope-producing targets and provide information regarding the temperature and pressure dependence of oxidation and hydrogen absorption of Zr- 4 over the specified range of test conditions. Comparisons between in- and ex-reactor test results were performed to evaluate the influence of irradiation.

  17. Comparison of EC-Kit with Quanti-Tray[tm] : testing, verification, and drinking water quality mapping in Capiz Province, Philippines

    E-Print Network [OSTI]

    Chuang, Patty

    2010-01-01T23:59:59.000Z

    This thesis accomplishes three tasks. First, it verifies the EC-Kit under different water source conditions by comparing it to a laboratory standard method, the IDEXX Quanti-Tray[tm]. The EC-Kit is a simple, inexpensive ...

  18. 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.

    1999-01-01T23:59:59.000Z

    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.

  19. Sprayed skin turbine component

    DOE Patents [OSTI]

    Allen, David B

    2013-06-04T23:59:59.000Z

    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.

  20. Component failure data handbook

    SciTech Connect (OSTI)

    Gentillon, C.D.

    1991-04-01T23:59:59.000Z

    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.

  1. RAMA Surveillance Capsule and Component Activation Analyses

    SciTech Connect (OSTI)

    Watkins, Kenneth E.; Jones, Eric N. [TransWare Enterprises Inc., 1565 Mediterranean Dr., Sycamore, IL 60178 (United States); Carter, Robert G. [Electric Power Research Institute, 1300 West W. T. Harris Blvd., Charlotte, NC 28262 (United States)

    2011-07-01T23:59:59.000Z

    This paper presents the calculated-to-measured ratios associated with the application of the RAMA Fluence Methodology software to light water reactor surveillance capsule and reactor component activation evaluations. Comparisons to measurements are performed for pressurized water reactor and boiling water reactor surveillance capsule activity specimens from seventeen operating light water reactors. Comparisons to measurements are also performed for samples removed from the core shroud, top guide, and jet pump brace pads from two reactors. In conclusion: The flexible geometry modeling capabilities provided by RAMA, combined with the detailed representation of operating reactor history and anisotropic scattering detail, produces accurate predictions of the fast neutron fluence and neutron activation for BWR and PWR surveillance capsule geometries. This allows best estimate RPV fluence to be determined without the need for multiplicative bias corrections. The three-dimensional modeling capability in RAMA provides an accurate estimate of the fast neutron fluence for regions far removed from the core mid-plane elevation. The comparisons to activation measurements for various core components indicate that the RAMA predictions are reasonable, and notably conservative (i.e., C/M ratios are consistently greater than unity). It should be noted that in the current evaluations, the top and bottom fuel regions are represented by six inch height nodes. As a result, the leakage-induced decrease in power near the upper and lower edges of the core are not well represented in the current models. More precise predictions of fluence for components that lie above and below the core boundaries could be obtained if the upper and lower fuel nodes were subdivided into multiple axial regions with assigned powers that reflect the neutron leakage at the top and bottom of the core. This use of additional axial sub-meshing at the top and bottom of the core is analogous to the use of pin-wise meshing in peripheral bundles to accurately represent radial leakage effects. The representation of thermal neutron fluence and activations are found to be reasonably accurate and consistently conservative, as demonstrated by comparison to the reactor component thermal neutron reaction activation measurements. Further improvement in the comparisons to measurements could be achieved by exploring the impact of enhanced sub-meshing of the geometry near the components of interest. The mesh densities utilized in the current evaluation are consistent with the mesh requirements for high energy neutron transport. The substantially shorter transport lengths for thermal neutrons relative to high energy neutrons suggests that localized regions of finer meshing are needed in the vicinity of those reactor components requiring thermal neutron fluence evaluations. (authors)

  2. Water quality and business aspects of sachet-vended water in Tamale, Ghana

    E-Print Network [OSTI]

    Okioga, Teshamulwa (Teshamulwa Irene)

    2007-01-01T23:59:59.000Z

    Microbial water quality analyses were conducted on 15 samples of factory-produced sachet water and 15 samples of hand-tied sachet water, sold in Tamale, Ghana. The tests included the membrane filtration (MF) test using ...

  3. Impacts of Imported Liquefied Natural Gas on Residential Appliance Components: Literature Review

    E-Print Network [OSTI]

    Lekov, Alex

    2010-01-01T23:59:59.000Z

    Fundamentals of Gas Combustion. 2001: Washington, DC. 131Components A gas appliance combustion system accomplishestransfers energy from hot combustion gases to water or air

  4. Soil Testing and Research

    E-Print Network [OSTI]

    Ciocan-Fontanine, Ionut

    Soil Testing and Research Analytical Laboratory Copyright © 2014 University of Minnesota Soil Testing and Research Analytical Laboratory Department of Soil, Water and Climate College of Food payable to the University of Minnesota We also accept the following credit cards: Soil Testing

  5. Evaluation and silicon nitride internal combustion engine components

    SciTech Connect (OSTI)

    Voldrich, W. (Allied-Signal Aerospace Co., Torrance, CA (United States). Garrett Ceramic Components Div.)

    1992-04-01T23:59:59.000Z

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

  6. High Efficiency Hydrogen Production from Nuclear Energy: Laboratory Demonstration of S-I Water-Splitting

    SciTech Connect (OSTI)

    Buckingham, R.; Russ, B.; Brown, L.; Besenbruch, G.E.; Gelbard, F.; Pickard F.S.; Leybros, J.; Le Duigou, A.; Borgard, J.M.

    2004-11-30T23:59:59.000Z

    The objective of the French CEA, US-DOE INERI project is to perform a lab scale demonstration of the sulfur iodine (S-I) water splitting cycle, and assess the potential of this cycle for application to nuclear hydrogen production. The project will design, construct and test the three major component reaction sections that make up the S-I cycle. The CEA will design and test the prime (Bunsen) reaction section. General Atomics will develop and test the HI decomposition section, and SNL will develop and test the H2SO4 decomposition section. Activities for this period included initial program coordination and information exchange, the development of models and analyses that will support the design of the component sections, and preliminary designs for the component reaction sections. The sections are being designed to facilitate integration into a closed loop demonstration in a later stage of the program.

  7. Automotive Component Product Development Enhancement

    E-Print Network [OSTI]

    Automotive Component Product Development Enhancement Through Multi-Attribute System Design Engineering Systems Division #12;Automotive Component Product Development Enhancement Through Multi of Science in Engineering and Management February 2005 ABSTRACT Automotive industry is facing a tough period

  8. Biointrusion test plan for the Permanent Isolation Surface Barrier Prototype

    SciTech Connect (OSTI)

    Link, S.O.; Cadwell, L.L.; Brandt, C.A.; Downs, J.L.; Rossi, R.E.; Gee, G.W.

    1994-04-01T23:59:59.000Z

    This document provides a testing and monitoring plan for the biological component of the prototype barrier slated for construction at the Hanford Site. The prototype barrier is an aboveground structure engineered to demonstrate the basic features of an earthen cover system. It is designed to permanently isolate waste from the biosphere. The features of the barrier include multiple layers of soil and rock materials and a low-permeability asphalt sublayer. The surface of the barrier consists of silt loam soil, covered with plants. The barrier sides are reinforced with rock or coarse earthen-fill to protect against wind and water erosion. The sublayers inhibit plant and animal intrusion and percolation of water. A series of tests will be conducted on the prototype barrier over the next several years to evaluate barrier performance under extreme climatic conditions. Plants and animals will play a significant role in the hydrologic and water and wind erosion characteristics of the prototype barrier. Studies on the biological component of the prototype barrier will include work on the initial revegetation of the surface, continued monitoring of the developing plant community, rooting depth and dispersion in the context of biointrusion potential, the role of plants in the hydrology of the surface and toe regions of the barrier, the role of plants in stabilizing the surface against water and wind erosion, and the role of burrowing animals in the hydrology and water and wind erosion of the barrier.

  9. 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.

    1992-10-01T23:59:59.000Z

    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.

  10. 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.

    1992-10-01T23:59:59.000Z

    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.

  11. FILTER COMPONENT ASSESSMENT--CERAMIC CANDLES--

    SciTech Connect (OSTI)

    M.A. Alvin

    2004-04-23T23:59:59.000Z

    Efforts at Siemens Westinghouse Power Corporation (SWPC) have been focused on development of hot gas filter systems as an enabling technology for advanced coal and biomass-based gas turbine power generation applications. SWPC has been actively involved in the development of advanced filter materials and component configuration, has participated in numerous surveillance programs characterizing the material properties and microstructure of field tested filter elements, and has undertaken extended, accelerated filter life testing programs. This report summarizes the results of SWPC's filter component assessment efforts, identifying the performance and stability of porous monolithic, fiber reinforced, and filament wound ceramic hot gas candle filters, potentially for {ge}3 years of viable pressurized fluidized-bed combustion (PFBC) service operating life.

  12. Determination of Water Saturation in Relatively Dry Porous Media...

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

    Water Saturation in Relatively Dry Porous Media Using Gas-phase Tracer Tests. Determination of Water Saturation in Relatively Dry Porous Media Using Gas-phase Tracer Tests....

  13. Feasibility study for use of the natural convection shutdown heat removal test facility (NSTF) for VHTR water-cooled RCCS shutdown.

    SciTech Connect (OSTI)

    Tzanos, C.P.; Farmer, M.T.; Nuclear Engineering Division

    2007-08-31T23:59:59.000Z

    In summary, a scaling analysis of a water-cooled Reactor Cavity Cooling System (RCCS) system was performed based on generic information on the RCCS design of PBMR. The analysis demonstrates that the water-cooled RCCS can be simulated at the ANL NSTF facility at a prototypic scale in the lateral direction and about half scale in the vertical direction. Because, by necessity, the scaling is based on a number of approximations, and because no analytical information is available on the performance of a reference water-cooled RCCS, the scaling analysis presented here needs to be 'validated' by analysis of the steady state and transient performance of a reference water-cooled RCCS design. The analysis of the RCCS performance by CFD and system codes presents a number of challenges including: strong 3-D effects in the cavity and the RCCS tubes; simulation of turbulence in flows characterized by natural circulation, high Rayleigh numbers and low Reynolds numbers; validity of heat transfer correlations for system codes for heat transfer in the cavity and the annulus of the RCCS tubes; the potential of nucleate boiling in the tubes; water flashing in the upper section of the RCCS return line (during limiting transient); and two-phase flow phenomena in the water tanks. The limited simulation of heat transfer in cavities presented in Section 4.0, strongly underscores the need of experimental work to validate CFD codes, and heat transfer correlations for system codes, and to support the analysis and design of the RCCS. Based on the conclusions of the scaling analysis, a schematic that illustrates key attributes of the experiment system is shown in Fig. 4. This system contains the same physical elements as the PBMR RCCS, plus additional equipment to facilitate data gathering to support code validation. In particular, the prototype consists of a series of oval standpipes surrounding the reactor vessel to provide cooling of the reactor cavity during both normal and off-normal operating conditions. The standpipes are headered (in groups of four in the prototype) to water supply (header) tanks that are situated well above the reactor vessel to facilitate natural convection cooling during a loss of forced flow event. During normal operations, the water is pumped from a heat sink located outside the containment to the headered inlets to the standpipes. The water is then delivered to each standpipe through a centrally located downcomer that passes the coolant to the bottom of each pipe. The water then turns 180{sup o} and rises up through the annular gap while extracting heat from the reactor cavity due to a combination of natural convection and radiation across the gap between the reactor vessel and standpipes. The water exits the standpipes at the top where it is headered (again in groups of four) into a return line that passes the coolant to the top of the header tank. Coolant is drawn from each tank through a fitting located near the top of the tank where it flows to the heat rejection system located outside the containment. This completes the flow circuit for normal operations. During off-normal conditions, forced convection water cooling in the RCCS is presumed to be lost, as well as the ultimate heat sink outside the containment. In this case, water is passively drawn from an open line located at the bottom of the header tank. This line is orificed so that flow bypass during normal operations is small, yet the line is large enough to provide adequate flow during passive operations to remove decay heat while maintaining acceptable fuel temperatures. In the passive operating mode, water flows by natural convection from the bottom of the supply tank to the standpipes, and returns through the normal pathway to the top of the tanks. After the water reaches saturation and boiling commences, steam will pass through the top of the tanks and be vented to atmosphere. In the experiment system shown in Fig. 4, a steam condensation and collection system is included to quantify the boiling rate, thereby providing additional validation data. This sys

  14. Estimate of the scatter component in SPECT

    SciTech Connect (OSTI)

    Ivanovic, M.; Weber, D.A. [Univ. of California, Sacramento, CA (United States); Loncaric, S. [Univ. of Zagreb (Croatia)

    1996-12-31T23:59:59.000Z

    Analytical expressions that describe the dependence of slopes and amplitudes of the scatter distribution functions (SDF) on source depth and media density are used to estimate a scatter component in SPECT projection data. Since the ratio of detected scattered to total photons (S/T), SDF amplitude and slope depend strongly on line source length (SL) used to obtain SDFs, we compared estimated scattered components using SDFs, obtained for lengths of 2-21 cm. At 10 cm source depth, S/T changes from 0.19 to 0.36 when SL changes from 2 to 21 cm. Scatter amplitude`s dependence on source depth (d) in water was described by 6.38e{sup -0.186d} for a 2 cm and 16.15e{sup -0.129d} for a 21 cm SL. Slope was described by 0.292d{sup -0.601} for a cm SL and by 0.396d{sup -0.82} for a 21 cm SL. The estimated scatter components are compared with simulated SPECT projection data obtained with Monte Carlo modeling of six hot spheres placed in a cylindrical water filled phantom. The comparison of estimated with simulated total counts/projection shows very good agreement when approaching SDF for a point source (the % difference varied from 2 to 13% for 2 cm SL). Significant overestimate is seen when source length increases.

  15. WATER AS A REAGENT FOR SOIL REMEDIATION

    SciTech Connect (OSTI)

    Indira S. Jayaweera; Montserrat Marti-Perez; Jordi Diaz-Ferrero; Angel Sanjurjo

    2001-11-12T23:59:59.000Z

    SRI International conducted experiments in a two-year, two-phase process to develop and evaluate hydrothermal extraction technology, also known as hot water extraction (HWE) technology, to separate petroleum-related contaminants and other hazardous pollutants from soil and sediments. In this process, water with added electrolytes (inexpensive and environmentally friendly) is used as the extracting solvent under subcritical conditions (150-300 C). The use of electrolytes allows us to operate reactors under mild conditions and to obtain high separation efficiencies that were hitherto impossible. Unlike common organic solvents, water under subcritical conditions dissolves both organics and inorganics, thus allowing opportunities for separation of both organic and inorganic material from soil. In developing this technology, our systematic approach was to (1) establish fundamental solubility data, (2) conduct treatability studies with industrial soils, and (3) perform a bench-scale demonstration using a highly contaminated soil. The bench-scale demonstration of the process has shown great promise. The next step of the development process is the successful pilot demonstration of this technology. Once pilot tested, this technology can be implemented quite easily, since most of the basic components are readily available from mature technologies (e.g., steam stripping, soil washing, thermal desorption). The implementation of this technology will revolutionize the conventional use of water in soil remediation technologies and will provide a stand-alone technology for removal of both volatile and heavy components from contaminated soil.

  16. TID Tolerance of Popular CubeSat Components

    E-Print Network [OSTI]

    Kingsbury, Ryan W.

    In this paper we report total dose test results of COTS components commonly used on CubeSats. We investigate a variety of analog integrated circuits, a popular microcontroller (PIC24) as well as SD memory cards

  17. Presence of pathogenic amoebae in power plant cooling waters. Final report, October 15, 1977-September 30, 1979. [Naegleria fowleri

    SciTech Connect (OSTI)

    Tyndall, R.L.; Willaert, E.; Stevens, A.R.

    1981-03-01T23:59:59.000Z

    Cooling-water-associated algae and sediments from five northern and five southern or western electric power plants were tested for the presence of pathogenic amoebae. In addition, water algae and sediments from five northern and five southern/western sites not associated with power plants were tested. There was a significant correlation at northern power plants between the presence of thermophilic, pathogenic amoebae in cooling waters and thermal additions. Presence of the pathogenic did not correlate with salinity, pH, conductivity, or a variety of various chemical components of the cooling waters. Selected pathogenic isolates were tested serologically and were classified as Naegleria fowleri. Although thermal additions were shown to be contributing factor in predisposing cooling waters to the growth of pathogenic amoebae, the data suggest the involvement of other currently undefined parameters associated with the presence of the pathogenic amoebae. 35 refs., 21 tabs.

  18. Enabling Technologies for Ceramic Hot Section Components

    SciTech Connect (OSTI)

    Venkat Vedula; Tania Bhatia

    2009-04-30T23:59:59.000Z

    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 components for gas turbine engines. Significant technical progress has been made towards maturation of the EBC and CMC technologies for incorporation into gas turbine engine hot-section. Promising EBC candidates for longer life and/or higher temperature applications relative to current state of the art BSAS-based EBCs have been identified. These next generation coating systems have been scaled-up from coupons to components and are currently being field tested in Solar Centaur 50S engine. CMC combustor liners were designed, fabricated and tested in a FT8 sector rig to demonstrate the benefits of a high temperature material system. Pretest predictions made through the use of perfectly stirred reactor models showed a 2-3x benefit in CO emissions for CMC versus metallic liners. The sector-rig test validated the pretest predictions with >2x benefit in CO at the same NOx levels at various load conditions. The CMC liners also survived several trip shut downs thereby validating the CMC design methodology. Significant technical progress has been made towards incorporation of ceramic matrix composites (CMC) and environmental barrier coatings (EBC) technologies into gas turbine engine hot-section. The second phase of the program focused on the demonstration of a reverse flow annular CMC combustor. This has included overcoming the challenges of design and fabrication of CMCs into 'complex' shapes; developing processing to apply EBCs to 'engine hardware'; testing of an advanced combustor enabled by CMCs in a PW206 rig; and the validation of performance benefits against a metal baseline. The rig test validated many of the pretest predictions with a 40-50% reduction in pattern factor compared to the baseline and reductions in NOx levels at maximum power conditions. The next steps are to develop an understanding of the life limiting mechanisms in EBC and CMC materials, developing a design system for EBC coated CMCs and durability testing in an engine environment.

  19. Fusion Test Facilities John Sheffield

    E-Print Network [OSTI]

    Fusion Test Facilities John Sheffield ISSE - University of Tennessee FPA meeting Livermore December Stambaugh, and their colleagues #12;Destructive Testing · It is common practice to test engineered components to destruction prior to deployment of a system e.g., - Automobile crash tests - Airplane wing

  20. Cost analysis of revisions to 10 CFR Part 50, Appendix J, leak tests for primary and secondary containments of light-water-cooled nuclear power plants

    SciTech Connect (OSTI)

    Sciacca, F.; Nelson, W.; Simpkins, B.; Riordan, B.; Godfrey, P.; Cohen, S.; Beal, S.; Goldin, D.

    1985-09-01T23:59:59.000Z

    The report examines the differences between the existing and proposed Appendix J and identifies eleven substantive areas where quantifiable impacts will likely result. The analysis indicated that there are four areas of change which tend to dominate all others in terms of cost impacts. The applicable paragraph numbers from Draft E2 of the Appendix J revision and the nature of the change follows: III.A(4) and III.A(6) - Test Pressure and Testing at Reduced Pressure No Longer Allowed; III.A(7)(b)(i) Acceptance Criteria 1.0 L/sub a/ Acceptable ''As Found'' Leakage; III.A(8)(2) Retesting Following Failure of ''As Found'' Type A Test - Corrective Action Plan, and III.A(8)(b)(ii) Option To Do More Frequent Type B and C Testing Rather Than More Type A Penalty Tests. The best estimate is that the proposed Appendix J would result in a cost savings ranging from about $100 million to $160 million, and increase routing occupational exposure on the order of 10,000 person-rem. These estimates capture the total impact to industry and the NRC over the assumed operating life of all existing and planned future power reactors. All dollar impacts projected to occur in future years have been present worthed at discount rates ranging from 5% to 10%.

  1. Water Loss Test Results for the Pipeline Units: I-19/I-18, I-7A, and I-22 Hidalgo County Irrigation District No. 2

    E-Print Network [OSTI]

    Fipps, G.; Leigh, E.

    ...................................................... ..9 Acknowledgements........................................................................................................................................... 13 List of Figures Figure 1. Photo of leaking pipeline control structure... I-19/I-18 52080 63653 58.4 71.3 SJ17 I-7A 50193 61347 56.2 68.7 J18 I-22 36490 44599 40.9 50.0 * Water loss rates given are based on an in-service use of 24 hours/day and 365 days/year. Figure 1 shows a leaking pipeline control structure...

  2. DRINKING WATER ON EMPTY RINK WATER ON EMPTY STOMACHD

    E-Print Network [OSTI]

    Srivastava, Kumar Vaibhav

    DRINKING WATER ON EMPTY STOMACH RINK WATER ON EMPTY STOMACHD It is popular in Japan today to drink water immediately after waking up every morning. Furthermore, scientific tests have proven its value.. We publish below a description of use of water for our readers. For old and serious diseases as well

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

    SciTech Connect (OSTI)

    Chance, T.F.

    1996-11-01T23:59:59.000Z

    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.

  4. Fueling Components Testing and Certification | Department of Energy

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

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

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

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement3 Beryllium-Associated6-05.pdfATTENDEEES: Ashley Armstrong, DOEUpDepartmentTestbed |

  6. Testing, Manufacturing, and Component Development Projects | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeEnvironment,Institutes and1Telework Telework The Department'sBlog »

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd: Scope ChangeL-01-06Hot-Humid-BasicHardware inThermal Modelingof

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

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 IndustrialIsadoreConnecticut Regions National11-12, 2005 HighMay 22-23,

  9. Nambe Pueblo Water Budget and Forecasting model.

    SciTech Connect (OSTI)

    Brainard, James Robert

    2009-10-01T23:59:59.000Z

    This report documents The Nambe Pueblo Water Budget and Water Forecasting model. The model has been constructed using Powersim Studio (PS), a software package designed to investigate complex systems where flows and accumulations are central to the system. Here PS has been used as a platform for modeling various aspects of Nambe Pueblo's current and future water use. The model contains three major components, the Water Forecast Component, Irrigation Scheduling Component, and the Reservoir Model Component. In each of the components, the user can change variables to investigate the impacts of water management scenarios on future water use. The Water Forecast Component includes forecasting for industrial, commercial, and livestock use. Domestic demand is also forecasted based on user specified current population, population growth rates, and per capita water consumption. Irrigation efficiencies are quantified in the Irrigated Agriculture component using critical information concerning diversion rates, acreages, ditch dimensions and seepage rates. Results from this section are used in the Water Demand Forecast, Irrigation Scheduling, and the Reservoir Model components. The Reservoir Component contains two sections, (1) Storage and Inflow Accumulations by Categories and (2) Release, Diversion and Shortages. Results from both sections are derived from the calibrated Nambe Reservoir model where historic, pre-dam or above dam USGS stream flow data is fed into the model and releases are calculated.

  10. "Open Water/Closed Water: a filmic portrait of America's disappearing public

    E-Print Network [OSTI]

    Sekelsky, Jeff

    "Open Water/Closed Water: a filmic portrait of America's disappearing public pools" Rachel Johnson space of water as a vital component of the public sphere. My movie features footage and interviews. But ultimately, the film is also a meditation on water itself: the transformative powers the sphere of water can

  11. Ceramic Component Development Process Analysis

    SciTech Connect (OSTI)

    Boss, D.; Sambasivan, S.; Kuehmann, C. [Northwestern Univ., Evanston, IL (United States). Basic Industrial Research Lab.; Faber, K. [Northwestern University, MEAS Materials Science & Engineering, Evanston, IL (United States)

    1996-12-31T23:59:59.000Z

    The development of ceramic components and coatings is critical to the demonstration of advanced fossil energy systems. Ceramic components and coating will play critical role in hot-gas filtration, high- temperature heat exchangers, thermal barrier coatings, and the hot- section of turbines. Continuous-fiber composites (CFCC) are expected to play an increasing role in these applications. This program encompassed five technical areas related to ceramic component development for fossil energy systems.

  12. Innovative Technologies to Manufacture Hybrid Metal Foam/Composite Components

    SciTech Connect (OSTI)

    Carrino, L.; Durante, M.; Franchitti, S. [DIMP, University of Naples 'Federico II', P.le Tecchio, 80-80125 Naples (Italy); Sorrentino, L.; Tersigni, L. [DII, University of Cassino, Via G. Di Biasio, 43-03043 Cassino (Italy)

    2011-01-17T23:59:59.000Z

    The aim of this paper is to verify the technological feasibility to realize hybrid metal-foam/composite component and the mechanical performances of the final structure. The hybrid component is composed by a cylindrical core in aluminum foam, the most used between those commercially available, and an outer layer in epoxy/S2-glass, manufactured by filament winding technology.A set of experimental tests have been carried out, to the aim to estimate the improvement of the hybrid component characteristics, compared to the sum of the single components (metal foam cylinder and epoxy/S2-glass tube).

  13. Durability of ACERT Engine Components

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

    strength data from with FE model "load factors" and stress field to estimate fast fracture strength and fatigue resistance of design component Determination of FE model "load...

  14. Durability of ACERT Engine Components

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

    Accomplishments (continued) * Determine the mechanical properties of airfoils from TiAl turbo wheel. * Provide "real" component database for verification of design and life...

  15. Coal-water slurry fuel combustion testing in an oil-fired industrial boiler. Semiannual technical progress report, February 15--August 15, 1996

    SciTech Connect (OSTI)

    Miller, B.G.; Scaroni, A.W.

    1997-06-03T23:59:59.000Z

    The project consists of four phases: (1) design, permitting, and test planning, (2) construction and start up, (3) demonstration and evaluation (1,000-hour demonstration), and (4) expanded demonstration and evaluation (installing a CWSF preparation circuit, performing baseline tests firing No. 6 fuel oil, and conducting additional CWSF testing). The boiler testing and evaluation will determine if the CWSF combustion characteristics, heat release rate, fouling and slagging behavior, corrosion and erosion tendencies, and fuel transport, storage, and handling characteristics can be accommodated in a boiler system designed to fire heavy fuel oil. In addition, the proof-of-concept demonstration will generate data to determine how the properties of a CWSF and its parent coal affect boiler performance. The economic factors associated with retrofitting boilers is also evaluated. The first three phases have been completed and the combustion performance of the burner that was provided with the boiler did not meet performance goals. A maximum coal combustion efficiency of 95% (compared to a target of 98%) was achieved and natural gas cofiring (15% of the total thermal input) was necessary to maintain a stable flame. Consequently, the first demonstration was terminated after 500 hours. The second CWSF demonstration (Phase 4) was conducted with a proven coal-designed burner. Prior to starting the second demonstration, a CWSF preparation circuit was constructed to provide flexibility in CWSF production. The circuit initially installed involved single-stage grinding. A regrind circuit was recently installed and was evaluated. A burner was installed from ABB Combustion Engineering (ABB/CE) and was used to generate baseline data firing No. 6 fuel oil and fire CWSF. A temporary storage system for No. 6 fuel oil was installed and modifications to the existing CWSF handling and preheating system were made to accommodate No. 6 oil.

  16. taken all o of our test

    E-Print Network [OSTI]

    Duchowski, Andrew T.

    safe and do not act of our test Water Qu ARJWS P Water So The Clem water from South Ca stations t drinking wat al Protection strict standa ria and water pus once a m al and state re treat our wat month and the equirements d ter and theref his report lab to continuou oratory tests o tem is suppli f

  17. taken all o of our test

    E-Print Network [OSTI]

    Duchowski, Andrew T.

    safe and do not act of our test Water Qu ARJWS P Water So The Clem water from South Ca stations t drinking wat al Protection strict standa ria and water pus once a m al and state re treat our wat month and the equirements d ter and theref his report lab to continuou oratory tests o stem is suppli f

  18. Design report on the test system used to assess treatment of trench water from Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Kent, T.E.; Taylor, P.A.

    1992-09-01T23:59:59.000Z

    New liquid waste streams will be generated as a consequence of closure activities at Waste Area Grouping (WAG) 6 at Oak Ridge National Laboratory (ORNL). It is proposed that these waste streams be treated for removal of contaminants by adding them to the ORNL wastewater treatment facilities. Previous bench-scale treatability studies indicate that ORNL treatment operations will adequately remove the contaminants, although additional study is required to characterize the secondary waste materials produced as a result of the treatment. A larger scale treatment system was constructed to produce secondary wastes in the quantities necessary for characterization and US Environmental protection Agency toxicity characteristic leaching procedure (TCLP) testing. The test system is designed to simulate the operation of the ORNL process waste treatment facilities and to treat a mixture of ORNL process wastewater and WAG 6 wastewater at a combined flow rate of 0.5 L/min. The system is designed to produce the necessary quantities of waste sludges and spent carbon for characterization studies and TCLP testing.

  19. Our Environment in Hot Water: Comparing Water Heaters, A Life Cycle Approach Comparing Tank and Tankless Water Heaters in California

    E-Print Network [OSTI]

    Lu, Alison

    2011-01-01T23:59:59.000Z

    Study on Eco-Design of Water Heaters, Van Holstein en Kemnaon Eco-Design of Water Heaters”, Task 5 Report, DefinitionTesting of Tankless Gas Water Heater Performance. Davis

  20. Test Laboratory Instructions (Updated 2/12)

    E-Print Network [OSTI]

    . · Test Laboratory Application for Large Storage Water Heaters ­ this application covers non- instantaneous gas and electric water heaters above 75,000 BTU/h or 12 kW input, respectively. · Test Laboratory://www.energy.ca.gov/appliances/forms/. For commercial refrigeration, large storage water heaters, and plumbing fittings, an example test report must

  1. Standards for Power Electronic Components

    E-Print Network [OSTI]

    Standards for Power Electronic Components and Systems EPE 14 ECCE Europe Dr Peter R. Wilson #12;Session Outline · "Standards for Power Electronic Components and Systems" ­ Peter Wilson, IEEE PELS Electronics ­ where next? · Wide Band Gap Devices ­ SiC, GaN etc... · Transformers (ETTT) · Power Modules

  2. Heat treating of manufactured components

    DOE Patents [OSTI]

    Ripley, Edward B. (Knoxville, TN)

    2012-05-22T23:59:59.000Z

    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.

  3. Work plan for monitor well installation water and sediment sample collection aquifer testing and topographic surveying at the Riverton, Wyoming, UMTRA Project Site

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    Investigations conducted during preparation of the site observational work plan (SOWP) at the Uranium Mill Tailings Remedial Action (UMTRA) Project site support a proposed natural flushing ground water compliance strategy, with institutional controls. However, additional site-specific data are needed to reduce uncertainties in order to confirm the applicability and feasibility of this proposed compliance strategy option. This proposed strategy will be analyzed in the site-specific environmental assessment. The purpose of this work plan is to summarize the data collection objectives to fill those data needs, describe the data collection activities that will be undertaken to meet those objectives, and elaborate on the data quality objectives which define the procedures that will be followed to ensure that the quality of these data meet UMTRA Project needs.

  4. Electrophoretic Clarification of Water

    E-Print Network [OSTI]

    Hiler, E. A.; Lyle, W. M.

    purification by electrochemical means overcame this problem and was successful both operationally and economically. As a result of the experimental testing, an example design of a small semiautomated electrochemical water system is offered which incorporates...

  5. Rocky Mountain Basins Produced Water Database

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

    Historical records for produced water data were collected from multiple sources, including Amoco, British Petroleum, Anadarko Petroleum Corporation, United States Geological Survey (USGS), Wyoming Oil and Gas Commission (WOGC), Denver Earth Resources Library (DERL), Bill Barrett Corporation, Stone Energy, and other operators. In addition, 86 new samples were collected during the summers of 2003 and 2004 from the following areas: Waltman-Cave Gulch, Pinedale, Tablerock and Wild Rose. Samples were tested for standard seven component "Stiff analyses", and strontium and oxygen isotopes. 16,035 analyses were winnowed to 8028 unique records for 3276 wells after a data screening process was completed. [Copied from the Readme document in the zipped file available at http://www.netl.doe.gov/technologies/oil-gas/Software/database.html] Save the Zipped file to your PC. When opened, it will contain four versions of the database: ACCESS, EXCEL, DBF, and CSV formats. The information consists of detailed water analyses from basins in the Rocky Mountain region.

  6. Water Quality

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

    Water Quality Water Quality We protect water quality through stormwater control measures and an extensive network of monitoring wells and stations encompassing groundwater, surface...

  7. Coal slurry letdown valve-concept test phase. Final report

    SciTech Connect (OSTI)

    Collins, E.R. Jr.; Suitor, J.W.

    1984-01-01T23:59:59.000Z

    The results of the concept test phase of a novel pressure letdown device indicate usefulness of the concept. The device, using staged letdown, was designed to minimize erosion damage by minimizing slurry velocities through the pressure restrictions. Tests were performed on air, steam/water and a coal slurry with a flashing component. Two valve sizes were used. Based on the results of these tests, the following conclusions were drawn: (1) the basic operating principle of designing for a constant velocity through the orifice restrictions is correct; (2) multiphase pressure letdown can be modeled; (3) temperature profiles are predictable; and (4) erosion in three-phase flow is a complex phenomenon. Recommendations for further work on the device include: (1) development of a controllable device; (2) correlation of further test data; and (3) study of flow regimes where erosion is minimized. 9 refs., 48 figs., 6 tabs.

  8. High Heat Flux Components Program

    SciTech Connect (OSTI)

    Whitley, J.B.

    1983-01-01T23:59:59.000Z

    Purpose is the development of the technologies necessary to design, build and operate high heat flux components such as actively cooled limiters, divertor collector plates, R.F. antennas, mirror end cells, mirror halo collectors, direct convertor collectors, and neutral beam dumps. These components require an integrated design that considers the plasma-materials interaction (PMI) issues, heat removal problems and materials issues (including possible low Z coatings and claddings). As a general definition, high heat flux components see heat fluxes ranging from 1 to 100 MW/m/sup 2/. Suitable materials include copper and copper alloys.

  9. The John Deere E diesel Test & Research Project

    SciTech Connect (OSTI)

    Fields, Nathan; Mitchell, William E.

    2008-09-23T23:59:59.000Z

    Three non-road Tier II emissions compliant diesel engines manufactured by John Deere were placed on a durability test plan of 2000 hours each at full load, rated speed (FLRS). The fuel was a blend of 10% fuel ethanol and 90% low sulfur #2 diesel fuel. Seven operational failures involving twenty seven fuel system components occurred prior to completion of the intended test plan. Regulated emissions measured prior to component failure indicated compliance to Tier II certification goals for the observed test experience. The program plan included operating three non-road Tier II diesel engines for 2000 hours each monitoring the regulated emissions at 500 hour intervals for changes/deterioration. The program was stopped prematurely due to number and frequency of injection system failures. The failures and weaknesses observed involved injector seat and valve wear, control solenoid material incompatibility, injector valve deposits and injector high pressure seal cavitation erosion. Future work should target an E diesel fuel standard that emphasizes minimum water content, stability, lubricity, cetane neutrality and oxidation resistance. Standards for fuel ethanol need to require water content no greater than the base diesel fuel standard. Lubricity bench test standards may need new development for E diesel.

  10. Durability of ACERT Engine Components

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

    * Tensile creep database of commercial TiAl alloys was generated for probabilistic turbo rotor component design and life prediction Daido HIP TiAl Howmet TiAl 16 Managed by...

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

    SciTech Connect (OSTI)

    John Minihan; Ed Schmidt; Greg Enserro; Melissa Thompson

    2008-06-30T23:59:59.000Z

    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 only NWC part information but also includes technical reference data for over 25 Million electronic and electromechanical commercial and military parts via a data subscription. With the capabilities added to the system through this project, eCIS provides decision support, parts list/BOM analysis, editing, tracking, workflows, reporting, and history/legacy information integrating manufacturer reference, company technical, company business, and design data.

  12. Emissions of metals, chromium and nickel species, and organics from municipal waste-water-sludge incinerators. Volume 7. Site 8 emission-test report: Appendices. Final report, 1989-91

    SciTech Connect (OSTI)

    Segall, R.R.; DeWees, W.G.

    1992-03-01T23:59:59.000Z

    The Site 8 facility is a 24.1 million gallons per day (MGD) secondary biological treatment plant with a 0.1 MGD septage handling facility. The wastewater influent comes from predominantly (90 percent) domestic sources. The treatment facility serves a population of approximately 175,000. All 22 tons per day of sludge solids are dewatered by two belt presses to a concentration of 22 to 25 percent solids. Approximately 15 to 17 tons of solids are dewatered by one press and fed to the fluidized bed incinerator. The air pollution control system associated with this incinerator consists of a water injection venturi, and an impingement tray scrubber. A pilot-scale wet eletrostatic precipitator had been installed and was tested. Volume 7 contains the appendices for volume 6. These are (1) Incinerator and Scrubber Operating Data; (2) Sampling and Analytical Methods; (3) Sample Calculations; (4) Analytical Data and Reports, and (5) Continuous Emission Monitoring Data Calibrations/One-min averages.

  13. Fabrication Control Plan for ORNL RH-LOCA ATF Test Specimens to be Irradiated in the ATR

    SciTech Connect (OSTI)

    Kevin G. Field; Richard Howard; Michael Teague

    2014-06-01T23:59:59.000Z

    The purpose of this fabrication plan is (1) to summarize the design of a set of rodlets that will be fabricated and then irradiated in the Advanced Test Reactor (ATR) and (2) provide requirements for fabrication and acceptance criteria for inspections of the Light Water Reactor (LWR) – Accident Tolerant Fuels (ATF) rodlet components. The functional and operational (F&OR) requirements for the ATF program are identified in the ATF Test Plan. The scope of this document only covers fabrication and inspections of rodlet components detailed in drawings 604496 and 604497. It does not cover the assembly of these items to form a completed test irradiation assembly or the inspection of the final assembly, which will be included in a separate INL final test assembly specification/inspection document. The controls support the requirements that the test irradiations must be performed safely and that subsequent examinations must provide valid results.

  14. In-situ continuous water monitoring system

    DOE Patents [OSTI]

    Thompson, C.V.; Wise, M.B.

    1998-03-31T23:59:59.000Z

    An in-situ continuous liquid monitoring system for continuously analyzing volatile components contained in a water source comprises: a carrier gas supply, an extraction container and a mass spectrometer. The carrier gas supply continuously supplies the carrier gas to the extraction container and is mixed with a water sample that is continuously drawn into the extraction container by the flow of carrier gas into the liquid directing device. The carrier gas continuously extracts the volatile components out of the water sample. The water sample is returned to the water source after the volatile components are extracted from it. The extracted volatile components and the carrier gas are delivered continuously to the mass spectrometer and the volatile components are continuously analyzed by the mass spectrometer. 2 figs.

  15. Field Evaluations of Low-Frequency SAFT-UT on Cast Stainless Steel and Dissimilar Metal Weld Components

    SciTech Connect (OSTI)

    Diaz, Aaron A.; Harris, R. V.; Doctor, Steven R.

    2008-11-01T23:59:59.000Z

    This report documents work performed at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington, and at the Electric Power Research Institute's (EPRI) Nondestructive Examination (NDE) Center in Charlotte, North Carolina, on evalutating a low frequency ultrasonic inspection technique used for examination of cast stainless steel (CSS) and dissimilar metal (DMW) reactor piping components. The technique uses a zone-focused, multi-incident angle, low frequency (250-450 kHz) inspection protocol coupled with the synthetic aperture focusing technique (SAFT). The primary focus of this work is to provide information to the United States Nuclear Regulatory Commission on the utility, effectiveness and reliability of ultrasonic testing (UT) inspection techniques as related to the inservice ultrasonic inspection of coarse grained primary piping components in pressurized water reactors (PWRs).

  16. New Developments in Planning Accelerated Life Tests.

    E-Print Network [OSTI]

    Ma, Haiming

    2009-01-01T23:59:59.000Z

    ??Accelerated life tests (ALTs) are often used to make timely assessments of the life time distribution of materials and components. The goal of many ALTs… (more)

  17. Dynamic characterization of satellite components through non-invasive methods

    SciTech Connect (OSTI)

    Mullins, Joshua G [Los Alamos National Laboratory; Wiest, Heather K [Los Alamos National Laboratory; Mascarenas, David D. L. [Los Alamos National Laboratory; Macknelly, David [INST-OFF/AWE; Park, Gyuhae [Los Alamos National Laboratory

    2010-10-21T23:59:59.000Z

    The rapid deployment of satellites is hindered by the need to flight-qualify their components and the resulting mechanical assembly. Conventional methods for qualification testing of satellite components are costly and time consuming. Furthermore, full-scale vehicles must be subjected to launch loads during testing. This harsh testing environment increases the risk of component damage during qualification. The focus of this research effort was to assess the performance of Structural Health Monitoring (SHM) techniques as a replacement for traditional vibration testing. SHM techniques were applied on a small-scale structure representative of a responsive satellite. The test structure consisted of an extruded aluminum space-frame covered with aluminum shear plates, which was assembled using bolted joints. Multiple piezoelectric patches were bonded to the test structure and acted as combined actuators and sensors. Various methods of SHM were explored including impedance-based health monitoring, wave propagation, and conventional frequency response functions. Using these methods in conjunction with finite element modelling, the dynamic properties of the test structure were established and areas of potential damage were identified and localized. The adequacy of the results from each SHM method was validated by comparison to results from conventional vibration testing.

  18. Vendor System Vulnerability Testing Test Plan

    SciTech Connect (OSTI)

    James R. Davidson

    2005-01-01T23:59:59.000Z

    The Idaho National Laboratory (INL) prepared this generic test plan to provide clients (vendors, end users, program sponsors, etc.) with a sense of the scope and depth of vulnerability testing performed at the INL’s Supervisory Control and Data Acquisition (SCADA) Test Bed and to serve as an example of such a plan. Although this test plan specifically addresses vulnerability testing of systems applied to the energy sector (electric/power transmission and distribution and oil and gas systems), it is generic enough to be applied to control systems used in other critical infrastructures such as the transportation sector, water/waste water sector, or hazardous chemical production facilities. The SCADA Test Bed is established at the INL as a testing environment to evaluate the security vulnerabilities of SCADA systems, energy management systems (EMS), and distributed control systems. It now supports multiple programs sponsored by the U.S. Department of Energy, the U.S. Department of Homeland Security, other government agencies, and private sector clients. This particular test plan applies to testing conducted on a SCADA/EMS provided by a vendor. Before performing detailed vulnerability testing of a SCADA/EMS, an as delivered baseline examination of the system is conducted, to establish a starting point for all-subsequent testing. The series of baseline tests document factory delivered defaults, system configuration, and potential configuration changes to aid in the development of a security plan for in depth vulnerability testing. The baseline test document is provided to the System Provider,a who evaluates the baseline report and provides recommendations to the system configuration to enhance the security profile of the baseline system. Vulnerability testing is then conducted at the SCADA Test Bed, which provides an in-depth security analysis of the Vendor’s system.b a. The term System Provider replaces the name of the company/organization providing the system being evaluated. This can be the system manufacturer, a system user, or a third party organization such as a government agency. b. The term Vendor (or Vendor’s) System replaces the name of the specific SCADA/EMS being tested.

  19. A study on an air-water Stirling engine

    SciTech Connect (OSTI)

    Akayawa, H.; Hirata, M.; Kasayi, N.

    1983-08-01T23:59:59.000Z

    A two-phase two-component Stirling engine using an air-water mixture as a working fluid is presently constructed and tested. This choice of working fluid, instead of usually adopted gases such as hydrogen and helium, is aimed to realize a high volumetric efficiency by high heat transfer coefficients of evaporation and condensation in the heat exchangers. Based upon the results of the performance test of the engine, the effects of the air-water mixture ratio and the heat input are mainly studied and discussed. It is concluded that using a condensable working fluid is an effective measure to improve the performance of the Stirling engine for a comparatively low temperature heat source.

  20. Changing Western water institutions: energy's role

    SciTech Connect (OSTI)

    Brown, F.L.; Roach, F.

    1982-01-01T23:59:59.000Z

    This paper describes the institutional mechanisms through which physical availability of water, historical pattern of water use, and unresolved water issues combine to constrain and channel the energy industry's use of water. These institutional mechanisms include the developing markets for water rights, the legal and administrative structure governing water allocation, the formation of social attitudes about water, and the political process that often implements concensus. Within this context, the narrow physical interpretation commonly given to the question, Is there enough water, broadens greatly to include the institutional dimension that is the most important component of the question.

  1. Optical monitor for water vapor concentration

    DOE Patents [OSTI]

    Kebabian, Paul (Acton, MA)

    1998-01-01T23:59:59.000Z

    A system for measuring and monitoring water vapor concentration in a sample uses as a light source an argon discharge lamp, which inherently emits light with a spectral line that is close to a water vapor absorption line. In a preferred embodiment, the argon line is split by a magnetic field parallel to the direction of light propagation from the lamp into sets of components of downshifted and upshifted frequencies of approximately 1575 Gauss. The downshifted components are centered on a water vapor absorption line and are thus readily absorbed by water vapor in the sample; the upshifted components are moved away from that absorption line and are minimally absorbed. A polarization modulator alternately selects the upshifted components or downshifted components and passes the selected components to the sample. After transmission through the sample, the transmitted intensity of a component of the argon line varies as a result of absorption by the water vapor. The system then determines the concentration of water vapor in the sample based on differences in the transmitted intensity between the two sets of components. In alternative embodiments alternate selection of sets of components is achieved by selectively reversing the polarity of the magnetic field or by selectively supplying the magnetic field to the emitting plasma.

  2. Transducer for downhole drilling components

    DOE Patents [OSTI]

    Hall, David R; Fox, Joe R

    2006-05-30T23:59:59.000Z

    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.

  3. Waste Package Component Design Methodology Report

    SciTech Connect (OSTI)

    D.C. Mecham

    2004-07-12T23:59:59.000Z

    This Executive Summary provides an overview of the methodology being used by the Yucca Mountain Project (YMP) to design waste packages and ancillary components. This summary information is intended for readers with general interest, but also provides technical readers a general framework surrounding a variety of technical details provided in the main body of the report. The purpose of this report is to document and ensure appropriate design methods are used in the design of waste packages and ancillary components (the drip shields and emplacement pallets). The methodology includes identification of necessary design inputs, justification of design assumptions, and use of appropriate analysis methods, and computational tools. This design work is subject to ''Quality Assurance Requirements and Description''. The document is primarily intended for internal use and technical guidance for a variety of design activities. It is recognized that a wide audience including project management, the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission, and others are interested to various levels of detail in the design methods and therefore covers a wide range of topics at varying levels of detail. Due to the preliminary nature of the design, readers can expect to encounter varied levels of detail in the body of the report. It is expected that technical information used as input to design documents will be verified and taken from the latest versions of reference sources given herein. This revision of the methodology report has evolved with changes in the waste package, drip shield, and emplacement pallet designs over many years and may be further revised as the design is finalized. Different components and analyses are at different stages of development. Some parts of the report are detailed, while other less detailed parts are likely to undergo further refinement. The design methodology is intended to provide designs that satisfy the safety and operational requirements of the YMP. Four waste package configurations have been selected to illustrate the application of the methodology during the licensing process. These four configurations are the 21-pressurized water reactor absorber plate waste package (21-PWRAP), the 44-boiling water reactor waste package (44-BWR), the 5 defense high-level radioactive waste (HLW) DOE spent nuclear fuel (SNF) codisposal short waste package (5-DHLWDOE SNF Short), and the naval canistered SNF long waste package (Naval SNF Long). Design work for the other six waste packages will be completed at a later date using the same design methodology. These include the 24-boiling water reactor waste package (24-BWR), the 21-pressurized water reactor control rod waste package (21-PWRCR), the 12-pressurized water reactor waste package (12-PWR), the 5 defense HLW DOE SNF codisposal long waste package (5-DHLWDOE SNF Long), the 2 defense HLW DOE SNF codisposal waste package (2-MC012-DHLW), and the naval canistered SNF short waste package (Naval SNF Short). This report is only part of the complete design description. Other reports related to the design include the design reports, the waste package system description documents, manufacturing specifications, and numerous documents for the many detailed calculations. The relationships between this report and other design documents are shown in Figure 1.

  4. Thermal Systems Process and Components Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01T23:59:59.000Z

    This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Thermal Systems Process and Components Laboratory at the Energy Systems Integration Facility. The focus of the Thermal Systems Process and Components Laboratory at NREL's Energy Systems Integration Facility (ESIF) is to research, develop, test, and evaluate new techniques for thermal energy storage systems that are relevant to utility-scale concentrating solar power plants. The laboratory holds test systems that can provide heat transfer fluids for the evaluation of heat exchangers and thermal energy storage devices. The existing system provides molten salt at temperatures up to 800 C. This unit is charged with nitrate salt rated to 600 C, but is capable of handling other heat transfer fluid compositions. Three additional test bays are available for future deployment of alternative heat transfer fluids such as hot air, carbon dioxide, or steam systems. The Thermal Systems Process and Components Laboratory performs pilot-scale thermal energy storage system testing through multiple charge and discharge cycles to evaluate heat exchanger performance and storage efficiency. The laboratory equipment can also be utilized to test instrument and sensor compatibility with hot heat transfer fluids. Future applications in the laboratory may include the evaluation of thermal energy storage systems designed to operate with supercritical heat transfer fluids such as steam or carbon dioxide. These tests will require the installation of test systems capable of providing supercritical fluids at temperatures up to 700 C.

  5. In-Pile Experiment of a New Hafnium Aluminide Composite Material to Enable Fast Neutron Testing in the Advanced Test Reactor

    SciTech Connect (OSTI)

    Donna Post Guillen; Douglas L. Porter; James R. Parry; Heng Ban

    2010-06-01T23:59:59.000Z

    A new hafnium aluminide composite material is being developed as a key component in a Boosted Fast Flux Loop (BFFL) system designed to provide fast neutron flux test capability in the Advanced Test Reactor. An absorber block comprised of hafnium aluminide (Al3Hf) particles (~23% by volume) dispersed in an aluminum matrix can absorb thermal neutrons and transfer heat from the experiment to pressurized water cooling channels. However, the thermophysical properties, such as thermal conductivity, of this material and the effect of irradiation are not known. This paper describes the design of an in-pile experiment to obtain such data to enable design and optimization of the BFFL neutron filter.

  6. Water Intoxication

    E-Print Network [OSTI]

    Lingampalli, Nithya

    2013-01-01T23:59:59.000Z

    2008, May 14). Too much water raises seizure risk in babies.id=4844 9. Schoenly, Lorry. “Water Intoxication and Inmates:article/246650- overview>. 13. Water intoxication alert. (

  7. Large Component Removal/Disposal

    SciTech Connect (OSTI)

    Wheeler, D. M.

    2002-02-27T23:59:59.000Z

    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.

  8. Primary Components of Binomial Ideals

    E-Print Network [OSTI]

    Eser, Zekiye

    2014-07-11T23:59:59.000Z

    for primary components of special binomial ideals. A feature of this work is that our results are independent of the characteristic of the field. First of all, we analyze the primary decomposition of a special class of binomial ideals, lattice ideals...

  9. Prioritization of reactor control components susceptible to fire damage as a consequence of aging

    SciTech Connect (OSTI)

    Lowry, W.; Vigil, R. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Nowlen, S. [Sandia National Labs., Albuquerque, NM (United States)

    1994-01-01T23:59:59.000Z

    The Fire Vulnerability of Aged Electrical Components Test Program is to identify and assess issues of plant aging that could lead to an increase in nuclear power plant risk because of fires. Historical component data and prior analyses are used to prioritize a list of components with respect to aging and fire vulnerability and the consequences of their failure on plant safety systems. The component list emphasizes safety system control components, but excludes cables, large equipment, and devices encompassed in the Equipment Qualification (EQ) program. The test program selected components identified in a utility survey and developed test and fire conditions necessary to maximize the effectiveness of the test program. Fire damage considerations were limited to purely thermal effects.

  10. Water Quality

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

    of desalination research. The primary technological method of generating additional water supplies is through desalination and enhanced water reuse and recycling technologies....

  11. Load Component Database of Household Appliances and Small Office Equipment

    SciTech Connect (OSTI)

    Lu, Ning; Xie, YuLong; Huang, Zhenyu; Puyleart, Francis; Yang, Steve

    2008-07-24T23:59:59.000Z

    This paper discusses the development of a load component database for household appliances and office equipment. To develop more accurate load models at both transmission and distribution level, a better understanding on the individual behaviors of home appliances and office equipment under power system voltage and frequency variations becomes more and more critical. Bonneville Power Administration (BPA) has begun a series of voltage and frequency tests against home appliances and office equipments since 2005. Since 2006, Researchers at Pacific Northwest National Laboratory has collaborated with BPA personnel and developed a load component database based on these appliance testing results to facilitate the load model validation work for the Western Electricity Coordinating Council (WECC). In this paper, the testing procedure and testing results are first presented. The load model parameters are then derived and grouped. Recommendations are given for aggregating the individual appliance models to feeder level, the models of which are used for distribution and transmission level studies.

  12. Experiential Component Approval Form Concentration in Nanotechnology

    E-Print Network [OSTI]

    Goldberg, Bennett

    Experiential Component Approval Form Concentration in Nanotechnology Return completed form to ENG Plan to complete the experiential component as a requirement for the concentration in Nanotechnology to complete the experiential component for the Nanotechnology Concentration by: Research Experience in Lab

  13. SOFA Component Revision Identification 1 Premysl Brada

    E-Print Network [OSTI]

    SOFA Component Revision Identification 1 Premysl Brada Department of Computer Science versions, component revision numbers and change indications are derived as a well- founded version called "component revisions" and the basic fine-grained "type revisions", can subsequently be used

  14. Component failures that lead to reactor scrams. [PWR; BWR

    SciTech Connect (OSTI)

    Burns, E. T.; Wilson, R. J.; Lim, E. Y.

    1980-04-01T23:59:59.000Z

    This report summarizes the operating experience scram data compiled from 35 operating US light water reactors (LWRs) to identify the principal components/systems related to reactor scrams. The data base utilized to identify the scram causes is developed from a EPRI-utility sponsored survey conducted by SAI coupled with recent data from the USNRC Gray Books. The reactor population considered in this evaluation is limited to 23 PWRs and 12 BWRs because of the limited scope of the program. The population includes all the US NSSS vendors. It is judged that this population accurately characterizes the component-related scrams in LWRs over the first 10 years of plant operation.

  15. Electrochemical sensor for monitoring electrochemical potentials of fuel cell components

    DOE Patents [OSTI]

    Kunz, Harold R. (Vernon, CT); Breault, Richard D. (Coventry, CT)

    1993-01-01T23:59:59.000Z

    An electrochemical sensor comprised of wires, a sheath, and a conduit can be utilized to monitor fuel cell component electric potentials during fuel cell shut down or steady state. The electrochemical sensor contacts an electrolyte reservoir plate such that the conduit wicks electrolyte through capillary action to the wires to provide water necessary for the electrolysis reaction which occurs thereon. A voltage is applied across the wires of the electrochemical sensor until hydrogen evolution occurs at the surface of one of the wires, thereby forming a hydrogen reference electrode. The voltage of the fuel cell component is then determined with relation to the hydrogen reference electrode.

  16. Decant pump assembly and controls qualification testing - test report

    SciTech Connect (OSTI)

    Staehr, T.W., Westinghouse Hanford

    1996-05-02T23:59:59.000Z

    This report summarizes the results of the qualification testing of the supernate decant pump and controls system to be used for in-tank sludge washing in aging waste tank AZ-101. The test was successful and all components are qualified for installation and use in the tank.

  17. Name ___________________________________________ The laboratory website provides access to multiple water use and water quality publications.

    E-Print Network [OSTI]

    to lower water pH) 4. R + Metals + Titration for Drip Irrigation $42.50 per sample 5. R + Metals + Heavy water use and water quality publications. Soil, Water and Forage Testing Laboratory Department of Soil and Crop Sciences Texas AgriLife Extension Service W14 WATER SAMPLE INFORMATION FORM Please submit

  18. Water chemists develop and use water University of NebraskaLincoln

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

    Water chemists develop and use water tests. University of Nebraska­Lincoln The University. Imagine a career... keeping water healthy for people and wildlife engineering systems to get water where it's needed developing water policies and using laws to benefit people and the environment analyzing

  19. Effect of hydrogen bond cooperativity on the behavior of water

    E-Print Network [OSTI]

    Kevin Stokely; Marco G. Mazza; H. Eugene Stanley; Giancarlo Franzese

    2009-08-27T23:59:59.000Z

    Four scenarios have been proposed for the low--temperature phase behavior of liquid water, each predicting different thermodynamics. The physical mechanism which leads to each is debated. Moreover, it is still unclear which of the scenarios best describes water, as there is no definitive experimental test. Here we address both open issues within the framework of a microscopic cell model by performing a study combining mean field calculations and Monte Carlo simulations. We show that a common physical mechanism underlies each of the four scenarios, and that two key physical quantities determine which of the four scenarios describes water: (i) the strength of the directional component of the hydrogen bond and (ii) the strength of the cooperative component of the hydrogen bond. The four scenarios may be mapped in the space of these two quantities. We argue that our conclusions are model-independent. Using estimates from experimental data for H bond properties the model predicts that the low-temperature phase diagram of water exhibits a liquid--liquid critical point at positive pressure.

  20. Nuclear component horizontal seismic restraint

    DOE Patents [OSTI]

    Snyder, Glenn J. (Lynchburg, VA)

    1988-01-01T23:59:59.000Z

    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.

  1. Choosing and Using Safe Water Technologies: Evidence from a Field Experiment in Kenya

    E-Print Network [OSTI]

    Luoto, Jill Emily

    2010-01-01T23:59:59.000Z

    We test whether lack of awareness about water quality ishouseholds lack information about their water quality (thei.e. , they lack information that contaminated water leads

  2. Getting Our Feet Wet: Water Management at Mt. Laguna in Cleveland National Forest

    E-Print Network [OSTI]

    Mumby, William Cade

    2013-01-01T23:59:59.000Z

    Regional Water Quality Control Board, “Watershed Managementof Land Management (BLM) Tests preserve water quality, whichRegional Water Quality Control Board. “Watershed Management

  3. E-Print Network 3.0 - ambient water toxicity Sample Search Results

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

    The most Summary: waters of the toxicity test beakers. Immediate collection and analysis of interstitial water... was necessary. Others have recommended interstitial waters...

  4. Hot Water Draw Patterns in Single-Family Houses: Findings from Field Studies

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    Two Demand Electric Water Heaters for Northeast Utilities.Two Demand Electric Water Heaters for Northeast Utilities.Johnson. Heat Pump Water Heater Field Test: 30 Crispaire

  5. An International Survey of Electric Storage Tank Water Heater Efficiency and Standards

    E-Print Network [OSTI]

    Johnson, Alissa

    2013-01-01T23:59:59.000Z

    Fixed Electric Storage Water Heaters, South African Nationalinternational electric storage water heater test proceduresefficiency of electric storage water heaters, and outlines

  6. Name ___________________________________________ Soil, Water and Forage Testing Laboratory

    E-Print Network [OSTI]

    or effluent samples) should be collected in plastic bottles (16 ounce) with at least 50% headspace Please submit this completed form and payment with samples. Mark each sample bottle with your sample, not just the outside surface. Mix subsamples thoroughly in clean plastic bucket. Transfer sample

  7. Water Management for Evaporatively Cooled Condensers

    E-Print Network [OSTI]

    California at Davis, University of

    Water Management for Evaporatively Cooled Condensers Theresa Pistochini May 23rd, 2012 ResearchAirCapacity,tons Gallons of Water Continuous Test - Outdoor Air 110-115 Deg F Cyclic Test - Outdoor Air 110-115 Deg F #12 AverageWaterHardness(ppm) Cooling Degree Days (60°F Reference) 20% Population 70% Population 10

  8. TREATMENT OF PRODUCED OIL AND GAS WATERS WITH SURFACTANT-MODIFIED ZEOLITE

    SciTech Connect (OSTI)

    Lynn E. Katz; R.S. Bowman; E.J. Sullivan

    2003-11-01T23:59:59.000Z

    Co-produced water from the oil and gas industry accounts for a significant waste stream in the United States. It is by some estimates the largest single waste stream in the country, aside from nonhazardous industrial wastes. Characteristics of produced water include high total dissolved solids content, dissolved organic constituents such as benzene and toluene, an oil and grease component, and chemicals added during the oil-production process. While most of the produced water is disposed via reinjection, some must be treated to remove organic constituents before the water is discharged. Current treatment options are successful in reducing the organic content; however, they cannot always meet the levels of current or proposed regulations for discharged water. Therefore, an efficient, cost-effective treatment technology is needed. Surfactant-modified zeolite (SMZ) has been used successfully to treat contaminated ground water for organic and inorganic constituents. In addition, the low cost of natural zeolites makes their use attractive in water-treatment applications. This report summarizes the work and results of this four-year project. We tested the effectiveness of surfactant-modified zeolite (SMZ) for removal of BTEX with batch and column experiments using waters with BTEX concentrations that are comparable to those of produced waters. The data from our experimental investigations showed that BTEX sorption to SMZ can be described by a linear isotherm model, and competitive effects between compounds were not significant. The SMZ can be readily regenerated using air stripping. We field-tested a prototype SMZ-based water treatment system at produced water treatment facilities and found that the SMZ successfully removes BTEX from produced waters as predicted by laboratory studies. When compared to other existing treatment technologies, the cost of the SMZ system is very competitive. Furthermore, the SMZ system is relatively compact, does not require the storage of potentially hazardous chemicals, and could be readily adapted to an automated system.

  9. DOE Publishes Notice of Proposed Rulemaking for Residential Water...

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

    has published a notice of proposed rulemaking regarding test procedures for residential water heaters and certain commercial water heaters. 78 FR 66201 (November 4, 2013). DOE...

  10. Carbon Fiber Components with Integrated Wiring for Millirobot Prototyping *

    E-Print Network [OSTI]

    Fearing, Ron

    Carbon Fiber Components with Integrated Wiring for Millirobot Prototyping * Ranjana Sahai Erik a simple four bar mechanism as an example. Finally, the tests show that the wiring loop over a flexure the folded stainless steel triangles and polyester flexures. Hence, we decided to use carbon fiber instead

  11. UNSUPERVISED CLUSTERING FOR FAULT DIAGNOSIS IN NUCLEAR POWER PLANT COMPONENTS

    E-Print Network [OSTI]

    Boyer, Edmond

    1 UNSUPERVISED CLUSTERING FOR FAULT DIAGNOSIS IN NUCLEAR POWER PLANT COMPONENTS Piero Baraldi1 of prototypical behaviors. Its performance is tested with respect to an artificial case study and then applied on transients originated by different faults in the pressurizer of a nuclear power reactor. Key Words: Fault

  12. SOLAR RADIATION DURABILITY OF MATERIALS, COMPONENTS AND SYSTEMS FOR PHOTOVOLTAICS

    E-Print Network [OSTI]

    Rollins, Andrew M.

    SOLAR RADIATION DURABILITY OF MATERIALS, COMPONENTS AND SYSTEMS FOR PHOTOVOLTAICS Myles P. Murray 1 exposed photovoltaic materials, is defined as the rate of photodarkening or photobleaching of a material testing. The potential to predict power losses in a photovoltaic system over time caused

  13. Marketing water

    E-Print Network [OSTI]

    Wythe, Kathy

    2008-01-01T23:59:59.000Z

    management, water conservation programs Story by Kathy Wythe tx H2O | pg. 17 public information programs and materials that increase awareness about regional water issues. The company recently opened the TecH2O, a water resource learning center...tx H2O | pg. 16 W ith rapid population growth and the memory of the worst drought in 50 years, cities and groups are promoting programs that educate their constituents about water quality, water conservation, and landscape management. Many...

  14. Solving Water Quality Problems in the Home

    E-Print Network [OSTI]

    Dozier, Monty; McFarland, Mark L.

    2004-02-20T23:59:59.000Z

    If your drinking water comes from a private water well, there are certain procedures you can follow to make sure the water is safe. This publication explains how to get your water tested and, if treatment is necessary, to select the correct...

  15. K West integrated water treatment system subproject safety analysis document

    SciTech Connect (OSTI)

    SEMMENS, L.S.

    1999-02-24T23:59:59.000Z

    This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System.

  16. In-Pile SCC Growth Behavior of Type 304 Stainless Steel in High Temperature Water at JMTR

    SciTech Connect (OSTI)

    Yoshiyuki Kaji; Hirokazu Ugachi; Takashi Tsukada; Yoshinori Matsui; Masao Ohmi [Japan Atomic Energy Agency (Japan); Nobuaki Nagata; Koji Dozaki; Hideki Takiguchi [Japan Atomic Power Company (Japan)

    2006-07-01T23:59:59.000Z

    Irradiation assisted stress corrosion cracking (IASCC) is one of the critical concerns when stainless steel components have been in service in light water reactors (LWRs) for a long period. In general, IASCC can be reproduced on the materials irradiated over a certain threshold fluence level of fast neutron by the post-irradiation examinations (PIEs). It is, however, considered that the reproduced IASCC by PIEs must be carefully compared with the actual IASCC in nuclear power plants, because the actual IASCC occurs in the core under simultaneous effects of radiation, stress and high temperature water environment. In the research field of IASCC, mainly PIEs for irradiated materials have been carried out, because there are many difficulties on SCC tests under neutron irradiation. Hence as a part of the key techniques for in-pile SCC tests, we have embarked on a development of the test technique to obtain information concerning effects of applied stress level, water chemistry, irradiation conditions, etc. A high temperature water loop facility was installed at the Japan Materials Testing Reactor (JMTR) to carry out the in-pile IASCC testing under a framework of cooperative research program between JAERI and the JAPC. In-pile IASCC growth tests have been successfully carried out using the compact tension (CT) type specimens of type 304 stainless steel that had been pre-irradiated up to a neutron fluence level around 1 x 10{sup 25} n/m{sup 2} before the in-pile testing since 2004. The tests were carried out in pure water simulated boiling water reactor (BWR) coolant condition. In the paper, results of the in-pile SCC growth tests will be discussed comparing with the result obtained by PIEs from a viewpoint of the synergistic effects on IASCC. (authors)

  17. Selected component failure rate values from fusion safety assessment tasks

    SciTech Connect (OSTI)

    Cadwallader, L.C.

    1998-09-01T23:59:59.000Z

    This report is a compilation of component failure rate and repair rate values that can be used in magnetic fusion safety assessment tasks. Several safety systems are examined, such as gas cleanup systems and plasma shutdown systems. Vacuum system component reliability values, including large vacuum chambers, have been reviewed. Values for water cooling system components have also been reported here. The report concludes with the examination of some equipment important to personnel safety, atmospheres, combustible gases, and airborne releases of radioactivity. These data should be useful to system designers to calculate scoping values for the availability and repair intervals for their systems, and for probabilistic safety or risk analysts to assess fusion systems for safety of the public and the workers.

  18. Selected Component Failure Rate Values from Fusion Safety Assessment Tasks

    SciTech Connect (OSTI)

    Cadwallader, Lee Charles

    1998-09-01T23:59:59.000Z

    This report is a compilation of component failure rate and repair rate values that can be used in magnetic fusion safety assessment tasks. Several safety systems are examined, such as gas cleanup systems and plasma shutdown systems. Vacuum system component reliability values, including large vacuum chambers, have been reviewed. Values for water cooling system components have also been reported here. The report concludes with the examination of some equipment important to personnel safety, atmospheres, combustible gases, and airborne releases of radioactivity. These data should be useful to system designers to calculate scoping values for the availability and repair intervals for their systems, and for probabilistic safety or risk analysts to assess fusion systems for safety of the public and the workers.

  19. Thermal well-test method

    DOE Patents [OSTI]

    Tsang, Chin-Fu (Albany, CA); Doughty, Christine A. (Berkeley, CA)

    1985-01-01T23:59:59.000Z

    A well-test method involving injection of hot (or cold) water into a groundwater aquifer, or injecting cold water into a geothermal reservoir. By making temperature measurements at various depths in one or more observation wells, certain properties of the aquifer are determined. These properties, not obtainable from conventional well test procedures, include the permeability anisotropy, and layering in the aquifer, and in-situ thermal properties. The temperature measurements at various depths are obtained from thermistors mounted in the observation wells.

  20. Modeling Water Resource Systems under Climate Change: IGSM-WRS

    E-Print Network [OSTI]

    Strzepek, K.

    Through the integration of a Water Resource System (WRS) component, the MIT Integrated Global System Model (IGSM) framework has been enhanced to study the effects of climate change on managed water-resource systems. ...

  1. Analysis of U.S. Water Resources under Climate Change

    E-Print Network [OSTI]

    Blanc, E.

    The MIT Integrated Global System Model (IGSM) framework, extended to include a Water Resource System (WRS) component, is applied to an integrated assessment of effects of alternative climate policy scenarios on U.S. water ...

  2. College of Agriculture and Life Sciences Map of Arizona. Source: Arizona Water Map Poster, 2002, Water Resources Research

    E-Print Network [OSTI]

    Cushing, Jim. M.

    Water Treatment Options Authors: Janick F. Artiola, Ph.D., Department of Soil, Water and Environmental. · Adetaileddiscussionofacceptedhomewatertreatmenttechnologies and home water treatment selection guidelines, based on water quality and user preferences Water Testing Chapter to help determine appropriate water treatment options for home use. © 2004, 2006

  3. Certification of alternative aviation fuels and blend components

    SciTech Connect (OSTI)

    Wilson III, George R. (Southwest Research Institute, 6220 Culebra Road, San Antonio, Texas 78238 (United States)); Edwards, Tim; Corporan, Edwin (United States Air Force Research Laboratory, Wright-Patterson Air Force Base, Ohio 45433 (United States)); Freerks, Robert L. (Rentech, Incorporated, 1331 17th Street, Denver, Colorado 80202 (United States))

    2013-01-15T23:59:59.000Z

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

  4. The Water-Wise Vegetable Garden: An Analysis of the Potential for Irrigation through Rainwater Harvesting in Sunny Northern California

    E-Print Network [OSTI]

    Smith, Adrienne; Esterer-Vogel, Elisabeth

    2009-01-01T23:59:59.000Z

    more suitable to harvesting potable water are Galvalume® and8: Rainwater Harvesting System Components Figure 9: Waterrainwater harvesting can supply adequate quantities of water

  5. Water Transport in PEM Fuel Cells: Advanced Modeling, Material...

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

    Testing, and Design Optimization Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing, and Design Optimization This presentation, which focuses on...

  6. Water Transport in PEM Fuel Cells: Advanced Modeling, Material...

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

    Testing and Design Optimization Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing and Design Optimization Part of a 100 million fuel cell award...

  7. Integrated Water Management Options in the Nebraska Ground Water Management &

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

    ag chemical best management practices 7. soil testing 8. voluntary or mandatory educational programs regulate ground water development (well spacing regulations, well drilling prohibitions) and ground water by implementing the above GMA regulations, well drilling may be halted or conditioned. NRD permits are required

  8. Safe water storage in Kenya's modified clay pot : standardization, tap design, and cost recovery

    E-Print Network [OSTI]

    Young, Suzanne E

    2005-01-01T23:59:59.000Z

    One of the main components necessary for providing safe drinking water for users who lack piped water in the home is the ability to safely store it in the home. Users in the Nyanza Province of Kenya frequently carry water ...

  9. Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2

    SciTech Connect (OSTI)

    Olson, Gail Lynn; Mc Cardell, Richard Keith; Illum, Douglas Brent

    2002-09-01T23:59:59.000Z

    The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.

  10. Guidelines for Developing Soil and Water Management Programs: Irrigated Pecans

    E-Print Network [OSTI]

    Miyamoto, S.

    The book describes the performance of pecan trees; water testing; determining how water quality may affect tree growth; improving drainage; selecting an irrigation system, and water conditioning to manage nutrients. It also describes how to estimate...

  11. Snow water equivalent estimation using blackbox optimization

    E-Print Network [OSTI]

    Alarie et al.

    2011-02-23T23:59:59.000Z

    Feb 23, 2011 ... managing water resources for hydroelectric power generation. SWE over ..... of the surrogate is very low and testing in a parallel environment is.

  12. Evaluation of aging degradation of structural components

    SciTech Connect (OSTI)

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

    1992-03-01T23:59:59.000Z

    Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport reactor, as well as thermal embrittlement of CF-8 cast stainless steel components from the Shippingport and KRB reactors, has been characterized. Increases in Charpy transition temperature (CTT), yield stress, and hardness of the NST material in the low-temperature low-flux environment are consistent with the test reactor data for irradiations at < 232{degrees}C. The shift in CTT is not as severe as that observed in surveillance samples from the High Flux Isotope Reactor (HFIR): however, it shows very good agreement with the results for HFIR A212-B steel irradiated in the Oak Ridge Research Reactor. The results indicate that fluence rate has not effect on radiation embrittlement at rates as low as 2 {times} 10{sup 8} n/cm{sup 2}{center_dot}s at the low operating temperature of the Shippingport NST, i.e., 55{degrees}C. This suggest that radiation damage in Shippingport NST and HFIR surveillance samples may be different because of the neutron spectra and/or Cu and Ni content of the two materials. Cast stainless steel components show relatively modest decreases in fracture toughness and Charpy-impact properties and a small increase in tensile strength. Correlations for estimating mechanical properties of cast stainless steels predict accurate or slightly conservative values for Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of the materials. The kinetics of thermal embrittlement and degree of embrittlement at saturation, i.e., the minimum impact energy achieved after long-term aging, were established from materials that were aged further in the laboratory. The results were consistent with the estimates. The correlations successfully predict the mechanical properties of the Ringhals 2 reactor hot- and crossover-leg elbows (CF-8M steel) after service of {approx}15 y.

  13. Evaluation of aging degradation of structural components

    SciTech Connect (OSTI)

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

    1992-03-01T23:59:59.000Z

    Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport reactor, as well as thermal embrittlement of CF-8 cast stainless steel components from the Shippingport and KRB reactors, has been characterized. Increases in Charpy transition temperature (CTT), yield stress, and hardness of the NST material in the low-temperature low-flux environment are consistent with the test reactor data for irradiations at < 232{degrees}C. The shift in CTT is not as severe as that observed in surveillance samples from the High Flux Isotope Reactor (HFIR): however, it shows very good agreement with the results for HFIR A212-B steel irradiated in the Oak Ridge Research Reactor. The results indicate that fluence rate has not effect on radiation embrittlement at rates as low as 2 {times} 10{sup 8} n/cm{sup 2}{center dot}s at the low operating temperature of the Shippingport NST, i.e., 55{degrees}C. This suggest that radiation damage in Shippingport NST and HFIR surveillance samples may be different because of the neutron spectra and/or Cu and Ni content of the two materials. Cast stainless steel components show relatively modest decreases in fracture toughness and Charpy-impact properties and a small increase in tensile strength. Correlations for estimating mechanical properties of cast stainless steels predict accurate or slightly conservative values for Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of the materials. The kinetics of thermal embrittlement and degree of embrittlement at saturation, i.e., the minimum impact energy achieved after long-term aging, were established from materials that were aged further in the laboratory. The results were consistent with the estimates. The correlations successfully predict the mechanical properties of the Ringhals 2 reactor hot- and crossover-leg elbows (CF-8M steel) after service of {approx}15 y.

  14. Water Conservation and Technology Center, director to focus on statewide water issues

    E-Print Network [OSTI]

    Wythe, Kathy

    2012-01-01T23:59:59.000Z

    WAT E R CONSERVATION & TECHNOLOGY CENTER Securing Our Water Future 28 tx H2O Summer 2012 Story by Kathy Wythe Dr. Calvin Finch, new director of the Water Conservation and Technology Center. #31;e newly established Water Conservation... and Technology Center (WCTC) in San Antonio will accelerate development, testing and adopting of new and innovative technologies to help solve water problems and meet water supply needs for Texas. Dr. Calvin Finch, formerly with the San Antonio Water System...

  15. Test Images

    E-Print Network [OSTI]

    Test Images. I hope to have a set of test images for the course soon. Some images are available now; some will have to wait until I can find another 100-200

  16. Common components of industrial metal-working fluids as sources of carbon for bacterial growth. [Acinetobacter; Pseudomonas

    SciTech Connect (OSTI)

    Foxall-vanAken, S.; Brown, J.A. Jr.; Young, W.; Salmeen, I.; McClure, T.; Napier, S. Jr.; Olsen, R.H.

    1986-06-01T23:59:59.000Z

    Water-based metal-working fluids in large-scale industrial operations consist of many components, but in the most commonly used formulations only three classes of components are present in high enough concentrations that they could, in principle, provide enough carbon to support the high bacterial densities (10/sup 9/ CFU/ml) often observed in contaminated factory fluids. These components are petroleum oil (1 to 5%), petroleum sulfonates (0.1 to 0.5%), and fatty acids (less than 0.1%, mainly linoleic and oleic acids supplied as tall oils). Pure strains of predominating bacteria were isolated from contaminated reservoirs of two metal-working systems and randomly selected 12 strains which were tested in liquid culture for growth with each of the metal-working fluid components as the sole source of carbon. Of the 12 strains, 7 reached high density (10/sup 9/ CFU/ml from an initial inoculum of less than 2 x 10/sup 3/) in 24 h, and 1 strain did the same in 48 h with 0.05% oleic or linoleic acid as the carbon source. These same strains also grew on 1% naphthenic petroleum oil but required up to 72 h to reach densities near 10/sup 8/ CFU/ml. One strain grew slightly and the others not at all on the petroleum sulfonates. The four remaining strains did not grow on any of the components, even though they were among the predominating bacteria in the contaminated system. Of the seven strains that grew best on the fatty acids and on the naphthenic petroleum oil, five were tentatively identified as Acinetobacter species and two were identified as Pseudomonas species. Four of the bacteria that did not grow were tentatively identified as species of Pseudomonas, and one could not be identified.

  17. UNL WATER CENTER WATER CURRENT

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

    ................ Sidney Area Deals with Drought 6................ Water and Electricity Are Inseparable 10's East Campus. "Consolidating administration,faculty and staff and facilities is costeffectiveandper or commercial products constitute endorsement by the U.S. Government. WATER CURRENT Water Center University

  18. UNL WATER CENTER WATER CURRENT

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

    INSIDE UNL WATER CENTER WATER CURRENT PROTECTING NEBRASKAíS WATER RESOURCES THROUGH RESEARCH with a vision, thereís an untapped market using resources right under our feet,î the University of Nebraska outdoors in India, Bangladesh, China and Viet- nam. Thousands of them have been grown to harvest

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

    SciTech Connect (OSTI)

    Voldrich, W. [Allied-Signal Aerospace Co., Torrance, CA (United States). Garrett Ceramic Components Div.

    1992-04-01T23:59:59.000Z

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

  20. IFE Chamber Technology Testing Program In NIF and Chamber Development Test Plan Mohamed A. Abdou

    E-Print Network [OSTI]

    Abdou, Mohamed

    . As ITER serves as a fusion testing facility for magnetic fusion energy (MFE) nuclear technology componentIFE Chamber Technology Testing Program In NIF and Chamber Development Test Plan Mohamed A. Abdou chamber technology testing program in NIF involoving: criteria for evaluation

  1. Drinking Water Implications of Cyanobacteria on the Kansas River to

    E-Print Network [OSTI]

    Page 1 Drinking Water Implications of Cyanobacteria on the Kansas River to WaterOne and other releases from Milford Lake during same period. Drinking Water Utilities become concerned about potential to partner with USGS to fund testing. Testing included treated drinking water from the three utilities

  2. Water Conservation and Water Use Efficiency (Wisconsin)

    Broader source: Energy.gov [DOE]

    Wisconsin has several statutes that promote water conservation and controlled water use, and this legislation establishes mandatory and voluntary programs in water conservation and water use...

  3. Arnold Schwarzenegger WATER HEATERS AND HOT WATER

    E-Print Network [OSTI]

    Arnold Schwarzenegger Governor WATER HEATERS AND HOT WATER DISTRIBUTION SYSTEMS: Lutz J.D. (Lawrence Berkeley National Laboratory). 2008. Water Heaters and Hot Water Distribution

  4. IEA Task 27 BUILDING ENVELOPE COMPONENTS

    E-Print Network [OSTI]

    IEA Task 27 BUILDING ENVELOPE COMPONENTS Performance, durability and sustainability of advanced windows and solar components for building envelopes Energy Performance Assessment Methodology Starting................................................................................................................................................. 3 2 Concepts of Energy Performance Assessment of Building Envelopes

  5. Advanced filters and components for power applications

    E-Print Network [OSTI]

    Neugebauer, Timothy Carl, 1975-

    2004-01-01T23:59:59.000Z

    The objective of this thesis is to improve the high frequency performance of components and filters by better compensating the parasitic effects of practical components. The main application for this improvement is in ...

  6. Battery components employing a silicate binder

    SciTech Connect (OSTI)

    Delnick, Frank M. (Albuquerque, NM); Reinhardt, Frederick W. (Albuquerque, NM); Odinek, Judy G. (Rio Rancho, NM)

    2011-05-24T23:59:59.000Z

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

  7. Ground Water Ground Sky Sky Water Vegetation Ground Vegetation Water

    E-Print Network [OSTI]

    Chen, Tsuhan

    Bear Snow Vegetation RhinoWater Vegetation Ground Water Ground Sky Sky Rhino Water Vegetation Ground Vegetation Water Rhino Water Vegetation Ground Rhino Water Rhino Water Ground Ground Vegetation Water Rhino Vegetation Rhino Vegetation Ground Rhino Vegetation Ground Sky Rhino Vegetation Ground Sky

  8. Evaluation of systems and components for hybrid optical firing sets

    SciTech Connect (OSTI)

    Landry, M.J.; Rupert, J.W.; Mittas, A.

    1989-06-01T23:59:59.000Z

    High-energy density light appears to be a unique energy form that may be used to enhance the nuclear safety of weapon systems. Hybrid optical firing sets (HOFS) utilize the weak-link/strong-link exclusion region concept for nuclear safety; this method is similar to present systems, but uses light to transmit power across the exclusion region barrier. This report describes the assembling, operating, and testing of fourteen HOFS. These firing sets were required to charge a capacitor-discharge unit to 2.0 and 2.5 kV (100 mJ) in less than 1 s. First, we describe the components, the measurement techniques used to evaluate the components, and the different characteristics of the measured components. Second, we describe the HOFS studied, the setups used for evaluating them, and the resulting characteristics. Third, we make recommendations for improving the overall performance and suggest the best HOFS for packaging. 36 refs., 145 figs., 14 tabs.

  9. LONG TERM AGING AND SURVEILLANCE OF 9975 PACKAGE COMPONENTS

    SciTech Connect (OSTI)

    Hoffman, E.; Skidmore, E.; Daugherty, W.; Dunn, K.

    2009-11-10T23:59:59.000Z

    The mission of the 9975 package, originally designed only for transportation of radioactive materials, has been broadened to include storage at the Savannah River Site. Two components of this package, namely the containment vessel O-rings and fiberboard overpack, require continued integrity assessment under the storage conditions. The performance of the components over time is being evaluated using accelerated-aging studies. Compression stress relaxation (CSR) and leak testing are being used to measure the performance of O-rings. The performance of the fiberboard is being evaluated using compression strength, thermal conductivity, specific heat capacity and other physical properties. Models developed from the data collected provide an initial prediction of service life for the two components, and support the conclusion that normal service conditions will not degrade the performance of the package beyond specified functional requirements for the first assessment interval. Increased confidence in this conclusion is derived from field surveillance data and destructive evaluation of packages removed from storage.

  10. Hot Water Draw Patterns in Single-Family Houses: Findings from Field Studies

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    and R.K. Johnson. Heat Pump Water Heater Field Test: 30a Market-Optimized Heat- Pump Water Heater. Prepared by TIAXcost savings of heat pump water heaters Field test of

  11. Tools to Implement MPDV Component Characteristics

    SciTech Connect (OSTI)

    Pena, M; Daykin, E; Emmit, R; Garza, A; Gibo, M; Hutchins, M; Perez, C; Teel, M

    2012-10-22T23:59:59.000Z

    This slide show presents work on photonic Doppler velocimetry multiplexing techniques, particularly as regards measurements on components.

  12. Tensor Principal Component Analysis via Convex Optimization

    E-Print Network [OSTI]

    Bo Jiang

    2012-12-11T23:59:59.000Z

    Dec 11, 2012 ... Keywords: Tensor; Principal Component Analysis; Low Rank; Nuclear Norm; Semidefinite Programming Relaxation. Category 1: Convex and ...

  13. Outsourcing the Design of Structural Building Components

    E-Print Network [OSTI]

    Swearingin, Adam V.

    2008-05-16T23:59:59.000Z

    component design work stateside. vi 1 Introduction The outsourcing of structural building component design has recently become available to component manufacturers in the United States. These manufacturers of metal plate connected (MPC) wood roof... of the effectiveness of outsourcing as a means of fulfilling the design requirements of MPC wood trusses. Although 1 this report does not evaluate other structural building components (i.e., i- joists, engineered wood beams and wall panels), the analysis provided...

  14. Control system health test system and method

    DOE Patents [OSTI]

    Hoff, Brian D.; Johnson, Kris W.; Akasam, Sivaprasad; Baker, Thomas M.

    2006-08-15T23:59:59.000Z

    A method is provided for testing multiple elements of a work machine, including a control system, a component, a sub-component that is influenced by operations of the component, and a sensor that monitors a characteristic of the sub-component. In one embodiment, the method is performed by the control system and includes sending a command to the component to adjust a first parameter associated with an operation of the component. Also, the method includes detecting a sensor signal from the sensor reflecting a second parameter associated with a characteristic of the sub-component and determining whether the second parameter is acceptable based on the command. The control system may diagnose at least one of the elements of the work machine when the second parameter of the sub-component is not acceptable.

  15. Drinking water treatment and distribution systems must comply with US EPA water quality regula-

    E-Print Network [OSTI]

    Fay, Noah

    Drinking water treatment and distribution systems must comply with US EPA water quality regula trihalomethanes (THMs). Drinking water providers do frequent, costly testing for THMs. Field real-time sensors PROJECT GOALS The goal of this project was to bring a team of experts in drinking water, polymers

  16. ACTUAL-WASTE TESTS OF ENHANCED CHEMICAL CLEANING FOR RETRIEVAL OF SRS HLW SLUDGE TANK HEELS AND DECOMPOSITION OF OXALIC ACID

    SciTech Connect (OSTI)

    Martino, C.; King, W.; Ketusky, E.

    2012-01-12T23:59:59.000Z

    Savannah River National Laboratory conducted a series of tests on the Enhanced Chemical Cleaning (ECC) process using actual Savannah River Site waste material from Tanks 5F and 12H. Testing involved sludge dissolution with 2 wt% oxalic acid, the decomposition of the oxalates by ozonolysis (with and without the aid of ultraviolet light), the evaporation of water from the product, and tracking the concentrations of key components throughout the process. During ECC actual waste testing, the process was successful in decomposing oxalate to below the target levels without causing substantial physical or chemical changes in the product sludge.

  17. Rapid classification of biological components

    DOE Patents [OSTI]

    Thompson, Vicki S.; Barrett, Karen B.; Key, Diane E.

    2006-01-24T23:59:59.000Z

    A method is disclosed for analyzing a biological sample by antibody profiling for identifying forensic samples or for detecting the presence of an analyte. In an illustrative embodiment of the invention, the analyte is a drug, such as marijuana, cocaine, methamphetamine, methyltestosterone, or mesterolone. The method involves attaching antigens to the surface of a solid support in a preselected pattern to form an array wherein the locations of the antigens are known; contacting the array with the biological sample such that a portion of antibodies in the sample reacts with and binds to antigens in the array, thereby forming immune complexes; washing away antibodies that do form immune complexes; and detecting the immune complexes, thereby forming an antibody profile. Forensic samples are identified by comparing a sample from an unknown source with a sample from a known source. Further, an assay, such as a test for illegal drug use, can be coupled to a test for identity such that the results of the assay can be positively correlated to the subject's identity.

  18. Rapid classification of biological components

    DOE Patents [OSTI]

    Thompson, Vicki S. (Idaho Falls, ID); Barrett, Karen B. (Meridian, ID); Key, Diane E. (Idaho Falls, ID)

    2010-03-23T23:59:59.000Z

    A method is disclosed for analyzing a biological sample by antibody profiling for identifying forensic samples or for detecting the presence of an analyte. In an illustrative embodiment of the invention, the analyte is a drug, such as marijuana, Cocaine (crystalline tropane alkaloid), methamphetamine, methyltestosterone, or mesterolone. The method involves attaching antigens of the surface of a solid support in a preselected pattern to form an array wherein the locations of the antigens are known; contacting the array with the biological sample such that a portion of antibodies in the sample reacts with and binds to antigens in the array, thereby forming immune complexes; washing away antibodies that do not form immune complexes; and detecting the immune complexes, thereby forming an antibody profile. Forensic samples are identified by comparing a sample from an unknown source with a sample from a known source. Further, an assay, such as a test for illegal drug use, can be coupled to a test for identity such that the results of the assay can be positively correlated to a subject's identity.

  19. Rapid classification of biological components

    DOE Patents [OSTI]

    Thompson, Vicki S. (Idaho Falls, ID); Barrett, Karen B. (Meridian, ID); Key, Diane E. (Idaho Falls, ID)

    2010-03-23T23:59:59.000Z

    A method is disclosed for analyzing a biological sample by antibody profiling for identifying forensic samples or for detecting the presence of an analyte. In an illustrative embodiment of the invention, the analyte is a drug, such as marijuana, cocaine (crystalline tropane alkaloid), methamphetamine, methyltestosterone, or mesterolone. The method involves attaching antigens to a surface of a solid support in a preselected pattern to form an array wherein the locations of the antigens are known; contacting the array with the biological sample such that a portion of antibodies in the sample reacts with and binds to antigens in the array, thereby forming immune complexes; washing away antibodies that do not form immune complexes; and detecting the immune complexes, thereby forming an antibody profile. Forensic samples are identified by comparing a sample from an unknown source with a sample from a known source. Further, an assay, such as a test for illegal drug use, can be coupled to a test for identity such that the results of the assay can be positively correlated to a subject's identity.

  20. Manufacturing complex silica aerogel target components

    SciTech Connect (OSTI)

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

    2008-01-01T23:59:59.000Z

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

  1. LIRMM UM II Component based Software Architecture

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 LIRMM UM II Component based Software Architecture of Robot Controllers R. Passama, D. Andreu, C component approaches and robot control architectures. This methodology defines a process that guides architecture, useful for analysis and integration, and a dedicated component-based language, focusing

  2. Principal Components Analysis for Binary Data

    E-Print Network [OSTI]

    Lee, Seokho

    2010-07-14T23:59:59.000Z

    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ix CHAPTER I INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Formulations of Principal Components Analysis . . . . . . . . 2 1.2 Generalization of Sparse Principal Components Analysis to Binary Variables... . . . . . . . . . . . . . . . . . . . . . . . . 8 1.3 Review of Estimation Procedures . . . . . . . . . . . . . . . . 11 1.4 Overview of Dissertation . . . . . . . . . . . . . . . . . . . . . 18 II SPARSE PRINCIPAL COMPONENTS ANALYSIS FOR BI- NARY DATA...

  3. Analysis of Fission Products on the AGR-1 Capsule Components

    SciTech Connect (OSTI)

    Paul A. Demkowicz; Jason M. Harp; Philip L. Winston; Scott A. Ploger

    2013-03-01T23:59:59.000Z

    The components of the AGR-1 irradiation capsules were analyzed to determine the retained inventory of fission products in order to determine the extent of in-pile fission product release from the fuel compacts. This includes analysis of (i) the metal capsule components, (ii) the graphite fuel holders, (iii) the graphite spacers, and (iv) the gas exit lines. The fission products most prevalent in the components were Ag-110m, Cs 134, Cs 137, Eu-154, and Sr 90, and the most common location was the metal capsule components and the graphite fuel holders. Gamma scanning of the graphite fuel holders was also performed to determine spatial distribution of Ag-110m and radiocesium. Silver was released from the fuel components in significant fractions. The total Ag-110m inventory found in the capsules ranged from 1.2×10 2 (Capsule 3) to 3.8×10 1 (Capsule 6). Ag-110m was not distributed evenly in the graphite fuel holders, but tended to concentrate at the axial ends of the graphite holders in Capsules 1 and 6 (located at the top and bottom of the test train) and near the axial center in Capsules 2, 3, and 5 (in the center of the test train). The Ag-110m further tended to be concentrated around fuel stacks 1 and 3, the two stacks facing the ATR reactor core and location of higher burnup, neutron fluence, and temperatures compared with Stack 2. Detailed correlation of silver release with fuel type and irradiation temperatures is problematic at the capsule level due to the large range of temperatures experienced by individual fuel compacts in each capsule. A comprehensive Ag 110m mass balance for the capsules was performed using measured inventories of individual compacts and the inventory on the capsule components. For most capsules, the mass balance was within 11% of the predicted inventory. The Ag-110m release from individual compacts often exhibited a very large range within a particular capsule.

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

    DOE Patents [OSTI]

    Sikka, Vinod K. (Oak Ridge, TN); Whitson, Barry G. (Corryton, TN); Blue, Craig A. (Knoxville, TN)

    1999-01-01T23:59:59.000Z

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

  5. Gas Test Loop Booster Fuel Hydraulic Testing

    SciTech Connect (OSTI)

    Gas Test Loop Hydraulic Testing Staff

    2006-09-01T23:59:59.000Z

    The Gas Test Loop (GTL) project is for the design of an adaptation to the Advanced Test Reactor (ATR) to create a fast-flux test space where fuels and materials for advanced reactor concepts can undergo irradiation testing. Incident to that design, it was found necessary to make use of special booster fuel to enhance the neutron flux in the reactor lobe in which the Gas Test Loop will be installed. Because the booster fuel is of a different composition and configuration from standard ATR fuel, it is necessary to qualify the booster fuel for use in the ATR. Part of that qualification is the determination that required thermal hydraulic criteria will be met under routine operation and under selected accident scenarios. The Hydraulic Testing task in the GTL project facilitates that determination by measuring flow coefficients (pressure drops) over various regions of the booster fuel over a range of primary coolant flow rates. A high-fidelity model of the NW lobe of the ATR with associated flow baffle, in-pile-tube, and below-core flow channels was designed, constructed and located in the Idaho State University Thermal Fluids Laboratory. A circulation loop was designed and constructed by the university to provide reactor-relevant water flow rates to the test system. Models of the four booster fuel elements required for GTL operation were fabricated from aluminum (no uranium or means of heating) and placed in the flow channel. One of these was instrumented with Pitot tubes to measure flow velocities in the channels between the three booster fuel plates and between the innermost and outermost plates and the side walls of the flow annulus. Flow coefficients in the range of 4 to 6.5 were determined from the measurements made for the upper and middle parts of the booster fuel elements. The flow coefficient for the lower end of the booster fuel and the sub-core flow channel was lower at 2.3.

  6. Computerized Waters

    E-Print Network [OSTI]

    Wythe, Kathy

    2006-01-01T23:59:59.000Z

    - ing 2002?2005 and documented in TWRI?s Technical Report 284 released in January 2006, include: ? Capabilities for short-term reliability analyses based on current storage conditions (Or what is the likelihood of meeting water needs in the near... System Reference Manual. TWRI Technical Report 255, Second Edition, April 2005. ? Water Rights Analysis Package Modeling System Users Manual. TWRI Technical Report 256, Second Edition, April 2005. ? Fundamentals of Water Availability Modeling...

  7. Water Quality

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

    which can lead to public health problems. * MtBE (Methyl tert Butyl Ether), a gasoline additive, has begun to contaminate ground water supplies. * Similarly, perchlorate has...

  8. Water Management

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

    Water Management This department applies multi-disciplinary science and technology-based modeling to assess complex environmental systems. It integrates ecology, anthropology, and...

  9. Component acquisition and single-source vendor management strategy in a defense application

    E-Print Network [OSTI]

    Hammer, Lory (Lory Yeamans)

    2009-01-01T23:59:59.000Z

    Building an aircraft carrier is one of the most complex manufacturing undertakings in the world. Each component must be designed, tested and manufactured to not only Northrop Grumman Shipbuilding's (NGSB) exceptionally ...

  10. Fine and coarse components in surface sediments from Bikini Lagoon

    SciTech Connect (OSTI)

    Noshkin, V. E., LLNL

    1997-01-01T23:59:59.000Z

    In 1979, 21 years after the moratorium on nuclear testing in the Marshall Islands, surface sediment samples (to depths of 2 and 4 cm) were collected from 87 locations in the lagoon of Bikini Atoll, one of the two sites in the Marshall Islands used by the United States to test nuclear devices from 1946 through 1958. The main purpose for the collections was to map the distribution of long-lived man-made radionuclides associated with the bottom material. In addition the samples were processed to estimate the fraction of fine and coarse components to show, by comparison, what modifications occurred in the composition since the sediments were first described in samples collected before testing in 1946. Nuclear testing produced more finely divided material that is now found in the surface sediment layer over large areas of the lagoon and especially in regions of the lagoon and reef adjacent to test sites. The 5 cratering events alone at Bikini Atoll redistributed sufficient material to account for the higher inventory of fine material found over the surface 4 cm of the sediment of the lagoon. Although the fraction of fine material in the bottom sediments was altered by the nuclear events, the combined processes of formation, transport and deposition were not sufficiently dynamic to greatly change the general geographical features of the major sedimentary components over most of the lagoon floor.

  11. Expandable Metal Liner For Downhole Components

    DOE Patents [OSTI]

    Hall, David R. (Provo, UT); Fox, Joe R. (Provo, UT)

    2004-10-05T23:59:59.000Z

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

  12. Dark Energy from "Water"

    E-Print Network [OSTI]

    Holman, R; Holman, Richard; Naidu, Siddartha

    2004-01-01T23:59:59.000Z

    We propose a new equation of state for the Dark Energy component of the Universe. It is modeled on the equation of state $p=w(\\rho-\\rho_{*})$ which can describe a liquid, for example water. We show that its energy density naturally decomposes into a component that behaves as a cosmological constant and one whose energy density scales as $a^{-3(1+w)}$, and fit the parameters specifying the equation of state to the new SNIa data, as well as WMAP and 2dF data. We find that reasonable values of the parameters can be found that give our model the same $\\chi^2$ as that of $\\Lambda$CDM. A remarkable feature of the model is that we can do all this with $w>0$.

  13. STATEMENT OF CONSIDERATIONS Advance Test Reactor Class Waiver

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

    Advance Test Reactor Class Waiver W(C)-2008-004 The Advanced Test Reactor (A TR) is a pressurized water test reactor at the Idaho National Laboratory (INL) that operates at low...

  14. Efficient speaker verification using Gaussian mixture model component clustering.

    SciTech Connect (OSTI)

    De Leon, Phillip L. (New Mexico State University, Las Cruces, NM); McClanahan, Richard D.

    2012-04-01T23:59:59.000Z

    In speaker verification (SV) systems that employ a support vector machine (SVM) classifier to make decisions on a supervector derived from Gaussian mixture model (GMM) component mean vectors, a significant portion of the computational load is involved in the calculation of the a posteriori probability of the feature vectors of the speaker under test with respect to the individual component densities of the universal background model (UBM). Further, the calculation of the sufficient statistics for the weight, mean, and covariance parameters derived from these same feature vectors also contribute a substantial amount of processing load to the SV system. In this paper, we propose a method that utilizes clusters of GMM-UBM mixture component densities in order to reduce the computational load required. In the adaptation step we score the feature vectors against the clusters and calculate the a posteriori probabilities and update the statistics exclusively for mixture components belonging to appropriate clusters. Each cluster is a grouping of multivariate normal distributions and is modeled by a single multivariate distribution. As such, the set of multivariate normal distributions representing the different clusters also form a GMM. This GMM is referred to as a hash GMM which can be considered to a lower resolution representation of the GMM-UBM. The mapping that associates the components of the hash GMM with components of the original GMM-UBM is referred to as a shortlist. This research investigates various methods of clustering the components of the GMM-UBM and forming hash GMMs. Of five different methods that are presented one method, Gaussian mixture reduction as proposed by Runnall's, easily outperformed the other methods. This method of Gaussian reduction iteratively reduces the size of a GMM by successively merging pairs of component densities. Pairs are selected for merger by using a Kullback-Leibler based metric. Using Runnal's method of reduction, we were able to achieve a factor of 2.77 reduction in a posteriori probability calculations with no loss in accuracy when the original UBM consisted of 256 component densities. When clustering was implemented with a 1024 component UBM, we achieved a computation reduction of 5 with no loss in accuracy and a reduction by a factor of 10 with less than 2.4% relative loss in accuracy.

  15. The waste water free coke plant

    SciTech Connect (OSTI)

    Schuepphaus, K.; Brink, N. [Thyssen Still Otto Anlagentechnik GmbH, Bochum (Germany)

    1995-12-01T23:59:59.000Z

    Apart from coke which is the actual valuable material a coke oven plant also produces a substantial volume of waste water. These effluent water streams are burdened with organic components (e.g. phenols) and inorganic salts (e.g. NH{sub 4}Cl); due to the concentration of the constituents contained therein these effluent waters must be subjected to a specific treatment before they can be introduced into public waters. For some years a lot of separation tasks have been solved successfully by applying the membrane technology. It was especially the growing number of membrane facilities for cleaning of landfill leakage water whose composition can in fact be compared with that of coking plant waste waters (organic constituents, high salt fright, ammonium compounds) which gave Thyssen Still Otto Anlagentechnik the idea for developing a process for coke plant effluent treatment which contains the membrane technology as an essential component.

  16. Hydrogeologic investigations at the Nevada Test Site

    SciTech Connect (OSTI)

    Hawkins, W L [Los Alamos National Lab., NM (United States)] [Los Alamos National Lab., NM (United States); Trudeau, D A [Geological Survey, Las Vegas, NV (United States)] [Geological Survey, Las Vegas, NV (United States); Drellack, S L [Raytheon Services Nevada, Inc., Mercury, NV (United States)] [Raytheon Services Nevada, Inc., Mercury, NV (United States)

    1992-01-01T23:59:59.000Z

    The Nevada Test Site was established in 1950 as a continental area for testing nuclear devices and, since 1963, all nuclear detonations there have been underground. Most tests are conducted in vertical shafts with a small percentage conducted in tunnels. The majority of detonation points are above the water table, primarily in volcanic rocks or alluvium. In the testing areas the water table is 450--700 m below the surface. Pre- and post- event geologic investigations are conducted for each test location and long-term studies assess the impact of underground testing on a more regional scale. Studies in progress have not identified any impact on the regional ground water system from testing, but some local effects have been recognized. In some areas where several large tests have been conducted below the water table, water levels hundreds of meters above the regional water table have been measured and radioactivity has been discovered associated with fractures in a few holes. Flow-through and straddle packer testing has revealed unexpectedly high hydraulic pressures at depth. Recently, a multiple completion monitoring well installed to study three zones has confirmed the existence of a significant upward hydraulic gradient. These observations of local pressurization and fracture flow are being further explored to determine the influence of underground nuclear testing on the regional hydrogeologic system.

  17. Comparison of Recuperator Alloy Degradation in Laboratory and Engine Testing

    SciTech Connect (OSTI)

    Pint, Bruce A [ORNL; More, Karren Leslie [ORNL; Trejo, Rosa M [ORNL; Lara-Curzio, Edgar [ORNL

    2006-01-01T23:59:59.000Z

    In order to increase the efficiency of advanced microturbines, durable alloy foils are needed for their recuperators to operate at 650-700 C. Prior work has demonstrated that water vapor in the exhaust gas causes more rapid consumption of Cr from austenitic alloys, leading to a reduction in lifetime for the thin-walled components in this application. New commercial alloy foils are being tested in both laboratory tests in humid air and in the exhaust gas of a modified 60 kW microturbine. Initial results are presented for a commercial batch of 80 {micro}m alloy 120 foil. The Cr consumption rates in laboratory testing were similar to those observed in previous testing. The initial results from the microturbine indicate a faster Cr consumption rate compared to the laboratory test, but longer term results are needed to quantify the difference. These results will help to verify a Cr consumption model for predicting lifetimes in this environment based on classical gas transport theory.

  18. Testing and analysis of structural steel columns subjected to blast loads

    E-Print Network [OSTI]

    Stewart, Lauren K.

    2010-01-01T23:59:59.000Z

    Blast Simulator Testing of Steel Columns and Components. ”Testing of Structural Steel Columns. ” 8 th Internationaland Analysis of Structural Steel Columns Subjected to Blast

  19. Fuel Cell Development and Test Laboratory (Fact Sheet), NREL...

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

    Fuel Cell Development and Test Laboratory may include: * Fuel cell and fuel cell component manufacturers * Certification laboratories * Government agencies * Universities * Other...

  20. A comprehensive approach for stimulating produced water injection wells at Prudhoe Bay, Alaska

    SciTech Connect (OSTI)

    Fambrough, J.D.; Lane, R.H.; Braden, J.C.

    1995-11-01T23:59:59.000Z

    The paper presents a three-component approach to removing damage from produced water injection wells of Prudhoe Bay Field, Alaska: (1) identification of plugging material, (2) evaluation and selection of potential treatment chemicals, and (3) design and implementation of a well treatment and placement method. Plugging material was sampled anaerobically and kept frozen prior to identification and evaluation. Appropriate treatment chemicals were determined through a series of solvation, filtration, and weight-loss tests. Field treatments were designed so that the treating chemicals entered the formation under normal operating conditions, i.e., at pressures and rates similar to those present during produced water injection. A number of treatments improved injection rates and profiles, but continued injection of oil and solids-laden water caused deterioration of well performance at rates that precluded general application of the treatment at Prudhoe Bay.

  1. Membrane Desalination of Agricultural Drainage Water: Water Recovery Enhancement and Brine Minimization

    E-Print Network [OSTI]

    Cohen, Yoram

    2008-01-01T23:59:59.000Z

    Pilot-scale testing of reverse osmosis using conventionalY. Cohen, High- Recovery Reverse Osmosis Using IntermediateUltra-Low Pressure Reverse Osmosis for Surface Water

  2. Two Component Model of Dark Energy

    E-Print Network [OSTI]

    Yan Gong; Xuelei Chen

    2007-10-18T23:59:59.000Z

    We consider the possibility that the dark energy is made up of two or more independent components, each having a different equation of state. We fit the model with supernova and gamma-ray burst (GRB) data from resent observations, and use the Markov Chain Monte Carlo (MCMC) technique to estimate the allowed parameter regions. We also use various model selection criteria to compare the two component model with the LCDM, one component dark energy model with static or variable w(XCDM), and with other multi-component models. We find that the two component models can give reasonably good fit to the current data. For some data sets, and depending somewhat on the model selection criteria, the two component model can give better fit to the data than XCDM with static w and XCDM with variable w parameterized by w = w_0 + w_az/(1+z).

  3. Solid tags for identifying failed reactor components

    DOE Patents [OSTI]

    Bunch, Wilbur L. (Richland, WA); Schenter, Robert E. (Richland, WA)

    1987-01-01T23:59:59.000Z

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

  4. Physics-Based Stress Corrosion Cracking Component Reliability Model cast in an R7-Compatible Cumulative Damage Framework

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Lowry, Peter P.; Layton, Robert F.; Toloczko, Mychailo B.; Johnson, Kenneth I.; Sanborn, Scott E.

    2011-07-01T23:59:59.000Z

    This is a working report drafted under the Risk-Informed Safety Margin Characterization pathway of the Light Water Reactor Sustainability Program, describing statistical models of passives component reliabilities.

  5. Uranium Weapons Components Successfully Dismantled | National...

    National Nuclear Security Administration (NNSA)

    Successfully Dismantled March 20, 2007 Uranium Weapons Components Successfully Dismantled Oak Ridge, TN Continuing its efforts to reduce the size of the U.S. nuclear weapons...

  6. Developing Language Processing Components with GATE

    E-Print Network [OSTI]

    Maynard, Diana

    Developing Language Processing Components with GATE (a User Guide) For GATE version 3 beta 1 (July.3 Troubleshooting . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 3.4 [D] Get Started

  7. South Atlantic sag basins: new petroleum system components

    SciTech Connect (OSTI)

    Henry, S.G. [GeoLearn, Houston, TX (United States)] Mohriak, W.U. [Petroleo Brasileiro, S.A., Exploration and Production, Rio de Janeiro (Brazil); Mello, M.R. [Petroleo Brasieiro, S.A., Research Center, Rio de Janeiro (Brazil)

    1996-08-01T23:59:59.000Z

    Newly discovered pre-salt source rocks, reservoirs and seals need to be included as components to the petroleum systems of both sides of the South Atlantic. These new components lie between the pre-salt rift strata and the Aptian salt layers, forming large, post-rift, thermal subsidence sag basins. These are differentiated from the older rift basins by the lack of syn-rift faulting and a reflector geometry that is parallel to the base salt regional unconformity rather than to the Precambrian basement. These basins are observed in deep water regions overlying areas where both the mantle and the crust have been involved in the extension. This mantle involvement creates post-rift subsiding depocenters in which deposition is continuous while proximal rift-phase troughs with little or no mantle involvement are bypassed and failed to accumulate potential source rocks during anoxic times. These features have been recognized in both West African Kwanza Basin and in the East Brasil Rift systems. The pre-salt source rocks that are in the West African sag basins were deposited in lacustrine brackish to saline water environment and are geochemically distinct from the older, syn-rift fresh to brackish water lakes, as well as from younger, post-salt marine anoxic environments of the drift phase. Geochemical analyses of the source rocks and their oils have shown a developing source rock system evolving from isolated deep rift lakes to shallow saline lakes, and culminating with the infill of the sag basin by large saline lakes to a marginally marine restricted gulf. Sag basin source rocks may be important in the South Atlantic petroleum system by charging deep-water prospects where syn-rift source rocks are overmature and the post-salt sequences are immature.

  8. Modeling blue and green water availability in Africa Jurgen Schuol,1,2

    E-Print Network [OSTI]

    Modeling blue and green water availability in Africa Ju¨rgen Schuol,1,2 Karim C. Abbaspour,1 Hong a semidistributed hydrological model SWAT (Soil and Water Assessment Tool), the freshwater components blue water. J. B. Zehnder (2008), Modeling blue and green water availability in Africa, Water Resour. Res., 44

  9. Investigating Water

    E-Print Network [OSTI]

    Howard Jr., Ronald A.

    2002-01-02T23:59:59.000Z

    ........................................................................................... 193 Lesson 11 Water and Pollution........................................................................................................................ 195 Activity 11.1, Pollution, Pollution, Everywhere...! ............................................................................. 205 Record Sheet 11.1, Pollution, Pollution, Everywhere! ..................................................................... 207 Activity 11.2, Pollution at Its Source...

  10. Water Privatisation 

    E-Print Network [OSTI]

    Zölls, Elisa

    2011-08-17T23:59:59.000Z

    This dissertation deals with the policy issues of large-scale, urban water privatisation projects in the face of uncertainty and variability. The main objective is to evaluate whether a single policy approach, namely privatisation associated...

  11. Test Comparability

    E-Print Network [OSTI]

    Keller, Christine; Shulenburger, David E.

    2010-01-01T23:59:59.000Z

    KU ScholarWorks | http://kuscholarworks.ku.edu Test Comparability 2010 by Christine Keller and David Shulenburger This work has been made available by the University of Kansas Libraries’ Office of Scholarly Communication and Copyright. Please... and Shulenburger, David. “Test comparability,” with Christine Keller in the Letters section of Change, September/October 2010, p. 6. Published version: http://www.changemag.org/Archives/Back%20 Issues/September-October%202010/letters-to-editor.html Terms of Use...

  12. Thermal well-test method

    DOE Patents [OSTI]

    Tsang, C.F.; Doughty, C.A.

    1984-02-24T23:59:59.000Z

    A well-test method involving injection of hot (or cold) water into a groundwater aquifer, or injecting cold water into a geothermal reservoir is disclosed. By making temperature measurements at various depths in one or more observation wells, certain properties of the aquifer are determined. These properties, not obtainable from conventional well test procedures, include the permeability anisotropy, and layering in the aquifer, and in-situ thermal properties. The temperature measurements at various depths are obtained from thermistors mounted in the observation wells.

  13. Test Planning and Test Resource Optimization for Droplet-Based Microfluidic Systems*

    E-Print Network [OSTI]

    Chakrabarty, Krishnendu

    Test Planning and Test Resource Optimization for Droplet-Based Microfluidic Systems* Fei Su, Sule of droplet- based microfluidic systems for safety-critical biomedical applications. In order to ensure reliability, microsystems incorporating microfluidic components must be tested adequately. In this paper, we

  14. Water Heaters and Hot Water Distribution Systems

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    24 Figure 7. Comparison of Daily Water Heater28 Figure 8. Monitored Field Efficiency of Tankless Water28 Figure 9. Monitored Lab Efficiency of Tankless Water

  15. Water Heaters and Hot Water Distribution Systems

    E-Print Network [OSTI]

    Lutz, Jim

    2012-01-01T23:59:59.000Z

    Gas-fired Storage Water Heater .. 418 Assess California’s Small Gas Storage Water Heaters Small Gas Storage Water Heater Market The objective of

  16. Software Testing and Maintenance 1 Regression Testing

    E-Print Network [OSTI]

    Lei, Jeff Yu

    1 Software Testing and Maintenance 1 Regression Testing Introduction Test Selection Test Minimization Test Prioritization Summary Software Testing and Maintenance 2 What is it? Regression testing refers to the portion of the test cycle in which a program is tested to ensure that changes do not affect

  17. Test Automation Ant JUnit Test Automation

    E-Print Network [OSTI]

    Mousavi, Mohammad

    Test Automation Ant JUnit Test Automation Mohammad Mousavi Eindhoven University of Technology, The Netherlands Software Testing 2012 Mousavi: Test Automation #12;Test Automation Ant JUnit Outline Test Automation Ant JUnit Mousavi: Test Automation #12;Test Automation Ant JUnit Why? Challenges of Manual Testing

  18. The water solubility of naphthenes

    SciTech Connect (OSTI)

    Yaws, C.L.; Lin, Xiaoyan; Bu, Li (Lamar Univ., Beaumont, TX (United States))

    1993-10-01T23:59:59.000Z

    Naphthenes, like paraffins and aromatics, are a major component of unrefined fuels. Like these other hydrocarbons, naphthenes' solubility in water is of critical importance to engineers, particularly vis-a-vis the environmental hazard they present when spilled in water. Naphthenes' water solubility is described as a function of temperature. The correlation constants are displayed in an easy-to-use tabular format, which is especially applicable for rapid engineering usage with the personal computer or hand calculator. These data are applicable for a temperature range of 25--120 C, encountered in air and steam-stripping operations. An engineer can use the data to assess the distribution of a hydrocarbon spill in water, i.e., by determining the amount of dissolved naphthenes. Solubility values at ambient temperature, as well as higher-temperature values can be ascertained from the correlation.

  19. Hybrid solar lighting distribution systems and components

    DOE Patents [OSTI]

    Muhs, Jeffrey D. (Lenoir City, TN); Earl, Dennis D. (Knoxville, TN); Beshears, David L. (Knoxville, TN); Maxey, Lonnie C. (Powell, TN); Jordan, John K. (Oak Ridge, TN); Lind, Randall F. (Lenoir City, TN)

    2011-07-05T23:59:59.000Z

    A hybrid solar lighting distribution system and components having at least one hybrid solar concentrator, at least one fiber receiver, at least one hybrid luminaire, and a light distribution system operably connected to each hybrid solar concentrator and each hybrid luminaire. A controller operates all components.

  20. Hybrid solar lighting systems and components

    DOE Patents [OSTI]

    Muhs, Jeffrey D. (Lenoir City, TN); Earl, Dennis D. (Knoxville, TN); Beshears, David L. (Knoxville, TN); Maxey, Lonnie C. (Powell, TN); Jordan, John K. (Oak Ridge, TN); Lind, Randall F. (Lenoir City, TN)

    2007-06-12T23:59:59.000Z

    A hybrid solar lighting system and components having at least one hybrid solar concentrator, at least one fiber receiver, at least one hybrid luminaire, and a light distribution system operably connected to each hybrid solar concentrator and each hybrid luminaire. A controller operates each component.